Contrast media. Safety issues and ESUR guidelines

International Nuclear Information System (INIS)

Thomsen, H.S.

2006-01-01

In 1994 the European Society of Urogenital Radiology (ESUR) set up a committee to consider the safety of the contrast media used in radiology departments. Since then, the committee has questioned members, reviewed the literature, proposed guidelines, and discussed these proposals with participants at the annual symposia on urogenital radiology. This book represents the end result of this hard work. It contains all of the agreed guidelines, updated when necessary, and thereby comprehensively covers the many different safety issues relating to the diverse contrast media: barium contrast media, iodinated contrast media, MR contrast media (both gadolinium-based extracellular and organ-specific) and ultrasound contrast media. The prevention and treatment of both acute and delayed non-renal adverse reactions as well as the renal adverse reactions are covered in detail. The inclusion of all the ESUR guidelines within one book will offer an invaluable, unique and unparalleled resource. (orig.)

Guidelines for the Layout and Contents of Safety Reports for Stationary Nuclear Power Plants

International Nuclear Information System (INIS)

1970-01-01

The purpose of the present document is to suggest guidelines for the organization and contents of the Safety Reports which support the request for authorization to construct and operate a nuclear power plant incorporating one or more reactors. Safety Reports represent the principal communication between the applicant and the Regulatory Body, as outlined in the Code of Practice for the Safe Operation of Nuclear Power Plants. It should be understood that these Safety Reports will be a valuable document for the applicant. They should contain, therefore, precise information on the plant and its operating conditions. The writing of Safety Reports should be considered an opportunity to enhance the safety of the plant and its operating conditions. Their main purpose is to provide information to permit the assessment of the nuclear safety implications which may arise from the establishment of the plant at the chosen site with due consideration to the health and safety of the general public and the operating personnel. Safety Reports should include information such as design bases, site and plant characteristics, limits and conditions, conduct of operation and safety analyses, in such way that the Regulatory Body may be able to evaluate the safety of the plant. The applicant should consider the present guidelines as a series of recommendations to be interpreted according to each specific case.

Methodology for calculating guideline concentrations for safety shot sites

International Nuclear Information System (INIS)

1997-06-01

Residual plutonium (Pu), with trace quantities of depleted uranium (DU) or weapons grade uranium (WU), exists in surficial soils at the Nevada Test Site (NTS), Nellis Air Force Range (NAFR), and the Tonopah Test Range (TTR) as the result of the above-ground testing of nuclear weapons and special experiments involving the detonation of plutonium-bearing devices. The special experiments (referred to as safety shots) involving plutonium-bearing devices were conducted to study the behavior of Pu as it was being explosively compressed; ensure that the accidental detonation of the chemical explosive in a production weapon would not result in criticality; evaluate the ability of personnel to manage large-scale Pu dispersal accidents; and develop criteria for transportation and storage of nuclear weapons. These sites do not pose a health threat to either workers or the general public because they are under active institutional control. The DOE is committed to remediating the safety shot sites so that radiation exposure to the public, both now and in the future, will be maintained within the established limits and be as low as reasonably achievable. Remediation requires calculation of a guideline concentration for the Pu, U, and their decay products that are present in the surface soil. This document presents the methodology for calculating guideline concentrations of weapons grade plutonium, weapons grade uranium, and depleted uranium in surface soils at the safety shot sites. Emphasis is placed on obtaining site-specific data for use in calculating dose to potential residents from the residual soil contamination

Methodology for calculating guideline concentrations for safety shot sites

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-06-01

Residual plutonium (Pu), with trace quantities of depleted uranium (DU) or weapons grade uranium (WU), exists in surficial soils at the Nevada Test Site (NTS), Nellis Air Force Range (NAFR), and the Tonopah Test Range (TTR) as the result of the above-ground testing of nuclear weapons and special experiments involving the detonation of plutonium-bearing devices. The special experiments (referred to as safety shots) involving plutonium-bearing devices were conducted to study the behavior of Pu as it was being explosively compressed; ensure that the accidental detonation of the chemical explosive in a production weapon would not result in criticality; evaluate the ability of personnel to manage large-scale Pu dispersal accidents; and develop criteria for transportation and storage of nuclear weapons. These sites do not pose a health threat to either workers or the general public because they are under active institutional control. The DOE is committed to remediating the safety shot sites so that radiation exposure to the public, both now and in the future, will be maintained within the established limits and be as low as reasonably achievable. Remediation requires calculation of a guideline concentration for the Pu, U, and their decay products that are present in the surface soil. This document presents the methodology for calculating guideline concentrations of weapons grade plutonium, weapons grade uranium, and depleted uranium in surface soils at the safety shot sites. Emphasis is placed on obtaining site-specific data for use in calculating dose to potential residents from the residual soil contamination.

43 CFR 4.100 - General rules and guidelines.

Science.gov (United States)

2010-10-01

... 43 Public Lands: Interior 1 2010-10-01 2010-10-01 false General rules and guidelines. 4.100... rules and guidelines. (a) Effective date and applicability—(1) Effective date and general applicability..., in which event the period shall run to the end of the next business day. (e) General guidelines—(1...

Guidelines for computer security in general practice.

Science.gov (United States)

Schattner, Peter; Pleteshner, Catherine; Bhend, Heinz; Brouns, Johan

2007-01-01

As general practice becomes increasingly computerised, data security becomes increasingly important for both patient health and the efficient operation of the practice. To develop guidelines for computer security in general practice based on a literature review, an analysis of available information on current practice and a series of key stakeholder interviews. While the guideline was produced in the context of Australian general practice, we have developed a template that is also relevant for other countries. Current data on computer security measures was sought from Australian divisions of general practice. Semi-structured interviews were conducted with general practitioners (GPs), the medical software industry, senior managers within government responsible for health IT (information technology) initiatives, technical IT experts, divisions of general practice and a member of a health information consumer group. The respondents were asked to assess both the likelihood and the consequences of potential risks in computer security being breached. The study suggested that the most important computer security issues in general practice were: the need for a nominated IT security coordinator; having written IT policies, including a practice disaster recovery plan; controlling access to different levels of electronic data; doing and testing backups; protecting against viruses and other malicious codes; installing firewalls; undertaking routine maintenance of hardware and software; and securing electronic communication, for example via encryption. This information led to the production of computer security guidelines, including a one-page summary checklist, which were subsequently distributed to all GPs in Australia. This paper maps out a process for developing computer security guidelines for general practice. The specific content will vary in different countries according to their levels of adoption of IT, and cultural, technical and other health service factors. Making

Development of safety evaluation guidelines for base-isolated buildings in Japan

International Nuclear Information System (INIS)

Aoyama, Hiroyuki

1989-01-01

This paper describes the safety evaluation guidelines and the review process for non-nuclear base-isolated buildings proposed for construction in Japan. The paper discusses the guidelines application for two types of soil: hard soil and intermediate soil (soft soil was excluded.); safety evaluation items included in the level C design review; and safety margin of base isolation. Lessons learned through these design review efforts have potential applicability to design of seismic base isolation for nuclear power plants

Characteristics of effective clinical guidelines for general practice.

NARCIS (Netherlands)

Burgers, J.S.; Grol, R.P.T.M.; Zaat, J.O.M.; Spies, T.H.; Bij, A.K. van der; Mokkink, H.G.A.

2003-01-01

BACKGROUND: The use of clinical guidelines in general practice is often limited. Research on barriers to guideline adherence usually focuses on attitudinal factors. Factors linked to the guideline itself are much less studied. AIM: To identify characteristics of effective clinical guidelines for

OSART Independent Safety Culture Assessment (ISCA) Guidelines

International Nuclear Information System (INIS)

2016-01-01

Safety culture is understood as an important part of nuclear safety performance. This has been demonstrated by the analysis of significant events such as Chernobyl, Davis Besse, Vandellos II, Asco, Paks, Mihamma and Forsmark, among others. In order to enhance safety culture, one essential activity is to perform assessments. IAEA Safety Standard Series No. GS-R-3, The Management System for Facilitites and Activities, states requirements for continuous improvement of safety culture, of which self, peer and independent safety culture assessments constitute an essential part. In line with this requirement, the Independent Safety Culture Assessment (ISCA) module is offered as an add-on module to the IAEA Operational Safety Review Team (OSART) programme. The OSART programme provides advice and assistance to Member States to enhance the safety of nuclear power plants during commissioning and operation. By including the ISCA module in an OSART mission, the receiving organization benefits from the synergy between the technical and the safety culture aspects of the safety review. The joint operational safety and safety culture assessment provides the organization with the opportunity to better understand the interactions between technical, human, organizational and cultural aspects, helping the organization to take a systemic approach to safety through identifying actions that fully address the root causes of any identified issue. Safety culture assessments provide insight into the fundamental drivers that shape organizational patterns of behaviour, safety consciousness and safety performance. The complex nature of safety culture means that the analysis of the results of such assessments is not as straightforward as for other types of assessment. The benefits of the results of nuclear safety culture assessments are maximized only if appropriate tools and guidance for these assessments is used; hence, this comprehensive guideline has been developed. The methodology explained

EM Health and Safety Plan Guidelines

Energy Technology Data Exchange (ETDEWEB)

1994-12-01

This document contains information about the Health and Safety Plan Guidelines. Topics discussed include: Regulatory framework; key personnel; hazard assessment; training requirements; personal protective equipment; extreme temperature disorders or conditions; medical surveillance; exposure monitoring/air sampling; site control; decontamination; emergency response/contingency plan; emergency action plan; confined space entry; and spill containment.

Best-practices guidelines for L2PSA development and applications. Volume 1 - General

International Nuclear Information System (INIS)

Raimond, E.; Pichereau, F.; Durin, T.; Rahni, N.; Loeffler, H.; Roesch, O.; Lajtha, G.; Santamaria, C.S.; Dienstbier, J.; Rydl, A.; Holmberg, J.E.; Lindholm, I.; Maennistoe, I.; Pauli, E.M.; Dirksen, G.; Grindon, L.; Peers, K.; Bassi, C.; Hulqvist, G.; Parozzi, F.; Polidoro, F.; Cazzoli, E.; Vitazkova, J.; Burgazzi, L.; Brinkman, H.; Seidel, A.; Schubert, B.; Wohlstein, R.; Guentay, S.; Oury, L.; Ngatchou, C.; Siltanen, S.; Niemela, I.; Routamo, T.; Vincon, L.; Helstroem, P.

2010-01-01

The objective of this coordinated action was to develop best practice guidelines for the performance and application of Level 2 PSA with a view to achieve harmonisation at EU level and to allow a meaningful and practical uncertainty evaluation in a Level 2 PSA. Specific relationships with communities in charge of nuclear reactor safety (utilities, safety authorities, vendors, and research or services companies) have been established in order to define the current needs in terms of guidelines for Level 2 PSA development and application. An international workshop was organised in Hamburg, with the support of VATTENFALL, in November 2008. The Level 2 PSA experts from ASAMPSA2 project partners have proposed some guidelines for the development and application of L2PSA based on their experience, open literature, and on information available from international cooperation (EC Severe Accident network of Excellence - SARNET, IAEA standards, OECD-NEA publications and workshop). There are a large number of technical issues addressed in the guideline which are not all covered with the same level of detail in the first version of the guideline. This version was submitted for external review in November 2010 by severe accident and PSA experts (especially from SARNET and OECD-NEA members). The feedback of the external review will be dis cussed during an international open works hop planned for March 2011 and all outcomes will be taken into consideration in the final version of this guideline (June 2011). The guideline includes 3 volumes: - Volume 1 - General considerations on L2PSA. - Volume 2 - Technical recommendations for Gen II and III reactors. - Volume 3 - Specific considerations for future reactors (Gen IV). The recommendations formulated in the guideline should not be considered as 'mandatory' but should help Level 2 PSA developers to achieve high quality studies with limited time and resources. It may also help Level 2 PSA reviewers by positioning one specific study in

Development of Manitoba Hydro's public water safety around dams management guidelines

Energy Technology Data Exchange (ETDEWEB)

Bonin, Dave; McPhail, Gord; Murphy, Shayla; Schellenberg, Gord [KGS Acres, Winnipeg, (Canada); Read, Nick [Manitoba Hydro, Winnipeg, (Canada)

2010-07-01

Several drowning fatalities and safety incidents have occurred around dams in Ontario, Manitoba and other jurisdictions in Canada. Following these incidents, Manitoba Hydro implemented several measures to improve public safety around its dams with the development of a warning signs manual. Manitoba Hydro found that a standard centralized approach to the process of improving public safety is better for ensuring compliance and consistency, even though they have safety measures in place. This paper described the process that Manitoba Hydro has followed in developing a formal set of public water safety around dams (PWSD) guidelines and a program for implementing these guidelines. This program was developed with the intent of providing a high standard of public protection and continuous improvement and monitoring on par with the effect spent on similar dam safety type programs. This paper focused on the development of the pilot PWSD management plan for Pine Falls generating station in order to test the effectiveness and usability of the guidelines.

Adherence to cancer treatment guidelines: influence of general and cancer-specific guideline characteristics.

NARCIS (Netherlands)

Heins, M.J.; Jong, J.D. de; Spronk, I.; Ho, V.K.; Brink, M.; Korevaar, J.C.

2017-01-01

Background: Guideline adherence remains a challenge in clinical practice, despite guidelines’ ascribed potential to improve patient outcomes. We studied the level of adherence to recommendations from Dutch national cancer treatment guidelines, and the influence of general and

SALTO Peer Review Guidelines. Guidelines for Peer Review of Safety Aspects of Long Term Operation of Nuclear Power Plants

International Nuclear Information System (INIS)

2014-01-01

International peer review is a useful tool for Member States to exchange experiences, learn from each other and apply good practices in the long term operation (LTO) of nuclear power plants (NPPs). The peer review is also an important mechanism through which the IAEA supports Member States in enhancing the safety of NPPs. The IAEA has conducted various types of safety review that indirectly address aspects of LTO, including safety reviews for design, engineering, operation and external hazards. Operational Safety Review Team (OSART) services include review of ageing management programmes. In addition, several Member States have requested Ageing Management Assessment Team (AMAT) missions. Through these experiences, it was recognized that a comprehensive peer review on LTO would be very useful to Member States. The Safety Aspects of Long Term Operation (SALTO) peer review addresses strategy and key elements for the safe LTO of NPPs, which includes AMAT objectives and complements OSART reviews. The SALTO peer review is designed to assist operating organizations in adopting a proper approach to LTP including implementing appropriate activities to ensure that plant safety will be maintained during the LTO period. The SALTO peer review can be tailored to focus on ageing management programmes (AMPs) or on other activities related to LTO to support the Member State in enhancing the safety of its NPPs. The SALTO peer review can also support regulators in establishing or improving regulatory and licensing strategies for the LTO of NPPs. The guidelines in this publication are primarily intended for members of a SALTO review team and provide a basic structure and common reference for peer reviews of LTO. Additionally, the guidelines also provide useful information to the operating organizations of NPPs (or technical support organizations) for carrying out their own self-assessments or comprehensive programme reviews. The guidelines are intended to be generic, as there are

21 CFR 610.11 - General safety.

Science.gov (United States)

2010-04-01

... 21 Food and Drugs 7 2010-04-01 2010-04-01 false General safety. 610.11 Section 610.11 Food and... GENERAL BIOLOGICAL PRODUCTS STANDARDS General Provisions § 610.11 General safety. A general safety test... for administration to humans. The general safety test is required in addition to other specific tests...

Safety investigation of 'Mutsu', the first nuclear ship in Japan (the correspondence to the guideline of safety design examination, etc.)

International Nuclear Information System (INIS)

1981-01-01

Japan Nuclear Ship Development Agency had made previously application for the permission of the alteration of the reactor installation in the nuclear ship Mutsu (the first of this kind in Japan), based on the overall safety investigation of the ship made by JNDA. Taking the opportunity of the governmental safety examination concerning the permission, the correspondence of the safety aspects of the n.s. Mutsu to the existing guidelines for the safety of nuclear reactor facilities was examined. These results to further enhance the safety of the n.s. Mutsu are described concerning the following matters: the safety design examination guideline for power-generating LWR facilities (58 items); the safety evaluation guideline for power-generating LWR facilities (the analysis of abnormal transients during operation and accidents); the safety countermeasures to be adopted in the reactor plant of the n.s. Mutsu from the situation of the TMI nuclear accident in U.S. (7 in design and 10 in operation management); the analysis simulating the TMI accident. (J.P.N.)

Operational safety review programmes for nuclear power plants. Guidelines for assessment

International Nuclear Information System (INIS)

2002-01-01

The IAEA has been offering the Operational Safety Review Team (OSART) programme to provide advice and assistance to Member States in enhancing the operational safety of nuclear power plants (NPPs). Simultaneously, the IAEA has encouraged self-assessment and review by Member States of their own nuclear power plants to continuously improve nuclear safety. Currently, some utilities have been implementing safety review programmes to independently review their own plants. Corporate or national operational safety review programmes may be compliance or performance based. Successful utilities have found that both techniques are necessary to provide assurance that (i) as a minimum the NPP meets specific corporate and legal requirements and (ii) management at the NPP is encouraged to pursue continuous improvement principles. These programmes can bring nuclear safety benefits to the plants and utilities. The IAEA has conducted two pilot missions to assess the effectiveness of the operational review programme. Based on these missions and on the experience gained during OSART missions, this document has been developed to provide guidance on and broaden national/corporate safety review programmes in Member States, and to assist in maximizing their benefits. These guidelines are intended primarily for the IAEA team to conduct assessment of a national/corporate safety review programme. However, this report may also be used by a country or utility to establish its own national/corporate safety review programme. The guidelines may likewise be used for self-assessment or for establishing a baseline when benchmarking other safety review programmes. This report consists of four parts. Section 2 addresses the planning and preparation of an IAEA assessment mission and Sections 3 and 4 deal with specific guidelines for conducting the assessment mission itself

Guidelines for computer security in general practice

Directory of Open Access Journals (Sweden)

Peter Schattner

2007-06-01

Conclusions This paper maps out a process for developing computer security guidelines for general practice. The specific content will vary in different countries according to their levels of adoption of IT, and cultural, technical and other health service factors. Making these guidelines relevant to local contexts should help maximise their uptake.

Guidelines for preparing criticality safety evaluations at Department of Energy non-reactor nuclear facilities

International Nuclear Information System (INIS)

1993-11-01

This document contains guidelines that should be followed when preparing Criticality Safety Evaluations that will be used to demonstrate the safety of operations performed at DOE non-reactor nuclear facilities. Adherence to these guidelines will provide consistency and uniformity in criticality safety evaluations (CSEs) across the complex and will document compliance with the requirements of DOE Order 5480.24

Proposed Guideline Revisions for Dental Sedation and General Anesthesia: Why Target the Safest Level of Sedation?

Science.gov (United States)

Dionne, Raymond A

2016-09-01

Recently proposed revisions to the American Dental Association's Guidelines for the Use of Sedation and General Anesthesia by Dentists, aimed at improving safety in dental offices, differentiate between levels of sedation based on drug-induced changes in physiologic and behavioral states. However, the author of this op-ed is concerned the proposed revisions may have far-reaching and unintended consequences.

Measure Guideline: Combustion Safety for Natural Draft Appliances Using Indoor Air

Energy Technology Data Exchange (ETDEWEB)

Brand, L.

2014-04-01

This measure guideline covers how to assess and carry out the combustion safety procedures for appliances and heating equipment that uses indoor air for combustion in low-rise residential buildings. Only appliances installed in the living space, or in an area freely communicating with the living space, vented alone or in tandem with another appliance are considered here. A separate measure guideline addresses combustion appliances located either within the living space in enclosed closets or side rooms or outside the living space in an adjacent area like an attic or garage that use outdoor air for combustion. This document is for inspectors, auditors, and technicians working in homes where energy upgrades are being conducted whether or not air infiltration control is included in the package of measures being applied. In the indoor combustion air case, guidelines summarized here are based on language provided in several of the codes to establish minimum requirements for the space using simplified prescriptive measures. In addition, building performance testing procedures are provided by testing agencies. The codes in combination with the test procedures offer comprehensive combustion safety coverage to address safety concerns, allowing inexperienced residential energy retrofit inspectors to effectively address combustion safety issues and allow energy retrofits to proceed.

Guidelines for preparing criticality safety evaluations at Department of Energy non-reactor nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-09-01

This Department of Energy (DOE) is approved for use by all components of DOE. It contains guidelines that should be followed when preparing Criticality Safety Evaluations that will be used to demonstrate the safety of operations performed at DOE Non-Reactor Nuclear Facilities. Adherence with these guidelines will provide consistency and uniformity in Criticality Safety Evaluations (CSEs) across the complex and will document compliance with DOE Order 5480.24 requirements as they pertain to CSEs.

Guidelines for preparing criticality safety evaluations at Department of Energy non-reactor nuclear facilities

International Nuclear Information System (INIS)

1998-09-01

This Department of Energy (DOE) is approved for use by all components of DOE. It contains guidelines that should be followed when preparing Criticality Safety Evaluations that will be used to demonstrate the safety of operations performed at DOE Non-Reactor Nuclear Facilities. Adherence with these guidelines will provide consistency and uniformity in Criticality Safety Evaluations (CSEs) across the complex and will document compliance with DOE Order 5480.24 requirements as they pertain to CSEs

Guidelines for implementation of RCM on safety systems

International Nuclear Information System (INIS)

Kim, Tae Woon; Brijendra Singh.

1996-04-01

Reliability Centered Maintenance (RCM) methodology was originally developed by the commercial airlines industry in the early 1960s for identifying applicable and effective preventive maintenance tasks and as currently used in nuclear power industry. Effective maintenance of the systems at a nuclear power plant (NPP) is essential for its safe and reliable operation. Reliability Centered Maintenance at NPP is the program to assure that plant systems remain within an original design criteria and are not adversely affected during the plant life time. The aim of this report is to provide the guidelines to implement the RCM approach on NPP safety systems. Safety systems are usually standby and therefore, we need to periodically detect and repair failures that may have occurred since the previous activation or inspection the equipment. The RCM guidelines are intended to help identify the failure modes and related root causes and then decide the maintenance policies to achieve the high level of safety and reliability. The RCM is intended to improve or maintain high levels of system reliability and plant availability. Since the reliability of plant systems will be improved, the plant safety correspondingly will be increased. Another goal of RCM is to optimize the maintenance and surveillance tasks such that the overall level of resources required to accomplish essential tasks is kept to minimum. RCM also strives to eliminate unnecessary corrective maintenance and to select yet most cost-effective approach to maintenance, testing and inspection for system components. 9 refs. (Author) .new

Review guidelines on software languages for use in nuclear power plant safety systems. Final report

International Nuclear Information System (INIS)

Hecht, H.; Hecht, M.; Graff, S.; Green, W.; Lin, D.; Koch, S.; Tai, A.; Wendelboe, D.

1996-06-01

Guidelines for the programming and auditing of software written in high level languages for safety systems are presented. The guidelines are derived from a framework of issues significant to software safety which was gathered from relevant standards and research literature. Language-specific adaptations of these guidelines are provided for the following high level languages: Ada, C/C++, Programmable Logic Controller (PLC) Ladder Logic, International Electrotechnical Commission (IEC) Standard 1131-3 Sequential Function Charts, Pascal, and PL/M. Appendices to the report include a tabular summary of the guidelines and additional information on selected languages.s

Safety guidelines for magnetic resonance diagnostic facilities (1991)

International Nuclear Information System (INIS)

1992-01-01

These guidelines provide information on levels and health effects of exposure to magnetic and radiofrequency electromagnetic fields associated with magnetic resonance (MR) devices, and on precautions to minimize effects on patients, staff, and the general public. The guidelines are for use by regulatory authorities, MR users and health professionals. 22 refs., 1 tab

An overview of review guidelines for HDL programmable devices in nuclear safety systems

International Nuclear Information System (INIS)

Komanduri, Raghavan; Srivani, L.; Thirugnana Murthy, D.

2013-01-01

HDL programmable devices viz. CPLDs and FPGAs are increasingly being used to implement digital designs in the I and C systems performing safety functions of nuclear power plants. Synthesizable RTL descriptions manually written in HDLs are the first step in developing industry standard large scale digital designs. The reliability of the implementation is determined by the methodologies followed by the designer during development. Very few guidelines on HPD design practices, specific to nuclear industry are available. This paper presents an overview of the existing guidelines such as IEC 62566 and U.S. NRC's 'Review guidelines for FPGAs in nuclear power plant safety systems'. (author)

Monitoring and evaluation of Blyth Offshore wind farm: Health and Safety guidelines

Energy Technology Data Exchange (ETDEWEB)

Pepper, L

2002-07-01

Experiences during the construction, operation and maintenance of the wind farm off the coast of Blyth in Northumberland are used to assess the practicality of implementing existing draft British Wind Energy Association (BWEA) guidelines. These best practice guidelines, which were drawn up in consultation with the Health and Safety Executive (HSE) offer advice on health and safety issues specific to the wind industry in the UK. The guidelines are intended to cover both onshore and offshore sites; common advice is followed by advice specific to offshore sites. The Blyth Offshore project, the first offshore wind farm in the UK, features two 2 MW turbines installed on a submerged rocky outcrop about 1 km from the coast in a depth of about 6 m at low tide and a tidal range of about 5 m. The report concluded that, from the experience at Blyth, the draft guidelines will provide a useful tool for those involved in all stages of a wind farm project.

ASCOT guidelines revised 1996 edition. Guidelines for organizational self-assessment of safety culture and for reviews by the assessment of safety culture in organizations team

International Nuclear Information System (INIS)

1996-01-01

In order to properly assess safety culture, it is necessary to consider the contribution of all organizations which have an impact on it. Therefore, while assessing the safety culture in an operating organization it is necessary to address at least its interfaces with the local regulatory agency, utility corporate headquarters and supporting organizations. These guidelines are primarily intended for use by any organization wishing to conduct a self-assessment of safety culture. They should also serve as a basis for conducting an international peer review of the organization's self-assessment carried out by an ASCOT (Assessment of Safety Culture in Organizations Team) mission

Guideline for examination concerning the evaluation of safety in light water power reactor installations

International Nuclear Information System (INIS)

1978-01-01

This guideline was drawn up as the guide for examination when the safety evaluation of nuclear reactors is carried out at the time of approving the installation of light water power reactors. Accordingly in case of the examination of safety, it must be confirmed that the contents of application are in conformity with this guideline. If they are in conformity, it is judged that the safety evaluation of the policy in the basic design of a reactor facility is adequate, and also that the evaluation concerning the separation from the public in surroundings is adequate as the condition of location of the reactor facility. This guideline is concerned with light water power reactors now in use, but the basic concept may be the reference for the examination of the other types of reactors. If such a case occurs that the safety evaluation does not conform to this guideline, it is not excluded when the appropriate reason is clarified. The purpose of safety evaluation, the scope to be evaluated, the selection of the events to be evaluated, the criteria for judgement, the matters taken into consideration at the time of analysis, the concrete events of abnormal transient change and accident in operation, and the concrete events of serious accident and hypothetic accident are stipulated. The explanation and two appendices are attached. (Kako, I.)

Contrast media. Safety issues and ESUR guidelines. 2. rev. ed.

Energy Technology Data Exchange (ETDEWEB)

Thomsen, Henrik S. [Copenhagen University Hospital, Herlev (Denmark). Dept. of Diagnostic Radiology; Copenhagen Univ., Herlev (Denmark). Dept. of Diagnostic Sciences; Webb, Judith A.W. (eds.) [St. Bartholomew' s Hospital London Univ. (United Kingdom). Dept. of Radiology

2009-07-01

In 1994 the European Society of Urogenital Radiology (ESUR) set up a committee to consider the safety of contrast media used for diagnostic imaging. Subsequently the committee questioned members, reviewed the literature, proposed guidelines and discussed these proposals with participants at the annual symposia of the society. The end result of this work was the successful first edition of this book, published in 2006. This second edition not only updates the previous edition, but also contains some completely new chapters, for example on gadolinium-based contrast agents, meta-analyses in contrast media research and various regulatory issues. Comprehensive consideration is given to the many different safety issues relating to iodinated, MR, ultrasound and barium contrast media. The text includes chapters on both acute and delayed non-renal adverse reactions and on renal adverse reactions. All those questions frequently raised in radiological practice are addressed, and the well-known ESUR guidelines on contrast media are included. This book, presented in a handy, easy to use format, provides an invaluable, unique and unparalleled source of information on the safety issues relating to contrast media. (orig.)

Contrast media. Safety issues and ESUR guidelines. 2. rev. ed.

International Nuclear Information System (INIS)

Thomsen, Henrik S.; Copenhagen Univ., Herlev; Webb, Judith A.W.

2009-01-01

In 1994 the European Society of Urogenital Radiology (ESUR) set up a committee to consider the safety of contrast media used for diagnostic imaging. Subsequently the committee questioned members, reviewed the literature, proposed guidelines and discussed these proposals with participants at the annual symposia of the society. The end result of this work was the successful first edition of this book, published in 2006. This second edition not only updates the previous edition, but also contains some completely new chapters, for example on gadolinium-based contrast agents, meta-analyses in contrast media research and various regulatory issues. Comprehensive consideration is given to the many different safety issues relating to iodinated, MR, ultrasound and barium contrast media. The text includes chapters on both acute and delayed non-renal adverse reactions and on renal adverse reactions. All those questions frequently raised in radiological practice are addressed, and the well-known ESUR guidelines on contrast media are included. This book, presented in a handy, easy to use format, provides an invaluable, unique and unparalleled source of information on the safety issues relating to contrast media. (orig.)

Research oil guidelines for safety review of category 2 waste disposal

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

Safety confirmation items and monitoring items for engineered barriers were compiled, considering the current technical status and monitoring plan for the simulated subsurface disposal and its test facilities. In order to develop the guidelines of the safety review for the disposal of LLW generated from RI facilities and research facilities, technical issues relating toxic substances were surveyed. (author)

How do general practitioners use 'safety netting' in acutely ill children?

Science.gov (United States)

Bertheloot, Karen; Deraeve, Pieterjan; Vermandere, Mieke; Aertgeerts, Bert; Lemiengre, Marieke; De Sutter, An; Buntinx, Frank; Verbakel, Jan Y

2016-01-01

'Safety netting' advice allows general practitioners (GPs) to cope with diagnostic uncertainty in primary care. It informs patients on 'red flag' features and when and how to seek further help. There is, however, insufficient evidence to support useful choices regarding 'safety netting' procedures. To explore how GPs apply 'safety netting' in acutely ill children in Flanders. We designed a qualitative study consisting of semi-structured interviews with 37 GPs across Flanders. Two researchers performed qualitative analysis based on grounded theory components. Although unfamiliar with the term, GPs perform 'safety netting' in every acutely ill child, guided by their intuition without the use of specific guidelines. They communicate 'red flag' features, expected time course of illness and how and when to re-consult and try to tailor their advice to the context, patient and specific illness. Overall, GPs perceive 'safety netting' as an important element of the consultation, acknowledging personal and parental limitations, such as parents' interpretation of their advice. GPs do not feel a need for any form of support in the near future. GPs apply 'safety netting' intuitively and tailor the content. Further research should focus on the impact of 'safety netting' on morbidity and how the advice is conveyed to parents.

A framework for the development of patient safety education and training guidelines.

Science.gov (United States)

Zikos, Dimitrios; Diomidous, Marianna; Mantas, John

2010-01-01

Patient Safety (PS) is a major concern that involves a wide range of roles in healthcare, including those who are directly and indirectly involved, and patients as well. In order to succeed into developing a safety culture among healthcare providers, carers and patients, there should be given great attention into building appropriate education and training tools, especially addressing those who plan patient safety activities. The framework described in this policy paper is based on the results of the European Network for Patient Safety (EUNetPaS) project and analyses the principles and elements of the guidance that should be provided to those who design and implement Patient Safety Education and training activities. The main principles that it should be based on and the core teaching objectives-expected outcomes are addressed. Once the main context and considerations are properly set, the guidance should define the general schema of the content that should be included in the Education and Training activities, as well as how these activities would be delivered. It is also important that the different roles of the recipients are clearly distinguished and linked to their role-specific methods, proper delivery platforms and success stories. Setting these principles into practice when planning and implementing interventions, primarily aims to enlighten and support those who are enrolled to design and implement Patient Safety education and training teaching activities. This is achieved by providing them with a framework to build upon, succeeding to build a collaborative, safety conscious and competent environment, in terms of PS. A guidelines web platform has been developed to support this process.

KAERI software verification and validation guideline for developing safety-critical software in digital I and C system of NPP

Energy Technology Data Exchange (ETDEWEB)

Kim, Jang Yeol; Lee, Jang Soo; Eom, Heung Seop

1997-07-01

This technical report is to present V and V guideline development methodology for safety-critical software in NPP safety system. Therefore it is to present V and V guideline of planning phase for the NPP safety system in addition to critical safety items, for example, independence philosophy, software safety analysis concept, commercial off the shelf (COTS) software evaluation criteria, inter-relationships between other safety assurance organizations, including the concepts of existing industrial standard, IEEE Std-1012, IEEE Std-1059. This technical report includes scope of V and V guideline, guideline framework as part of acceptance criteria, V and V activities and task entrance as part of V and V activity and exit criteria, review and audit, testing and QA records of V and V material and configuration management, software verification and validation plan production etc., and safety-critical software V and V methodology. (author). 11 refs.

KAERI software verification and validation guideline for developing safety-critical software in digital I and C system of NPP

International Nuclear Information System (INIS)

Kim, Jang Yeol; Lee, Jang Soo; Eom, Heung Seop.

1997-07-01

This technical report is to present V and V guideline development methodology for safety-critical software in NPP safety system. Therefore it is to present V and V guideline of planning phase for the NPP safety system in addition to critical safety items, for example, independence philosophy, software safety analysis concept, commercial off the shelf (COTS) software evaluation criteria, inter-relationships between other safety assurance organizations, including the concepts of existing industrial standard, IEEE Std-1012, IEEE Std-1059. This technical report includes scope of V and V guideline, guideline framework as part of acceptance criteria, V and V activities and task entrance as part of V and V activity and exit criteria, review and audit, testing and QA records of V and V material and configuration management, software verification and validation plan production etc., and safety-critical software V and V methodology. (author). 11 refs

Integrated Safety in ''SARAF'

International Nuclear Information System (INIS)

Dickstein, P.; Grof, Y.; Machlev, M.; Pernick, A.

2004-01-01

As of the very early stages of the accelerator project at the Soreq Nuclear Research Center ''SARAF'' a safety group was established which has been an inseparable participant in the planning and design of the new facility. The safety group comprises of teams responsible for the shielding, radiation protection and general industrial safety aspects of ''SARAF''. The safety group prepared and documented the safety envelope for the accelerator, dealing with the safety requirements and guidelines for the first, pre-operational, stages of the project. The safety envelope, though based upon generic principles, took into account the accelerator features and the expected modes of operation. The safety envelope was prepared in a hierarchical structure, containing Basic Principles, Basic Guidelines, General Principles for Safety Implementation, Safety Requirements and Safety Underlining Issues. The above safety envelope applies to the entire facility, which entails the accelerator itself and the experimental areas and associated plant and equipment utilizing and supporting the production of the accelerated particle beams

Guidelines for the Review of Research Reactor Safety: Revised Edition. Reference Document for IAEA Integrated Safety Assessment of Research Reactors (INSARR)

International Nuclear Information System (INIS)

2013-01-01

The Integrated Safety Assessment of Research Reactors (INSARR) is an IAEA safety review service available to Member States with the objective of supporting them in ensuring and enhancing the safety of their research reactors. This service consists of performing a comprehensive peer review and an assessment of the safety of the respective research reactor. The reviews are based on IAEA safety standards and on the provisions of the Code of Conduct on the Safety of Research Reactors. The INSARR can benefit both the operating organizations and the regulatory bodies of the requesting Member States, and can include new research reactors under design or operating research reactors, including those which are under a Project and Supply Agreement with the IAEA. The first IAEA safety evaluation of a research reactor operated by a Member State was completed in October 1959 and involved the Swiss 20 MW DIORIT research reactor. Since then, and in accordance with its programme on research reactor safety, the IAEA has conducted safety review missions in its Member States to enhance the safety of their research reactor facilities through the application of the Code of Conduct on the Safety of Research Reactors and the relevant IAEA safety standards. About 320 missions in 51 Member States were undertaken between 1972 and 2012. The INSARR missions and other limited scope safety review missions are conducted following the guidelines presented in this publication, which is a revision of Guidelines for the Review of Research Reactor Safety (IAEA Services Series No. 1), published in December 1997. This publication details those IAEA safety standards and guidance publications relevant to the safety of research reactors that have been revised or published since 1997. The purpose of this publication is to give guidance on the preparation, implementation, reporting and follow-up of safety review missions. It is also intended to be of assistance to operators and regulators in conducting

The Italian National Guidelines for the fire safety of facades

Directory of Open Access Journals (Sweden)

Lamberto Mazziotti

2013-11-01

Full Text Available Traditionally, the facades' design buildings where once only focused on architectural or aesthetic purposes (in addition, of course, of whether protective issues. Nowadays, thanks to the technological development of the construction works and the use of new types of materials, the facades' design should also address fire safety related aspects. In Europe and especially in Italy – where the types of building façades are built with windows of small surface and natural stone coverings – the green building/sustainability movement has resulted in the development of new concepts in facade or curtain wall design that intended to enhance the energy efficiency of building façades. These new building surfaces are covered by extensive panelling fitted with insulating materials or by wide glass surfaces, capable of carry out the most diverse purposes including, just to name a few: energy reduction, climate comfort, recovery of electricity through photovoltaic panels that convert sunlight into electricity, large space for advertising purpose. One of the main fire safety goal for a building design is to restrict the vertical fire spread so that the smoke and flames are limited to the fire origin floor. The new building façade and curtain wall topologies could overwhelms concerns for fire safety, therefore the Italian National fire service has released a Fire Code Guideline in order to address the fire safety design for an high rise building façade. This paper aims to show the guideline contents and the related fire safety façades concerns.

A guideline for comprehensive evaluation of a licensee's effort to cultivate safety culture

International Nuclear Information System (INIS)

Makino, Maomi; Ishii, Yoichi

2009-01-01

The nuclear industry in Japan had held excellent performance in safety in the world during 90's. However recent events stem from organizational factors and defects of safety culture are pointed out in their contexts. In order to reduce accidents caused by organizational factors, the Japanese Regulatory body NISA (Nuclear and Industrial Safety Agency) decided to evaluate a licensee's effort for the cultivation of safety culture, and to order all licensses to add the provision of cultivating safety culture to their safety preservation rules. The inspection for the new safety preservation rules started in December, 2007. For a measure of evaluation by resident inspectors, NISA and the Japan Nuclear Energy Safety Organization (JNES) prepared a guideline for the prevention of degradation of safety culture and organizational climate. In this guideline, 14 items were defined as the components of the safety culture or as the viewpoints to evaluate the effort made to prevent any degradation of safety culture and organizational climate in the daily safety preservation activities. The 14 items are also used to establish the method to comprehensively evaluate the effort to prevent degradation of safety culture and organizational climate. This method consists of 10 steps: two steps to taken prior to start of the evaluation, two steps to be taken during the evaluation period, 5 steps to be taken during a comprehensive evaluation period and a final step to be taken for comprehensive findings for safety culture. This paper mainly describes the viewpoints to evaluate comprehensively a licensee's effort for cultivation of safety culture. (author)

Best Practice Guidelines for the use of CFD in Nuclear Reactor Safety Applications

International Nuclear Information System (INIS)

Mahaffy, J.; Chung, B.; Song, C.; Dubois, F.; Graffard, E.; Ducros, F.; Heitsch, M.; Scheuerer, M.; Henriksson, M.; Komen, E.; Moretti, F.; Morii, T.; Muehlbauer, P.; Rohde, U.; Smith, B. L.; Watanabe, T.; Zigh, G.

2007-01-01

In May 2002, an 'Exploratory Meeting of Experts to Define an Action Plan on the Application of Computational Fluid Dynamics (CFD) Codes to Nuclear Reactor Safety Problems' was held at Aix-en-Provence, France. One of three recommended actions was the formation of this writing group to report on the need for guidelines for use of CFD in single phase Nuclear Reactor Safety (NRS) applications. CSNI approved this writing group at the end of 2002, and work began in March 2003. A final report was submitted to GAMA in September 2004, summarizing existing Best Practice Guidelines (BPG) for CFD, and recommending creation of a BPG document for Nuclear Reactor Safety (NRS) applications. The present document is intended to provide an internally complete set of guidelines for a range of single phase applications of CFD to NRS problems. However, it is not meant to be comprehensive; it is recognized that for any specific application a higher level of specificity is possible on questions of nodalization, model selection, and validation. This document should provide direct guidance on the key considerations in known single phase applications, and general directions for resolving remaining details. The intent is that it will serve as a template for further application specific (e.g. PTS, induced break) BPG documents that will provide much more detailed information and examples. The document begins with a summary of NRS related CFD analysis in countries represented by the authors. Chapter 3 deals with definition of the problem and its solution approach. This includes isolation of the portion of the NRS problem most in need of CFD, and use of a classic thermal hydraulic (TH) safety code to provide boundary conditions for the CFD based upon less detailed simulation of the balance of plant. Chapter 4 provides guidance in choosing between various options, and also discusses use of a transient calculation with tightly coupled CFD and TH codes. Chapter 5 discusses selection of physical

TIS General Safety Group Annual Report 2000

CERN Document Server

Weingarten, W

2001-01-01

This report summarises the main activities of the General Safety (GS) Group of the Technical Inspection and Safety Division (TIS) during the year 2000, and the results obtained. The different topics in which the Group is active are covered: general safety inspections and ergonomy, electrical, chemistry and gas safety, chemical pollution containment and control, industrial hygiene, the safety of civil engineering works and outside contractors, fire prevention and the safety aspects of the LHC experiments.

Technical guidelines for the seismic safety re-evaluation at Eastern European NPPs

International Nuclear Information System (INIS)

Godoy, A.R.; Guerpinar, A.

2001-01-01

The paper describes one of the outcomes of the Engineering Safety Review Services (ESRS) that the IAEA provides as an element of the Agency's national, regional and interregional technical assistance and co-operation programmes and other extrabudgetary programmes to assess the safety of nuclear facilities. This refers to the establishment of detailed guidelines for conducting the seismic safety re-evaluation of existing nuclear power plants in Eastern European countries in line with updated criteria and current international practice. (author)

Review guidelines for software languages for use in nuclear power plant safety systems: Final report. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Hecht, M.; Decker, D.; Graff, S.; Green, W.; Lin, D.; Dinsmore, G.; Koch, S. [SoHaR, Inc., Beverly Hills, CA (United States)

1997-10-01

Guidelines for the programming and auditing of software written in high level languages for safety systems are presented. The guidelines are derived from a framework of issues significant to software safety which was gathered from relevant standards and research literature. Language-specific adaptations of these guidelines are provided for the following high level languages: Ada83 and Ada95; C and C++; International Electrochemical Commission (IEC) Standard 1131-3 Ladder Logic, Sequential Function Charts, Structured Text, and Function Block Diagrams; Pascal; and PL/M. Appendices to the report include a tabular summary of the guidelines and additional information on selected languages.

Review guidelines for software languages for use in nuclear power plant safety systems: Final report. Revision 1

International Nuclear Information System (INIS)

Hecht, M.; Decker, D.; Graff, S.; Green, W.; Lin, D.; Dinsmore, G.; Koch, S.

1997-10-01

Guidelines for the programming and auditing of software written in high level languages for safety systems are presented. The guidelines are derived from a framework of issues significant to software safety which was gathered from relevant standards and research literature. Language-specific adaptations of these guidelines are provided for the following high level languages: Ada83 and Ada95; C and C++; International Electrochemical Commission (IEC) Standard 1131-3 Ladder Logic, Sequential Function Charts, Structured Text, and Function Block Diagrams; Pascal; and PL/M. Appendices to the report include a tabular summary of the guidelines and additional information on selected languages

Patient safety in primary care: a survey of general practitioners in the Netherlands

Directory of Open Access Journals (Sweden)

Wensing Michel

2010-01-01

Full Text Available Abstract Background Primary care encompasses many different clinical domains and patient groups, which means that patient safety in primary care may be equally broad. Previous research on safety in primary care has focused on medication safety and incident reporting. In this study, the views of general practitioners (GPs on patient safety were examined. Methods A web-based survey of a sample of GPs was undertaken. The items were derived from aspects of patient safety issues identified in a prior interview study. The questionnaire used 10 clinical cases and 15 potential risk factors to explore GPs' views on patient safety. Results A total of 68 GPs responded (51.5% response rate. None of the clinical cases was uniformly judged as particularly safe or unsafe by the GPs. Cases judged to be unsafe by a majority of the GPs concerned either the maintenance of medical records or prescription and monitoring of medication. Cases which only a few GPs judged as unsafe concerned hygiene, the diagnostic process, prevention and communication. The risk factors most frequently judged to constitute a threat to patient safety were a poor doctor-patient relationship, insufficient continuing education on the part of the GP and a patient age over 75 years. Language barriers and polypharmacy also scored high. Deviation from evidence-based guidelines and patient privacy in the reception/waiting room were not perceived as risk factors by most of the GPs. Conclusion The views of GPs on safety and risk in primary care did not completely match those presented in published papers and policy documents. The GPs in the present study judged a broader range of factors than in previously published research on patient safety in primary care, including a poor doctor-patient relationship, to pose a potential threat to patient safety. Other risk factors such as infection prevention, deviation from guidelines and incident reporting were judged to be less relevant than by policy

Patient safety in primary care: a survey of general practitioners in The Netherlands.

Science.gov (United States)

Gaal, Sander; Verstappen, Wim; Wensing, Michel

2010-01-21

Primary care encompasses many different clinical domains and patient groups, which means that patient safety in primary care may be equally broad. Previous research on safety in primary care has focused on medication safety and incident reporting. In this study, the views of general practitioners (GPs) on patient safety were examined. A web-based survey of a sample of GPs was undertaken. The items were derived from aspects of patient safety issues identified in a prior interview study. The questionnaire used 10 clinical cases and 15 potential risk factors to explore GPs' views on patient safety. A total of 68 GPs responded (51.5% response rate). None of the clinical cases was uniformly judged as particularly safe or unsafe by the GPs. Cases judged to be unsafe by a majority of the GPs concerned either the maintenance of medical records or prescription and monitoring of medication. Cases which only a few GPs judged as unsafe concerned hygiene, the diagnostic process, prevention and communication. The risk factors most frequently judged to constitute a threat to patient safety were a poor doctor-patient relationship, insufficient continuing education on the part of the GP and a patient age over 75 years. Language barriers and polypharmacy also scored high. Deviation from evidence-based guidelines and patient privacy in the reception/waiting room were not perceived as risk factors by most of the GPs. The views of GPs on safety and risk in primary care did not completely match those presented in published papers and policy documents. The GPs in the present study judged a broader range of factors than in previously published research on patient safety in primary care, including a poor doctor-patient relationship, to pose a potential threat to patient safety. Other risk factors such as infection prevention, deviation from guidelines and incident reporting were judged to be less relevant than by policy makers.

75 FR 15485 - Pipeline Safety: Workshop on Guidelines for Integrity Assessment of Cased Pipe

Science.gov (United States)

2010-03-29

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket ID...: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice of workshop. SUMMARY... ``Guidelines for Integrity Assessment of Cased Pipe in Gas Transmission Pipelines'' and related Frequently...

Comparison of evaluation guidelines for life-safety seismic hazards

International Nuclear Information System (INIS)

Wyllie, L.A.; Love, R.J.

1989-01-01

The guidelines presented in Design Evaluation guidelines for Department of Energy Facilities Subjected to natural Phenomena Hazards (UCRL 15910 Draft; May 1989) include evaluation criteria for existing Department of Energy buildings subjected to earthquakes. These criteria were developed at the Lawrence Livermore National Laboratory for use in both the seismic design of new structures and the evaluation of existing structures. ATC-14: Evaluating The Seismic Resistance of Existing Buildings developed by the Applied Technology Council, consists of guidelines and criteria for identifying the buildings or building components that present unacceptable risk to human lives. This paper compares and contrasts the two evaluation guidelines for existing buildings using a prototype building as an example. The prototype building is a seven story, concrete shear wall building assuming a General Use Occupancy

49 CFR 238.229 - Safety appliances-general.

Science.gov (United States)

2010-10-01

... 49 Transportation 4 2010-10-01 2010-10-01 false Safety appliances-general. 238.229 Section 238.229... Equipment § 238.229 Safety appliances—general. (a) Except as provided in this part, all passenger equipment continues to be subject to the safety appliance requirements contained in Federal statute at 49 U.S.C...

Cholesterol management in Dutch general practice: a comparison with national guidelines.

NARCIS (Netherlands)

Weijden, T. van der; Hutten, J.B.F.; Brandenburg, B.J.; Grol, R.P.T.M.; Velden, K. van der

1994-01-01

OBJECTIVE: To examine cholesterol diagnosis and treatment by Dutch general practitioners (GPs) in the period before publication of national guidelines, in order to develop implementation strategies based on discrepancies found between daily practice and the guidelines. DESIGN: Data of the 'Dutch

Activities of ARCAL XX for the development of guidelines for the safety of radiation sources

International Nuclear Information System (INIS)

Velasques de Oliveira, S.M.; Betancourt, L.A.

2001-01-01

This report presents the contribution of the ARCAL XX project 'Guidelines for the Control of Radiation Sources' for the development and harmonization of the safety of radiation sources in Latin America. The project began in 1997 with the participation of nine countries. The methodology adopted has enabled all experts from the nine countries involved in the project to participate in discussions on the development of guidelines based on regional experience. Three common documents for all practices and six safety guides for the main practices have been revised for publication. For the next two years, the project co-ordinators are proposing regional and national workshops for the application of the safety guides approved by the ARCAL programme. (author)

Factors influencing adherence to guidelines in general practice

NARCIS (Netherlands)

Stewart, RE; Vroegop, S; van der Werf, GT; Meyboom-de Jong, B; Kamps, G.

2003-01-01

Objectives: To identify and assess the effects of general practitioner and patient characteristics on global adherence to pharmacotherapeutic guidelines. Methods: In a cross-sectional study in the northern Netherlands, a two-level multilevel model was applied to patients (n = 269,067) in 190

Do general practitioners adhere to the guideline on infectious conjunctivitis? Results of the Second Dutch National Survey of General Practice

Directory of Open Access Journals (Sweden)

Schellevis François G

2007-09-01

Full Text Available Abstract Background In 1996 the guideline 'The Red Eye' was first published by the Dutch College of General Practitioners. The extent to which general practitioners adhere to this guideline is unclear. Recently, data on the management of infectious conjunctivitis by general practitioners became available from the Second Dutch National Survey of General Practice. We measured the age-specific incidence of infectious conjunctivitis, described its management by Dutch general practitioners, and then compared these findings with the recommendations made in the guideline. Methods In 2001, over a 12-month period, data from all patient contacts with 195 general practitioners were taken from electronic medical records. Registration was episode-oriented; all consultations dealing with the same health problem were grouped into disease episodes. Data concerning all episodes of infectious conjunctivitis (ICPC-code F70 and sub codes were analysed. Results Over one year, 5,213 new and recurrent episodes of infectious conjunctivitis were presented to general practitioners from a population of N = 375,899, resulting in an overall incidence rate of 13.9 per 1000 person-years, varying from more than 80/1000 py in children up to one-year old, to less than 12/1000 py in children over the age of 4. Topical ophthalmic ointments were prescribed in 87% of the episodes, of which 80% was antibiotic treatment. Fusidic acid gel was most frequently prescribed (69%. In most episodes general practitioners did not adhere to the guideline. Conclusion In 2001, the management of infectious conjunctivitis by Dutch general practitioners was not in accordance with the recommendations of the consensus-based guideline published five years previously, despite its wide distribution. In 2006 this guideline was revised. Its successful implementation requires more than distribution alone. Probably the most effective way to achieve this is by following a model for systemic implementation.

ASVCP quality assurance guidelines: control of general analytical factors in veterinary laboratories.

Science.gov (United States)

Flatland, Bente; Freeman, Kathy P; Friedrichs, Kristen R; Vap, Linda M; Getzy, Karen M; Evans, Ellen W; Harr, Kendal E

2010-09-01

Owing to lack of governmental regulation of veterinary laboratory performance, veterinarians ideally should demonstrate a commitment to self-monitoring and regulation of laboratory performance from within the profession. In response to member concerns about quality management in veterinary laboratories, the American Society for Veterinary Clinical Pathology (ASVCP) formed a Quality Assurance and Laboratory Standards (QAS) committee in 1996. This committee recently published updated and peer-reviewed Quality Assurance Guidelines on the ASVCP website. The Quality Assurance Guidelines are intended for use by veterinary diagnostic laboratories and veterinary research laboratories that are not covered by the US Food and Drug Administration Good Laboratory Practice standards (Code of Federal Regulations Title 21, Chapter 58). The guidelines have been divided into 3 reports on 1) general analytic factors for veterinary laboratory performance and comparisons, 2) hematology and hemostasis, and 3) clinical chemistry, endocrine assessment, and urinalysis. This report documents recommendations for control of general analytical factors within veterinary clinical laboratories and is based on section 2.1 (Analytical Factors Important In Veterinary Clinical Pathology, General) of the newly revised ASVCP QAS Guidelines. These guidelines are not intended to be all-inclusive; rather, they provide minimum guidelines for quality assurance and quality control for veterinary laboratory testing. It is hoped that these guidelines will provide a basis for laboratories to assess their current practices, determine areas for improvement, and guide continuing professional development and education efforts. ©2010 American Society for Veterinary Clinical Pathology.

Radiation Safety Management Guidelines for PET-CT: Focus on Behavior and Environment

International Nuclear Information System (INIS)

Jung, Jin Wook; Han, Eun Ok

2011-01-01

Our purpose is to specify behavior and environmental factors aimed at reducing the exposed dosage caused by PET-CT and to develop radiation safety management guidelines adequate for domestic circumstances. We have used a multistep-multimethod as the methodological approach to design and to carry out the research both in quality and quantity, including an analysis on previous studies, professional consultations and a survey. The survey includes responses from 139 practitioners in charged of 109 PET-CTs installed throughout Korea(reported by the Korean Society of Nuclear Medicine, 2010). The research use 156 questions using Cronbach's α (alpha) coefficients which were: 0.818 for 'the necessity of setting and installing the radiation protective environment'; 0.916 for 'the necessity of radiation protection', 'setting and installing the radiation protective environment'; and 0.885 for 'radiation protection'. The check list, derived from the radiation safety management guidelines focused on behavior and environment, was composed of 20 items for the radiation protective environment: including 5 items for the patient; 4 items for the guardian; 3 items for the radiologist; and 8 items applied to everyone involved; for a total of 26 items for the radiation protective behavior including: 12 items for the patient; 1 item for the guardian, 7 items for the radiologist; and 6 items applied to everyone involved. The specific check list is shown in (Table 5-6). Since our country has no safety management guidelines of its own to reduce the exposed dosage caused by PET-CTs, we believe the guidelines developed through this study means great deal to the field as it is not only appropriate for domestic circumstances, but also contains specific check lists for each target who may be exposed to radiation in regards to behavior and environment.

The General Safety Group Annual Report 2001/2002

CERN Document Server

Weingarten, W

2003-01-01

This report summarizes the main activities of the General Safety (GS) Group of the Technical Inspection and Safety Division during 2001 and 2002, and the results obtained. The different topics in which the group is active are covered: general safety inspections and ergonomics, electrical, chemical and gas safety, chemical pollution containment and control, industrial hygiene, the safety of civil engineering works and outside contractors, fire prevention and the safety aspects of the LHC experiments.

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

Science.gov (United States)

2010-11-30

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

Radiological risk guidelines for nonreactor nuclear facilities at the Pacific Northwest Laboratory

International Nuclear Information System (INIS)

Lucas, D.E.; Ikenberry, T.A.

1993-09-01

Radiological risk evaluation guidelines for the public and workers have been developed at the Pacific Northwest Laboratory (PNL) based upon the Nuclear Safety Policy of the US Department of Energy (DOE) established in Secretary of Energy Notice SEN-35-91. The DOE nuclear safety policy states that the general public shall be protected such that no individual bears significant additional risk to health and safety from the operation of a DOE nuclear facility above the risks to which members of the general population are normally exposed. The radiological risk evaluation guidelines developed at PNL are unique in that they are (1) based upon quantitative risk goals and (2) provide a consistent level of risk management. These guidelines are used to evaluate the risk from radiological accidents that may occur during research and development activities at PNL, and are not intended for evaluation of routine exposures. A safety analyst uses the,frequency of the potential accident and the radiological dose to a given receptor to determine if the accident consequences meet the objectives of the Nuclear Safety Policy. The radiological risk evaluation guidelines are an effective tool for assisting in the management of risk at DOE nonreactor nuclear facilities. These guidelines (1) meet the nuclear safety policy of DOE, (2) establish a tool for managing risk at a consistent level within the defined constraints, and (3) set risk at an appropriate level, as compared with other risks encountered by the public and worker. Table S.1 summarizes the guidelines developed in this report

[The Dutch College of General Practitioners practice guideline 'The menopause'; reaction of the field of general practice

NARCIS (Netherlands)

Bosch, W.J.H.M. van den

2002-01-01

The Dutch College of General Practitioners' practice guideline on the menopause will not be any major cause for discussion. The hot issue of giving oestrogens to peri- and postmenopausal women to prevent osteoporosis or cardiovascular disease was already covered in the practice guideline on

New guidelines for dam safety classification

International Nuclear Information System (INIS)

Dascal, O.

1999-01-01

Elements are outlined of recommended new guidelines for safety classification of dams. Arguments are provided for the view that dam classification systems should require more than one system as follows: (a) classification for selection of design criteria, operation procedures and emergency measures plans, based on potential consequences of a dam failure - the hazard classification of water retaining structures; (b) classification for establishment of surveillance activities and for safety evaluation of dams, based on the probability and consequences of failure - the risk classification of water retaining structures; and (c) classification for establishment of water management plans, for safety evaluation of the entire project, for preparation of emergency measures plans, for definition of the frequency and extent of maintenance operations, and for evaluation of changes and modifications required - the hazard classification of the project. The hazard classification of the dam considers, as consequence, mainly the loss of lives or persons in jeopardy and the property damages to third parties. Difficulties in determining the risk classification of the dam lie in the fact that no tool exists to evaluate the probability of the dam's failure. To overcome this, the probability of failure can be substituted for by a set of dam characteristics that express the failure potential of the dam and its foundation. The hazard classification of the entire project is based on the probable consequences of dam failure influencing: loss of life, persons in jeopardy, property and environmental damage. The classification scheme is illustrated for dam threatening events such as earthquakes and floods. 17 refs., 5 tabs

Measure Guideline: Combustion Safety for Natural Draft Appliances Through Appliance Zone Isolation

Energy Technology Data Exchange (ETDEWEB)

Fitzgerald, J. [Center for Energy and Environment, Minneapolis, MN (United States); Bohac, D. [Center for Energy and Environment, Minneapolis, MN (United States)

2014-04-01

This measure guideline covers how to assess and carry out the isolation of natural draft combustion appliances from the conditioned space of low-rise residential buildings. It deals with combustion appliances located either within the living space in enclosed closets or side rooms or outside the living space in an adjacent area like an attic or garage. This subset of houses does not require comprehensive combustion safety tests and simplified prescriptive procedures can be used to address safety concerns. This allows residential energy retrofit contractors inexperienced in advanced combustion safety testing to effectively address combustion safety issues and allow energy retrofits including tightening and changes to distribution and ventilation systems to proceed.

Radiological risk guidelines for nonreactor nuclear facilities at the Pacific Northwest Laboratory

International Nuclear Information System (INIS)

Lucas, D.E.; Ikenberry, T.A.

1994-03-01

Radiological risk evaluation guidelines for the public and workers have been developed at the Pacific Northwest Laboratory (PNL) based upon the Nuclear Safety Policy of the US Department of Energy (DOE) established in Secretary of Energy Notice SEN-35-91 (DOE 1991). The DOE nuclear safety policy states that the general public be protected-such that no individual bears significant additional risk to health and safety from the operation of a DOE nuclear facility above the risks to which members of the general population are normally exposed. The radiological risk evaluation guidelines developed at PNL are unique in that they are (1) based upon quantitative risk goals and (2) provide a consistent level of risk management. These guidelines are used to evaluate the risk from radiological accidents that may occur during research and development activities at PNL. A safety analyst uses the frequency of the potential accident and the radiological dose to a given receptor to determine if the accident consequences meet the objectives of the Nuclear Safety Policy

Guideline on evaluation and acceptance of commercial grade digital equipment for nuclear safety applications

International Nuclear Information System (INIS)

1996-10-01

Nuclear power plants are increasingly upgrading their instrumentation and control (I ampersand C) systems with commercial digital equipment, which allows them to continue meeting safety and reliability requirements while controlling operating costs. However, the use of commercial software-based devices for safety related applications has raised new issues that impact design, procurement, and licensing activities. This guideline describes a consistent, comprehensive approach for the evaluation and acceptance of commercial digital equipment for nuclear safety systems

Advanced human-system interface design review guideline. Evaluation procedures and guidelines for human factors engineering reviews

Energy Technology Data Exchange (ETDEWEB)

O`Hara, J.M.; Brown, W.S. [Brookhaven National Lab., Upton, NY (United States); Baker, C.C.; Welch, D.L.; Granda, T.M.; Vingelis, P.J. [Carlow International Inc., Falls Church, VA (United States)

1994-07-01

Advanced control rooms will use advanced human-system interface (HSI) technologies that may have significant implications for plant safety in that they will affect the operator`s overall role in the system, the method of information presentation, and the ways in which operators interact with the system. The U.S. Nuclear Regulatory Commission (NRC) reviews the HSI aspects of control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported to protect public health and safety. The principal guidance available to the NRC, however, was developed more than ten years ago, well before these technological changes. Accordingly, the human factors guidance needs to be updated to serve as the basis for NRC review of these advanced designs. The purpose of this project was to develop a general approach to advanced HSI review and the human factors guidelines to support. NRC safety reviews of advanced systems. This two-volume report provides the results of the project. Volume I describes the development of the Advanced HSI Design Review Guideline (DRG) including (1) its theoretical and technical foundation, (2) a general model for the review of advanced HSIs, (3) guideline development in both hard-copy and computer-based versions, and (4) the tests and evaluations performed to develop and validate the DRG. Volume I also includes a discussion of the gaps in available guidance and a methodology for addressing them. Volume 2 provides the guidelines to be used for advanced HSI review and the procedures for their use.

Advanced human-system interface design review guideline. Evaluation procedures and guidelines for human factors engineering reviews

International Nuclear Information System (INIS)

O'Hara, J.M.; Brown, W.S.; Baker, C.C.; Welch, D.L.; Granda, T.M.; Vingelis, P.J.

1994-07-01

Advanced control rooms will use advanced human-system interface (HSI) technologies that may have significant implications for plant safety in that they will affect the operator's overall role in the system, the method of information presentation, and the ways in which operators interact with the system. The U.S. Nuclear Regulatory Commission (NRC) reviews the HSI aspects of control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported to protect public health and safety. The principal guidance available to the NRC, however, was developed more than ten years ago, well before these technological changes. Accordingly, the human factors guidance needs to be updated to serve as the basis for NRC review of these advanced designs. The purpose of this project was to develop a general approach to advanced HSI review and the human factors guidelines to support. NRC safety reviews of advanced systems. This two-volume report provides the results of the project. Volume I describes the development of the Advanced HSI Design Review Guideline (DRG) including (1) its theoretical and technical foundation, (2) a general model for the review of advanced HSIs, (3) guideline development in both hard-copy and computer-based versions, and (4) the tests and evaluations performed to develop and validate the DRG. Volume I also includes a discussion of the gaps in available guidance and a methodology for addressing them. Volume 2 provides the guidelines to be used for advanced HSI review and the procedures for their use

Safety of transcranial magnetic stimulation: review of international guidelines and new findings

Directory of Open Access Journals (Sweden)

N. A. Suponeva

2017-01-01

Full Text Available Transcranial magnetic stimulation (TMS is a rapidly developing method of neuromodulation. The use of TMS has increased significantly in both research and clinical practice. This allows not only to better understand this method, but also assess possible risks and consequences for both healthy individuals and patients. In 1998 and 2009 safety, ethical considerations, and application guidelines for the use of TMS in clinical practice and research were published. These recommendations are now the basis for safe application of the method in clinical practice and research. Safety of brain stimulation includes several aspects: the prevention and treatment of adverse effects, the strategy of patient and stimulation protocols selection, as well as safety and monitoring procedures. The most common adverse effects of TMS include headache and neck pain, syncope, transient hearing impairment. The risk of epileptic seizureis extremely low and can be minimized by careful selection of patients and the use of safe stimulation protocols. Careful selection of patients is important, taking into account a large number of factors that influence the risk of adverse effects. These factors are considered in the questionnaires to identify limitations and absolute or relative contraindications to TMS. Another important part of TMS safety is the choice of the stimulation protocol and parameters such as intensity, frequency, duration of one train of stimuli, and the interstimulus interval. Currently, the recommended limits of stimulation parameters are covered in the safety guidelines. It is also necessary to follow the procedure, including the monitoring the patient's condition during TMS and the providing qualified assistance in case of adverse effects.

SCART guidelines. Reference report for IAEA Safety Culture Assessment Review Team (SCART)

International Nuclear Information System (INIS)

2008-01-01

The IAEA Director General stressed the role of safety culture in his concluding remarks at the Meeting of the Contracting Parties to the Convention on Nuclear Safety in 2002: 'As we have learned in other areas, it is not enough simply to have a structure; it is not enough to say that we have the necessary laws and the appropriate regulatory bodies. All these are important, but equally important is that we have in place a safety culture that gives effect to the structure that we have developed. To me, effectiveness and transparency are keys. So, it is an issue which I am pleased to see, you are giving the attention it deserves and we will continue to work with you in clarifying, developing and applying safety culture through our programmes and through our technical cooperation activities.' The concept of safety culture was initially developed by the International Nuclear Safety Advisory Group (INSAG) after the Chernobyl accident in 1986. Since then the IAEA's perspective of safety culture has expanded with time as its recognition of the complexities of the concept developed. Safety culture is considered to be specific organizational culture in all types of organizations with activities that give rise to radiation risks. The aim is to make safety culture strong and sustainable, so that safety becomes a primary focus for all activities in such organizations, even for those, which might not look safety-related at first. SCART (Safety Culture Assessment Review Team) is a safety review service, which reflects the expressed interest of Members States for methods and tools for safety culture assessment. It is a replacement for the earlier service ASCOT (Assessment of Safety Culture in Organizations Team). The IAEA Safety Fundamentals, Requirements and Guides (Safety Standards) are the basis for the SCART Safety Review Service. The reports of INSAG, identifying important current nuclear safety issues, serve also as references during a SCART mission. SCART missions are based

[Need for clinical guidelines for chronic periodontitis in general and specialized Belgian practice].

Science.gov (United States)

Cosyn, Jan; Thevissen, Eric; Reners, Michèle; Rompen, Eric; Klinge, Björn; De Bruyn, Hugo

2008-01-01

As the prevalence of periodontitis is more than 40 % in the adult Belgian population, periodontists are clearly understaffed to treat this disease in all patients. Therefore, it seems logic that mild forms of chronic periodontitis are treated by the general practitioner especially because Belgium lacks dental hygienists. Important prerequisites for organizing periodontal care as such relate to the general practitioner who should use the same techniques, have comparable communicative skills to motivate patients and create a similar amount of time for periodontal treatment as the specialist. After all, the patient has the right to qualitative treatment regardless of the level of education of the care provider. In order to guarantee this in general practice as much as possible, there is a need for clinical guidelines developed by specialists. These guidelines should not only support the general practitioner in treating disease; above all, they should assist the dentist in periodontal diagnosis. Hitherto, periodontal screening by general dentists seems to be infrequently performed even though reimbursement of the Dutch Periodontal Screening Index is implemented in the Belgian healthcare security system. In this manuscript possible explanations for this phenomenon are discussed. Apart from the need for guidelines in general practice, guidelines for surgical treatment seem compulsory to uniform treatment protocols in specialized practice. Extreme variation in the recommendation of surgery among Belgian specialists calls for consensus statements.

Contrast media. Safety issues and ESUR guidelines. 3. ed.

International Nuclear Information System (INIS)

Thomsen, Henrik S.; Webb, Judith A.W.

2014-01-01

Fully updates the previous edition and includes new chapters on various complex topics. Represents a unique and unparalleled source of information on the many safety issues relating to different contrast media. Includes chapters on acute and delayed non-renal adverse reactions and on renal adverse reactions. Presented in a handy, easy-to-use format. In 1994 the European Society of Urogenital Radiology (ESUR) set up a committee to consider the safety of contrast media used for diagnostic imaging. Subsequently the committee questioned ESUR members, reviewed the literature, proposed guidelines, and discussed these proposals with participants at the annual symposia of the society. The end result of this work was the successful first edition of this book, published in 2006, which was followed by an equally successful second edition in 2009. This third edition not only fully updates the previous edition, but also includes new chapters on complex topics such as use of contrast media in children and practical aspects of off-label contrast media use. The authorship includes members, past members, and non-members of the Contrast Media Safety Committee.

Issues in the management of acute agitation: how much current guidelines consider safety?

Directory of Open Access Journals (Sweden)

Bruno ePacciardi

2013-05-01

Full Text Available Agitated behavior constitutes up to 10% of emergency psychiatric interventions. Pharmacological tranquilization is often used as a valid treatment for agitation but a strong evidence base does not underpin it. Available literature shows different recommendations, supported by research data, theoretical considerations or clinical experience. Rapid tranquilization is mainly based on parenteral drug treatment and the few existing guidelines on this topic, when suggesting the use of first generation antipsychotics and benzodiazepines, include drugs with questionable tolerability profile such as chlorpromazine, haloperidol, midazolam and lorazepam. In order to systematically evaluate safety concerns related to the adoption of such guidelines, we reviewed them independently from principal diagnosis while examining tolerability data for suggested treatments. There is a growing evidence about safety profile of second generation antipsychotics for rapid tranquilization but further controlled studies providing definitive data in this area are urgently needed.

Seismic PSA implementation standards by AESJ and the utilization of the advanced safety examination guideline for seismic design for nuclear power plant

International Nuclear Information System (INIS)

Ebisawa, Katsumi; Hibino, Kenta

2008-01-01

The Advanced Safety Examination Guideline for Seismic Design for Nuclear Power Plant (the advanced safety examination guideline) was worked out on September 19, 2006. In this paper, a summary of the method of probability theory in the advanced safety examination guideline and the Seismic PSA Implementation Standards is stated. On utilization of the probability theory for the advanced safety examination guideline, the uncertainty resulting from the process of the decision of the basic design earthquake ground motion (Ss) is stated to be considered using the proper method. The references of the extra probability for evaluation of earthquake hazard and combination of the working load and the earthquake load are stated. Definition, evaluation method and effort to lower the 'residual risks', and relation between the residual risks and the extra probability of Ss are described. A summary of the earthquake-resistant design for nuclear power facilities is explained by the old guideline. (S.Y.)

OSART guidelines

International Nuclear Information System (INIS)

1988-02-01

The IAEA Operational Safety Review Team (OSART) programme provides advice and assistance to Member States to enhance the operational safety of nuclear power plants. These OSART Guidelines provide overall guidance for the experts to ensure the consistency and comprehensiveness of the operational safety review. Specific guidelines are provided as guide for the systematic review in the following areas important to operational safety: management, organization and administration, training and qualification, operations, maintenance, technical support, radiation protection, chemistry, emergency planning and preparedness

Guidelines for authorities and operators from the EURATOM regulation according to nuclear safety

International Nuclear Information System (INIS)

Karpenstein, Ulrich

2010-01-01

At 22nd July, 2009 the guideline 2009/71/EURATOM on a community framework for the nuclear security of nuclear installations comes into effect. A lot of regulations of this guideline intervene very deeply in the competencies of the member states. In acknowledgment of the national responsibility for nuclear security, the guideline grants large free space to the member states. Thereby, the guideline aims at a general legal framework and a mutual learning process off.

System Guidelines for EMC Safety-Critical Circuits: Design, Selection, and Margin Demonstration

Science.gov (United States)

Lawton, R. M.

1996-01-01

Demonstration of safety margins for critical points (circuits) has traditionally been required since it first became a part of systems-level Electromagnetic Compatibility (EMC) requirements of MIL-E-6051C. The goal of this document is to present cost-effective guidelines for ensuring adequate Electromagnetic Effects (EME) safety margins on spacecraft critical circuits. It is for the use of NASA and other government agencies and their contractors to prevent loss of life, loss of spacecraft, or unacceptable degradation. This document provides practical definition and treatment guidance to contain costs within affordable limits.

Guidelines for confirmatory inplant tests of safety-relief valve discharges for BWR plants

International Nuclear Information System (INIS)

Su, T.M.

1981-05-01

Inplant tests of safety/relief valve (SRV) discharges may be required to confirm generically established specifications for SRV loads and the maximum suppression pool temperature, and to evaluate possible effects of plant-unique parameters. These tests are required in those plants which have features that differ substantially from those previously tested. Guidelines for formulating appropriate test matrices, establishing test procedures, selecting necessary instrumentation, and reporting the test results are provided in this report. Guidelines to determine if inplant tests are required on the basis of the plant unique parameters are also included in the report

76 FR 54110 - Attorney General's Guidelines on Implementation of the Provisions of the Voting Rights Act...

Science.gov (United States)

2011-08-31

... rule updates the Attorney General's interpretative guidelines under the language minority provisions of.... Also, on July 26, 2002, the Assistant Attorney General of the Civil Rights Division sent a letter to... of the then-existing Attorney General's interpretative guidelines, 28 CFR part 55. This rule conforms...

OSART Guidelines. 2015 Edition. Reference Report for IAEA Operational Safety Review Teams (OSARTs)

International Nuclear Information System (INIS)

2016-01-01

The IAEA works to provide a global nuclear safety and security framework for the protection of people and the environment from the effects of ionizing radiation, the minimization of the likelihood of accidents that could endanger life and property, and effective mitigation of the effects of any such events, should they occur. The strategic approach to achieving such a framework involves continual improvement in four areas: national and international safety infrastructures; the establishment and global acceptance of IAEA safety standards; an integrated approach to the provision for the application of the safety standards; and a global network of knowledge and experience. The IAEA Operational Safety Review Team (OSART) programme provides advice and assistance to Member States to enhance the safety of nuclear power plants during commissioning and operation. The OSART programme, initiated in 1982, is available to all Member States with nuclear power plants under commissioning or in operation. Conservative design, careful manufacture and sound construction are all prerequisites for the safe operation of nuclear power plants. However, the safety of the plant also depends ultimately on: sound management, policies, procedures, processes and practices; the capability and reliability of commissioning and operating personnel; comprehensive instructions; sound accident management and emergency preparedness; and adequate resources. Finally, a positive attitude and conscientiousness on the part of all staff in discharging their responsibilities is important to safety. The OSART programme is based on the safety standards applicable to nuclear power plants. IAEA safety standards reflect the consensus of Member States on nuclear safety matters. The reports of the International Nuclear Safety Group identify important current nuclear safety issues and also serve as references during an OSART review. The publication OSART Guidelines provides overall guidance on the conduct of OSART

Updating Human Factors Engineering Guidelines for Conducting Safety Reviews of Nuclear Power Plants

International Nuclear Information System (INIS)

O'Hara, J.M.; Higgins, J.; Fleger, Stephen

2011-01-01

The U.S. Nuclear Regulatory Commission (NRC) reviews the human factors engineering (HFE) programs of applicants for nuclear power plant construction permits, operating licenses, standard design certifications, and combined operating licenses. The purpose of these safety reviews is to help ensure that personnel performance and reliability are appropriately supported. Detailed design review procedures and guidance for the evaluations is provided in three key documents: the Standard Review Plan (NUREG-0800), the HFE Program Review Model (NUREG-0711), and the Human-System Interface Design Review Guidelines (NUREG-0700). These documents were last revised in 2007, 2004 and 2002, respectively. The NRC is committed to the periodic update and improvement of the guidance to ensure that it remains a state-of-the-art design evaluation tool. To this end, the NRC is updating its guidance to stay current with recent research on human performance, advances in HFE methods and tools, and new technology being employed in plant and control room design. This paper describes the role of HFE guidelines in the safety review process and the content of the key HFE guidelines used. Then we will present the methodology used to develop HFE guidance and update these documents, and describe the current status of the update program.

Safety of MR liver specific contrast media

Energy Technology Data Exchange (ETDEWEB)

Bellin, Marie-France [Hopital Paul Brousse, Universite Paris 11, Villejuif Cedex (France); Webb, Judith A.W. [St. Bartholomew' s Hospital, Department of Diagnostic Imaging, London (United Kingdom); Molen, Aart J. van der [Leiden University Medical Centre, Department of Radiology, Leiden (Netherlands); Thomsen, Henrik S. [Copenhagen University Hospital at Herlev, Department of Diagnostic Radiology 54E2, Herlev (Denmark); Morcos, Sameh K. [Northern General Hospital, Sheffield Teaching Hospitals NHS Trust, Department of Diagnostic Imaging, Sheffield (United Kingdom)

2005-08-01

Over the past few years a number of magnetic resonance (MR) liver specific contrast agents have been introduced. In this report the safety issues of these agents are addressed. A literature search was carried out. Based on the available information, simple guidelines on the safety issue of liver specific contrast agents have been produced by the Contrast Media Safety Committee of the European Society of Urogenital Radiology. The report and guidelines were discussed at the 11th European Symposium on Urogenital Radiology in Santiago de Compostela. Liver specific contrast agents appear in general to be safe and well tolerated. However, the incidence of adverse reactions with iron oxides and the intravenous manganese based agent seems to be slightly higher than with gadolinium based agents. However, no safety information from comparative clinical trials has been published. Guidelines on the safety aspects are presented. (orig.)

Safety of MR liver specific contrast media

International Nuclear Information System (INIS)

Bellin, Marie-France; Webb, Judith A.W.; Molen, Aart J. van der; Thomsen, Henrik S.; Morcos, Sameh K.

2005-01-01

Over the past few years a number of magnetic resonance (MR) liver specific contrast agents have been introduced. In this report the safety issues of these agents are addressed. A literature search was carried out. Based on the available information, simple guidelines on the safety issue of liver specific contrast agents have been produced by the Contrast Media Safety Committee of the European Society of Urogenital Radiology. The report and guidelines were discussed at the 11th European Symposium on Urogenital Radiology in Santiago de Compostela. Liver specific contrast agents appear in general to be safe and well tolerated. However, the incidence of adverse reactions with iron oxides and the intravenous manganese based agent seems to be slightly higher than with gadolinium based agents. However, no safety information from comparative clinical trials has been published. Guidelines on the safety aspects are presented. (orig.)

Guidelines regarding National Reports under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

2011-01-01

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

Guidelines regarding National Reports under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

2013-01-01

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

Guidelines regarding National Reports under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

2011-01-01

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

IAEA/NEA incident reporting system (IRS). Reporting guidelines. Feedback from safety related operating experience for nuclear power plants

International Nuclear Information System (INIS)

1998-01-01

The Incident Reporting System (IRS) is an international system jointly operated by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organisation for Economic Cooperation and Development (OECD/NEA). The fundamental objective of the IRS is to contribute to improving the safety of commercial nuclear power plants (NPPs) which are operated worldwide. This objective can be achieved by providing timely and detailed information on both technical and human factors related to events of safety significance which occur at these plants. The purpose of these guidelines, which supersede the previous IAEA Safety Series No. 93 (Part II) and the NEA IRS guidelines, is to describe the system and to give users the necessary background and guidance to enable them to produce IRS reports meeting a high standard of quality while retaining the high efficiency of the system expected by all Member States operating nuclear power plants. These guidelines have been jointly developed and approved by the NEA/IAEA

Guidelines prescribed by general practitioners to patients with acute ...

African Journals Online (AJOL)

The aim of this study was to investigate the guidelines prescribed by general practitioners (GPs) to patients with acute low back pain (ALBP) regarding 'return to work'. Methods: A systematic sample of 212 GPs, selected from a list supplied by the Health Professions Council of South Africa (HPCSA), was selected to complete ...

American Association for Dental Schools Curricular Guidelines for Microscopic Anatomy (General and Oral).

Science.gov (United States)

Susi, Frank; Mundell, Robert

1980-01-01

Guidelines developed by the Section on Anatomical Sciences of the American Association for Dental Schools are presented. These guidelines were drawn up as an effort to provide a general criterion-referenced standard against which a school can measure its course content in histology. (MLW)

NASA System Safety Handbook. Volume 2: System Safety Concepts, Guidelines, and Implementation Examples

Science.gov (United States)

Dezfuli, Homayoon; Benjamin, Allan; Everett, Christopher; Feather, Martin; Rutledge, Peter; Sen, Dev; Youngblood, Robert

2015-01-01

This is the second of two volumes that collectively comprise the NASA System Safety Handbook. Volume 1 (NASASP-210-580) was prepared for the purpose of presenting the overall framework for System Safety and for providing the general concepts needed to implement the framework. Volume 2 provides guidance for implementing these concepts as an integral part of systems engineering and risk management. This guidance addresses the following functional areas: 1.The development of objectives that collectively define adequate safety for a system, and the safety requirements derived from these objectives that are levied on the system. 2.The conduct of system safety activities, performed to meet the safety requirements, with specific emphasis on the conduct of integrated safety analysis (ISA) as a fundamental means by which systems engineering and risk management decisions are risk-informed. 3.The development of a risk-informed safety case (RISC) at major milestone reviews to argue that the systems safety objectives are satisfied (and therefore that the system is adequately safe). 4.The evaluation of the RISC (including supporting evidence) using a defined set of evaluation criteria, to assess the veracity of the claims made therein in order to support risk acceptance decisions.

School Safety Policies With Emphasis on Physical Education, Athletics and Recreation.

Science.gov (United States)

American Association for Health, Physical Education, and Recreation, Washington, DC.

This booklet outlines principles of hazard control, school accident problems, and the need for guidelines and policies. Suggested general school safety policies, guidelines for courses in safety education and for the provision of facilities and supplies, policies for the administration of first aid and emergency care, and procedures for reporting…

[Summary of the practice guideline 'Thyroid disorders' (first revision) from the Dutch College of General Practitioners

NARCIS (Netherlands)

Lieshout, J. van; Wessels, P.; Rijswijk, E. van; Boer, A.M; Wiersma, A.; Goudswaard, A.N.

2007-01-01

--The practice guideline 'Thyroid disorders' developed by the Dutch College of General Practitioners replaces the practice guideline 'Functional thyroid disorders' from 1996. Recommendations for palpable thyroid disorders have been added. --Hypothyroidism can often be treated by the general

Dam safety operating guidelines

International Nuclear Information System (INIS)

Elsayed, E.; Leung, T.; Kirkham, A.; Lum, D.

1990-01-01

As part of Ontario Hydro's dam structure assessment program, the hydraulic design review of several river systems has revealed that many existing dam sites, under current operating procedures, would not have sufficient discharge capacity to pass the Inflow Design Flood (IDF) without compromising the integrity of the associated structures. Typical mitigative measures usually considered in dealing with these dam sites include structural alterations, emergency action plans and/or special operating procedures designed for extreme floods. A pilot study was carried out for the Madawaska River system in eastern Ontario, which has seven Ontario Hydro dam sites in series, to develop and evaluate the effectiveness of the Dam Safety Operating Guidelines (DSOG). The DSOG consist of two components: the flood routing schedules and the minimum discharge schedules, the former of which would apply in the case of severe spring flood conditions when the maximum observed snowpack water content and the forecast rainfall depth exceed threshold values. The flood routing schedules would identify to the operator the optimal timing and/or extent of utilizing the discharge facilities at each dam site to minimize the potential for dam failures cased by overtopping anywhere in the system. It was found that the DSOG reduced the number of structures overtopped during probable maximum flood from thirteen to four, while the number of structures that could fail would be reduced from seven to two. 8 refs., 4 figs., 3 tabs

Canadian Association of Gastroenterology Consensus Guidelines on Safety and Quality Indicators in Endoscopy

Directory of Open Access Journals (Sweden)

David Armstrong

2012-01-01

Full Text Available Several organizations worldwide have developed procedure-based guidelines and/or position statements regarding various aspects of quality and safety indicators, and credentialing for endoscopy. Although important, they do not specifically address patient needs or provide a framework for their adoption in the context of endoscopy services. The consensus guidelines reported in this article, however, aimed to identify processes and indicators relevant to the provision of high-quality endoscopy services that will support ongoing quality improvement across many jurisdictions, specifically in the areas of ethics, facility standards and policies, quality assurance, training and education, reporting standards and patient perceptions.

Biological effects of electromagnetic fields and recently updated safety guidelines for strong static magnetic fields

International Nuclear Information System (INIS)

Yamaguchi-Sekino, Sachiko; Sekino, Masaki; Ueno, Shoogo

2011-01-01

Humans are exposed daily to artificial and naturally occurring magnetic fields that originate from many different sources. We review recent studies that examine the biological effects of and medical applications involving electromagnetic fields, review the properties of static and pulsed electromagnetic fields that affect biological systems, describe the use of a pulsed electromagnetic field in combination with an anticancer agent as an example of a medical application that incorporates an electromagnetic field, and discuss the recently updated safety guidelines for static electromagnetic fields. The most notable modifications to the 2009 International Commission on Non-Ionizing Radiation Protection guidelines are the increased exposure limits, especially for those who work with or near electromagnetic fields (occupational exposure limits). The recommended increases in exposure were determined using recent scientific evidence obtained from animal and human studies. Several studies since the 1994 publication of the guidelines have examined the effects on humans after exposure to high static electromagnetic fields (up to 9.4 tesla), but additional research is needed to ascertain further the safety of strong electromagnetic fields. (author)

Radiological risk comparison guidelines

International Nuclear Information System (INIS)

Hallinan, E.J.; Muhlestein, L.D.; Brown, L.F.; Yoder, R.E.

1992-01-01

An important aspect of DOE safety analyses is estimating potential accident risk. The estimates are used to: determine if additional controls are needed, identify Safety Class Items, and demonstrate adequate risk reduction. Thus, guidelines are needed to measure comparative risks. The Westinghouse M ampersand O Nuclear Facility Safety Committee and the Safety Envelope Working Group have developed radiological risk guidelines for comparing the risks from individual accident analyses. These guidelines were prepared under contract with the US Department of Energy. These guidelines are based on historical DOE guidelines and current requirements, and satisfy DOE and technical community proposals. for goals that demonstrate acceptable risk. The guidelines consist of a frequency versus consequence curve for credible accidents. Offsite and onsite guidelines are presented. The offsite risk acceptance guidelines are presented in Figure 1. The guidelines are nearly isorisk for anticipated events where impacts are chronic, and provide additional reduction for unlikely events where impacts may be acute and risk uncertainties may be significant. The guidelines are applied to individual release accident scenarios where a discrete frequency and consequence has been estimated. The guideline curves are not to be used for total risk assessments. Common cause events are taken into consideration only for an individual facility. Frequencies outside the guideline range are considered to be local site option (analyst judgement) as far as assessments of risk acceptance are concerned. If the curve is exceeded, then options include either a more detailed analysis or imposing additional preventive or mitigative features. Another presentation discusses implementation in detail. Additional work is needed to provide risk comparison guidelines for releases from multiple facilities and for toxic releases

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

Guidelines regarding the Review Process under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

2011-01-01

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

Guidelines regarding the review process under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

2002-01-01

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

Guidelines regarding the review process under the convention on nuclear safety

International Nuclear Information System (INIS)

1998-01-01

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

Guidelines regarding the Review Process under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

2011-01-01

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

Guidelines regarding the review process under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

1999-01-01

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

Guidelines regarding the Review Process under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

2011-01-01

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

OSART guidelines - 2005 edition. Reference report for IAEA Operational Safety Review Teams (OSARTs)

International Nuclear Information System (INIS)

2005-01-01

when exchanging ideas, at the working level, for enhancing safety. The OSART programme is based on the IAEA's Nuclear Safety Standard Series (Fundamentals, Requirements and Safety Guides) for nuclear power plants and the Basic Safety Standards for Radiation Protection. The Nuclear Safety Standards reflect the consensus of Member States on nuclear safety matters. The reports of the International Nuclear Safety Advisory Group, identifying important current nuclear safety issues also serve as references during an OSART review. The OSART Guidelines provide overall guidance for the experts to ensure the consistency and comprehensiveness of the operational safety review. Additional guidance and reference material prepared by the IAEA and the expertise of the OSART members contribute to the bases of the review. OSART reviews are performance oriented in that they accept different approaches to commissioning and operational safety that represent good practices and may contribute to ensuring a good safety record on the part of the operating organization. Recommendations are made on items of direct relevance to safety, whereas suggestions made might enhance plant safety indirectly but would certainly improve performance. Commendable good practices identified at plants are communicated to other plants where relevant in order to effect improvements. This revision of the OSART guidelines supersedes the 1994 Edition (IAEA-TECDOC-744)

OSART guidelines - 2005 edition. Reference report for IAEA Operational Safety Review Teams (OSARTs)

International Nuclear Information System (INIS)

2007-01-01

when exchanging ideas, at the working level, for enhancing safety. The OSART programme is based on the IAEA's Nuclear Safety Standard Series (Fundamentals, Requirements and Safety Guides) for nuclear power plants and the Basic Safety Standards for Radiation Protection. The Nuclear Safety Standards reflect the consensus of Member States on nuclear safety matters. The reports of the International Nuclear Safety Advisory Group, identifying important current nuclear safety issues also serve as references during an OSART review. The OSART Guidelines provide overall guidance for the experts to ensure the consistency and comprehensiveness of the operational safety review. Additional guidance and reference material prepared by the IAEA and the expertise of the OSART members contribute to the bases of the review. OSART reviews are performance oriented in that they accept different approaches to commissioning and operational safety that represent good practices and may contribute to ensuring a good safety record on the part of the operating organization. Recommendations are made on items of direct relevance to safety, whereas suggestions made might enhance plant safety indirectly but would certainly improve performance. Commendable good practices identified at plants are communicated to other plants where relevant in order to effect improvements. This revision of the OSART guidelines supersedes the 1994 Edition (IAEA-TECDOC-744)

OSART guidelines - 2005 edition. Reference report for IAEA Operational Safety Review Teams (OSARTs)

International Nuclear Information System (INIS)

2008-01-01

when exchanging ideas, at the working level, for enhancing safety. The OSART programme is based on the IAEA's Nuclear Safety Standard Series (Fundamentals, Requirements and Safety Guides) for nuclear power plants and the Basic Safety Standards for Radiation Protection. The Nuclear Safety Standards reflect the consensus of Member States on nuclear safety matters. The reports of the International Nuclear Safety Advisory Group, identifying important current nuclear safety issues also serve as references during an OSART review. The OSART Guidelines provide overall guidance for the experts to ensure the consistency and comprehensiveness of the operational safety review. Additional guidance and reference material prepared by the IAEA and the expertise of the OSART members contribute to the bases of the review. OSART reviews are performance oriented in that they accept different approaches to commissioning and operational safety that represent good practices and may contribute to ensuring a good safety record on the part of the operating organization. Recommendations are made on items of direct relevance to safety, whereas suggestions made might enhance plant safety indirectly but would certainly improve performance. Commendable good practices identified at plants are communicated to other plants where relevant in order to effect improvements. This revision of the OSART guidelines supersedes the 1994 Edition (IAEA-TECDOC-744)

Canadian Association of Gastroenterology consensus guidelines on safety and quality indicators in endoscopy.

Science.gov (United States)

Armstrong, David; Barkun, Alan; Bridges, Ron; Carter, Rose; de Gara, Chris; Dube, Catherine; Enns, Robert; Hollingworth, Roger; Macintosh, Donald; Borgaonkar, Mark; Forget, Sylviane; Leontiadis, Grigorios; Meddings, Jonathan; Cotton, Peter; Kuipers, Ernst J

2012-01-01

Increasing use of gastrointestinal endoscopy, particularly for colorectal cancer screening, and increasing emphasis on health care quality, highlight the need for clearly defined, evidence-based processes to support quality improvement in endoscopy. To identify processes and indicators of quality and safety relevant to high-quality endoscopy service delivery. A multidisciplinary group of 35 voting participants developed recommendation statements and performance indicators. Systematic literature searches generated 50 initial statements that were revised iteratively following a modified Delphi approach using a web-based evaluation and voting tool. Statement development and evidence evaluation followed the AGREE (Appraisal of Guidelines, REsearch and Evaluation) and GRADE (Grading of Recommendations, Assessment, Development and Evaluation) guidelines. At the consensus conference, participants voted anonymously on all statements using a 6-point scale. Subsequent web-based voting evaluated recommendations for specific, individual quality indicators, safety indicators and mandatory endoscopy reporting fields. Consensus was defined a priori as agreement by 80% of participants. Consensus was reached on 23 recommendation statements addressing the following: ethics (statement 1: agreement 100%), facility standards and policies (statements 2 to 9: 90% to 100%), quality assurance (statements 10 to 13: 94% to 100%), training, education, competency and privileges (statements 14 to 19: 97% to 100%), endoscopy reporting standards (statements 20 and 21: 97% to 100%) and patient perceptions (statements 22 and 23: 100%). Additionally, 18 quality indicators (agreement 83% to 100%), 20 safety indicators (agreement 77% to 100%) and 23 recommended endoscopy-reporting elements (agreement 91% to 100%) were identified. The consensus process identified a clear need for high-quality clinical and outcomes research to support quality improvement in the delivery of endoscopy services. The

Guidelines for Safety Evaluation of a Potential for PWR Steam Generator Tube Failure due to Fluid elastic Instability

Energy Technology Data Exchange (ETDEWEB)

Jo, Jong Chull; Do, Kyu Sik; Sheen, Cheol [Nuclear System Evaluation Dept., Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2013-05-15

It was found that both SG tube rupture events occurred at North Anna Unit 1 in 1987 and at Mihama Unit 2 in 1991 were caused by a high cycle fatigue due to fluid elastic instability. Therefore, with regard to nuclear safety it is important to design the SG properly in a conservative manner so that the potential for SG U-tube failures due to fluid elastic instability can be minimized. This article provides guidelines for assessing the potential for SG U-tube damage due to fluid elastic instability. This article described guidelines for safety evaluation of a potential for PWR steam generator tube failure due to fluid elastic instability. The guidelines address the requirements for realistically performing the SG thermal-hydraulic analysis and the modal analysis of tubes as well as the criteria for conservatively determining the added mass, the damping ratio and the fluid elastic instability coefficient. The guidelines can be used to predict the potential SG tubes which are susceptible to failure due to fluid elastic instability at operating nuclear power plants and also to evaluate the safety and structural integrity of new SG designs at the licensing review stage. Failure of a pressurized water reactor (PWR) steam generator (SG) tube leads to a leakage of contaminated primary coolant to the secondary system, which has serious safety implications such as the potential for direct release of radioactive fission products to the environment and the loss of coolant. Excessive tube vibration excited by dynamic forces of internal or external fluid flow is called flow-induced vibration (FIV). Among the FIV mechanisms, the so-called fluid elastic instability of SG tubes in cross flow is the most important safety issue in the design of SGs because it may cause severe tube failure in a very short time.

State of the art of probabilistic safety analysis (PSA) in the FRG, and principles of a PSA-guideline

International Nuclear Information System (INIS)

Balfanz, H.P.

1987-01-01

Contents of the articles: Survey of PSA performed during licensing procedures of an NPP; German Nuclear Standards' requirements on the reliability of safety systems; PSA-guideline for NPP: Principles and suggestions; Motivation and tasks of PSA; Aspects of the methodology of safety analyses; Structure of event tree and fault tree analyses; Extent of safety analyses; Performance and limits of PSA. (orig./HSCH)

Workplace health and safety during pandemic influenza : CAGC guideline

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-11-15

Pandemic influenza is a possible biological hazard that employers must take into account during hazard assessment and emergency planning. This report presented a guideline to all workplaces in Alberta and provided information on legislated requirements, best practices, guidelines and strategies in workplace health and safety and employment standards in the event of a pandemic influenza. The report explained the difference between a pandemic and a pandemic influenza, and why scientists expect another pandemic influenza. Pandemic influenza was described as being different from seasonal influenza. This document also explained how pandemic influenza relates to the worker and the workplace, and how the workplace can prepare for and respond to pandemic influenza. Pandemic influenza hazard categories were also listed along with steps in the hazard assessment and control of pandemic influenza. The steps involve listing the types of work and work-related activities; identifying the hazard; assessing the hazards; implementing controls; communicating the information to workers and providing training; and evaluating the effectiveness of controls. The guide also addressed emergency response plan development for pandemic influenza; first aid; and employment standards during pandemic influenza. refs., tabs.

Guidelines regarding the Review Process under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

2013-01-01

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

Guidelines regarding the Review Process under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

2013-01-01

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

Guidelines regarding the Review Process under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

2013-01-01

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

A study on the establishment of safety assessment guidelines of commercial grade item dedication in digitalized safety systems

International Nuclear Information System (INIS)

Hwang, H. S.; Kim, B. R.; Oh, S. H.

1999-01-01

Because of obsolescing the components used in safety related systems of nuclear power plants, decreasing the number of suppliers qualified for the nuclear QA program and increasing maintenance costs of them, utilities have been considering to use commercial grade digital computers as an alternative for resolving such issues. However, commercial digital computers use the embedded pre-existing software, including operating system software, which are not developed by using nuclear grade QA program. Thus, it is necessary for utilities to establish processes for dedicating digital commercial grade items. A regulatory body also needs guidance to evaluate the digital commercial products properly. This paper surveyed the regulations and their regulatory guides, which establish the requirements for commercial grade items dedication, industry standards and guidances applicable to safety related systems. This paper provides some guidelines to be applied in evaluating the safety of digital upgrades and new digital plant protection systems in Korea

A Handbook for Public Playground Safety. Volume II: Technical Guidelines for Equipment and Surfacing.

Science.gov (United States)

Consumer Product Safety Commission, Washington, DC.

This handbook suggests safety guidelines for public playground equipment and describes various surfaces used under the equipment and possible injuries resulting from falls. The handbook is intended for use mainly by manufacturers, installers, school and park officials, and others interested in technical criteria for public playground equipment.…

[The practice guideline 'Anemia' from the Dutch College of General Practitioners; a response from the perspective of general practice medicine

NARCIS (Netherlands)

Bosch, W.J.H.M. van den

2003-01-01

The practice guideline 'Anaemia' from the Dutch College of General Practitioners will certainly be a support for the Dutch general practitioner. The inclusion of an algorithm to make a more precise diagnosis is an experiment that needs to be evaluated in the near future. However, many general

SU-E-P-43: A Knowledge Based Approach to Guidelines for Software Safety

International Nuclear Information System (INIS)

Salomons, G; Kelly, D

2015-01-01

Purpose: In the fall of 2012, a survey was distributed to medical physicists across Canada. The survey asked the respondents to comment on various aspects of software development and use in their clinic. The survey revealed that most centers employ locally produced (in-house) software of some kind. The respondents also indicated an interest in having software guidelines, but cautioned that the realities of cancer clinics include variations, that preclude a simple solution. Traditional guidelines typically involve periodically repeating a set of prescribed tests with defined tolerance limits. However, applying a similar formula to software is problematic since it assumes that the users have a perfect knowledge of how and when to apply the software and that if the software operates correctly under one set of conditions it will operate correctly under all conditions Methods: In the approach presented here the personnel involved with the software are included as an integral part of the system. Activities performed to improve the safety of the software are done with both software and people in mind. A learning oriented approach is taken, following the premise that the best approach to safety is increasing the understanding of those associated with the use or development of the software. Results: The software guidance document is organized by areas of knowledge related to use and development of software. The categories include: knowledge of the underlying algorithm and its limitations; knowledge of the operation of the software, such as input values, parameters, error messages, and interpretation of output; and knowledge of the environment for the software including both data and users. Conclusion: We propose a new approach to developing guidelines which is based on acquiring knowledge-rather than performing tests. The ultimate goal is to provide robust software guidelines which will be practical and effective

SU-E-P-43: A Knowledge Based Approach to Guidelines for Software Safety

Energy Technology Data Exchange (ETDEWEB)

Salomons, G [Cancer Center of Southeastern Ontario & Queen’s University, Kingston, ON (Canada); Kelly, D [Royal Military College of Canada, Kingston, ON, CA (Canada)

2015-06-15

Purpose: In the fall of 2012, a survey was distributed to medical physicists across Canada. The survey asked the respondents to comment on various aspects of software development and use in their clinic. The survey revealed that most centers employ locally produced (in-house) software of some kind. The respondents also indicated an interest in having software guidelines, but cautioned that the realities of cancer clinics include variations, that preclude a simple solution. Traditional guidelines typically involve periodically repeating a set of prescribed tests with defined tolerance limits. However, applying a similar formula to software is problematic since it assumes that the users have a perfect knowledge of how and when to apply the software and that if the software operates correctly under one set of conditions it will operate correctly under all conditions Methods: In the approach presented here the personnel involved with the software are included as an integral part of the system. Activities performed to improve the safety of the software are done with both software and people in mind. A learning oriented approach is taken, following the premise that the best approach to safety is increasing the understanding of those associated with the use or development of the software. Results: The software guidance document is organized by areas of knowledge related to use and development of software. The categories include: knowledge of the underlying algorithm and its limitations; knowledge of the operation of the software, such as input values, parameters, error messages, and interpretation of output; and knowledge of the environment for the software including both data and users. Conclusion: We propose a new approach to developing guidelines which is based on acquiring knowledge-rather than performing tests. The ultimate goal is to provide robust software guidelines which will be practical and effective.

New set of Chemical Safety rules

CERN Multimedia

HSE Unit

2011-01-01

A new set of four Safety Rules was issued on 28 March 2011: Safety Regulation SR-C ver. 2, Chemical Agents (en); General Safety Instruction GSI-C1, Prevention and Protection Measures (en); General Safety Instruction GSI-C2, Explosive Atmospheres (en); General Safety Instruction GSI-C3, Monitoring of Exposure to Hazardous Chemical Agents in Workplace Atmospheres (en). These documents form part of the CERN Safety Rules and are issued in application of the “Staff Rules and Regulations” and of document SAPOCO 42. These documents set out the minimum requirements for the protection of persons from risks to their occupational safety and health arising, or likely to arise, from the effects of hazardous chemical agents that are present in the workplace or used in any CERN activity. Simultaneously, the HSE Unit has published seven Safety Guidelines and six Safety Forms. These documents are available from the dedicated Web page “Chemical, Cryogenic and Biological Safety&...

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

International Nuclear Information System (INIS)

1996-05-01

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

Overview of IAEA guidelines for fire safety inspection and operation in nuclear power plants

International Nuclear Information System (INIS)

Mowrer, D.S.

1998-01-01

In 1992, the International Atomic Energy Agency began an ambitious project on fire safety in nuclear power plants. The purpose of this ongoing project is to provide specific guidance on compliance with the requirements set forth through the IAEA Nuclear Safety Standards program established in 1974. The scope of the Fire Safety project encompasses several tasks, including the development of new standards and guidelines to assist Member States in assessing the level of fire safety in existing plants. Five new Safety Practices, one new Safety Guide and a Technical Document have been developed for use by the fire safety community. The primary intent of these new documents is to provide detailed guidance and a consistent format for the assessment of the overall level of fire safety being provided in existing nuclear power plants around the world and especially in developing countries. Sufficient detail is provided in the Safety Guide and Safety Practices to allow technically knowledgeable plant personnel, outside consultants or other technical experts to assess the adequacy of fire safety within the plant facilities. This paper describes topics addressed by each of the IAEA Fire Safety documents and discussed the relationship of each document to others in the series. (author)

Formalized 2003 ESH/ESC Hypertension Guidelines in Hospital and General Practice

Czech Academy of Sciences Publication Activity Database

Peleška, Jan; Anger, Z.; Buchtela, David; Tomečková, Marie; Veselý, Arnošt; Zvárová, Jana

22 Suppl. 2, - (2004), s. 253 ISSN 0263-6352. [European Meeting on Hypertension /14./. 13.06.2004-17.06.2004, Paris] R&D Projects: GA MŠk LN00B107 Keywords : hypertension guidelines * electronic form Subject RIV: BA - General Mathematics

RSK-guidelines for PWR reactors

International Nuclear Information System (INIS)

1979-01-01

The RSK guidelines for PWA reactors of April 24, 1974, have been revised and amended in this edition. The RSK presents a summary of safety requirements to be observed in the design, construction, and operation of PWR reactors in the form of guidelines. From January 1979 onwards these guidelines will be the basis of siting and safety considerations for new PWR reactors, and newly built nuclear power plants will have to form these guidelines. They are not binding for existing nuclear power plants under construction or in operation. It will be a matter of individual discussion whether or not the guidelines will be applied in these plants. The main purpose of the guidelines is to facilitate discussion among RSK members and to give early information on necessary safety requirements. If the guidelines are observed by producers and operators, the RSK will make statements on individual projects at short notice. (orig./HP) [de

IRIS guidelines. 2014 ed. Integrated Review of Infrastructure for Safety (IRIS) for self-assessment when establishing the safety infrastructure for a nuclear power programme

International Nuclear Information System (INIS)

2014-01-01

The IAEA safety standards reflect an international consensus on what constitutes a high level of safety for protecting people and the environment, and therefore represent what all Member States should achieve, whilst recognizing the ultimate responsibility of each State to ensure safety when implementing a nuclear power programme. IAEA Safety Standards Series No. SSG-16, entitled Establishing the Safety Infrastructure for a Nuclear Power Programme was published in order to provide recommendations, presented in the form of sequential actions, on meeting safety requirements progressively during the initial three phases of the development of safety, as described in INSAG-22, Nuclear Safety Infrastructure for a National Nuclear Power Programme Supported by the IAEA Fundamental Safety Principles. To that end, the 200 safety related actions, which are proposed by SSG-16, constitute a roadmap to establish a foundation for promoting a high level of safety over the entire lifetime of the nuclear power plant. These actions reflect international consensus on good practice in order to achieve full implementation of IAEA safety standards. The IAEA has developed a methodology and tool, the Integrated Review of Infrastructure for Safety (IRIS), to assist States in undertaking self-assessment with respect to SSG-16 recommendations when establishing the safety infrastructure for a nuclear power programme, and to develop an action plan for improvement. The IRIS methodology and the associated tool are fully compatible with the IAEA safety standards and are also used, when appropriate, in the preparation of review missions, such as the Integrated Regulatory Review Service and advisory missions. The present guidelines describe the IRIS methodology for self-assessment against SSG-16 recommendations. Through IRIS implementation, every organization concerned with nuclear safety may gain proper awareness and engage in a continuous progressive process to develop the effective national

Development of safety and regulatory requirements for Korean next generation reactor - Development of human factors design review guidelines (II)

Energy Technology Data Exchange (ETDEWEB)

Lee, Jung Woon; Oh, In Suk; Lee, Hyun Chul; Cheon, Se Woo [Korea Atomic Energy Research Institute, Taejon (Korea)

1999-02-01

The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: '25. Human Factors Engineering Program Review Model' and '26. Review Criteria for Human Factors Aspects of Advanced Controls and Instrumentation', which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and the characteristics of the KNGR design, and reviewing the reference documents of NURGE-0711. We also computerized the Korean version of NUREG-0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides at KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system design review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm systems. Then we updated the guidelines by reviewing the literature related to alarm design that published after 1994. 12 refs., 11 figs., 2 tabs. (Author)

Development of safety and regulatory requirements for Korean next generation reactor - Development of human factors design review guidelines (II)

Energy Technology Data Exchange (ETDEWEB)

Lee, Jung Woon; Oh, In Suk; Lee, Hyun Chul; Cheon, Se Woo [Korea Atomic Energy Research Institute, Taejon (Korea)

1999-02-01

The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: '25. Human Factors Engineering Program Review Model' and '26. Review Criteria for Human Factors Aspects of Advanced Controls and Instrumentation', which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and the characteristics of the KNGR design, and reviewing the reference documents of NURGE-0711. We also computerized the Korean version of NUREG-0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides at KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system design review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm systems. Then we updated the guidelines by reviewing the literature related to alarm design that published after 1994. 12 refs., 11 figs., 2 tabs. (Author)

General safety orientations of the Jules Horowitz Reactor Project (JHRP)

International Nuclear Information System (INIS)

Tremodeux, P.; Fiorini, G.L.

2000-01-01

After a brief reminder of the JHR purpose, the document outlines the General Safety related Orientations/Recommendations used for the design and the safety assessment of the facility. As far as the JHR design is new, the safety philosophy adopted for this reactor will be as consistent as possible with that recommended for future (power...) reactors. The general recommendations developed in the paper are: the general nuclear safety approach for the design, operation and analysis with, in particular, the adoption of the Defence In Depth principle; the general safety objectives in terms of radiological consequences; the use of Probabilistic Safety Studies; quality assurance. The 'Defence in Depth' concept using amongst others the 'Barrier' principle remains the basis of the JHR safety. 'Defence In Depth' is applied both to design and operation. Its adequacy is checked during the safety assessment and the paper gives the technical recommendations that should allow the designer to implement this concept into the final design. Built mainly for experimental irradiation the JHR facilities will be handled according to conventional or new operation rules which could put materials under stress and entail handling errors. Specific recommendations are defined to take into account the corresponding peculiarities; they are discussed in the paper. The safety design of the JHR takes into account the experience accumulated through the CEA experimental irradiation programmes, which represents several dozen reactor years; the consultation of CEA reactor facilities operators is ongoing. The corresponding feedback is shortly described. Recommendations related to maintenance and associated operation are indicated as well as those regarding the human factor. Details are given on the JHR safety practical implementation through the CEA/DRN Safety approach. Details of the corresponding Safety Objectives are also discussed. Finally the designer position on the role of probabilistic safety

Usability and Safety in Electronic Medical Records Interface Design: A Review of Recent Literature and Guideline Formulation.

Science.gov (United States)

Zahabi, Maryam; Kaber, David B; Swangnetr, Manida

2015-08-01

The objectives of this study were to (a) review electronic medical record (EMR) and related electronic health record (EHR) interface usability issues, (b) review how EMRs have been evaluated with safety analysis techniques along with any hazard recognition, and (c) formulate design guidelines and a concept for enhanced EMR interfaces with a focus on diagnosis and documentation processes. A major impact of information technology in health care has been the introduction of EMRs. Although numerous studies indicate use of EMRs to increase health care quality, there remain concerns with usability issues and safety. A literature search was conducted using Compendex, PubMed, CINAHL, and Web of Science databases to find EMR research published since 2000. Inclusion criteria included relevant English-language papers with subsets of keywords and any studies (manually) identified with a focus on EMR usability. Fifty studies met the inclusion criteria. Results revealed EMR and EHR usability problems to include violations of natural dialog, control consistency, effective use of language, effective information presentation, and customization principles as well as a lack of error prevention, minimization of cognitive load, and feedback. Studies focusing on EMR system safety made no objective assessments and applied only inductive reasoning methods for hazard recognition. On the basis of the identified usability problems and structure of safety analysis techniques, we provide EMR design guidelines and a design concept focused on the diagnosis process and documentation. The design guidelines and new interface concept can be used for prototyping and testing enhanced EMRs. © 2015, Human Factors and Ergonomics Society.

IAEA guidance on ageing management for nuclear power plants. Guidance on effective management of the physical ageing of systems, structures and components important to safety for nuclear power plants. Overview. Programmatic guidelines. Component specific guidelines. Review guidelines. Version 1, 2002

International Nuclear Information System (INIS)

2002-01-01

Operational experience shows that excellent plant safety and excellent performance go hand in hand, and that they are achieved by effective leadership and management that includes a unified approach to safety and production. This is also applicable to ageing management. Effective ageing management leads to both enhanced plant safety and enhanced performance and is a prerequisite for long service life. The IAEA project on Safety Aspects of NPP Ageing has produced since 1990 a comprehensive set of programmatic and component specific guidelines on managing ageing, while providing an interactive environment for information exchange and co-operation among practitioners, and has assisted Member States in the application of the guidelines through the provision of training and advice. The objective of the CD-ROM is to preserve the IAEA's guidance on ageing management and to facilitate its retrieval, updating, extension and dissemination in order to help increase the effectiveness of ageing management at nuclear power plants

Attorney General forces Infectious Diseases Society of America to redo Lyme guidelines due to flawed development process.

Science.gov (United States)

Johnson, L; Stricker, R B

2009-05-01

Lyme disease is one of the most controversial illnesses in the history of medicine. In 2006 the Connecticut Attorney General launched an antitrust investigation into the Lyme guidelines development process of the Infectious Diseases Society of America (IDSA). In a recent settlement with IDSA, the Attorney General noted important commercial conflicts of interest and suppression of scientific evidence that had tainted the guidelines process. This paper explores two broad ethical themes that influenced the IDSA investigation. The first is the growing problem of conflicts of interest among guidelines developers, and the second is the increasing centralisation of medical decisions by insurance companies, which use treatment guidelines as a means of controlling the practices of individual doctors and denying treatment for patients. The implications of the first-ever antitrust investigation of medical guidelines and the proposed model to remediate the tainted IDSA guidelines process are also discussed.

A Review of General Aviation Safety (1984-2017).

Science.gov (United States)

Boyd, Douglas D

2017-07-01

General aviation includes all civilian aviation apart from operations involving paid passenger transport. Unfortunately, this category of aviation holds a lackluster safety record, accounting for 94% of civil aviation fatalities. In 2014, of 1143 general aviation accidents, 20% were fatal compared with 0 of 29 airline mishaps in the United States. Herein, research findings over the past 30 yr will be reviewed. Accident risk factors (e.g., adverse weather, geographical region, post-impact fire, gender differences) will be discussed. The review will also summarize the development and implementation of stringent crashworthiness designs with multi-axis dynamic testing and head-injury protection and its impact on mitigating occupant injury severity. The benefits and drawbacks of new technology and human factor considerations associated with increased general aviation automation will be debated. Data on the safety of the aging general aviation population and increased drug usage will also be described. Finally, areas in which general aviation occupant survival could be improved and injury severity mitigated will be discussed with the view of equipping aircraft with 1) crash-resistant fuel tanks to reduce post-impact conflagration; 2) after-market ballistic parachutes for older aircraft; and 3) current generation electronic locator beacons to hasten site access by first responders.Boyd DD. A review of general aviation safety (1984-2017). Aerosp Med Hum Perform. 2017; 88(7):657-664.

Implementation guidelines for seismic PSA

International Nuclear Information System (INIS)

Coman, Ovidiu; Samaddar, Sujit; Hibino, Kenta; )

2014-01-01

The presentation was devoted to development of guidelines for implementation of a seismic PSA. If successful, these guidelines can close an important gap. ASME/ANS PRA standards and the related IAEA Safety Guide (IAEA NS-G-2.13) describe capability requirements for seismic PSA in order to support risk-informed applications. However, practical guidance on how to meet these requirements is limited. Such guidelines could significantly contribute to improving risk-informed safety demonstration, safety management and decision making. Extensions of this effort to further PSA areas, particularly to PSA for other external hazards, can enhance risk-informed applications

OSART guidelines. 1992 edition

International Nuclear Information System (INIS)

1992-01-01

The IAEA Operational Safety Review Team (OSART) Guidelines provide overall guidance for the experts to ensure the consistency and comprehensiveness of the operational safety review. Specific guidelines are provided as a guide for the systematic review in the following areas important to operational safety: management, organization and administration, training and qualification, operations, maintenance, technical support, radiation protection, chemistry, emergency planning and preparedness. Additional guidance and reference material has been prepared by the IAEA to complement the expertise of the OSART members

The development and evaluation of guidelines for the review of advanced human-system interfaces

International Nuclear Information System (INIS)

O'Hara, J.M.; Wachtel, J.

1992-01-01

Advanced control rooms for future nuclear power plants are being designed utilizing computer-based technologies. The US Nuclear Regulatory Commission reviews the human engineering aspects of such control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported in order to protect public health and safety. This paper describes a general approach to advanced human-system interface review, development of human factors guidelines to support NRC safety reviews of advanced systems, and the results of a guideline test and evaluation program

Programming Guidelines for FBD Programs in Reactor Protection System Software

International Nuclear Information System (INIS)

Jung, Se Jin; Lee, Dong Ah; Kim, Eui Sub; Yoo, Jun Beom; Lee, Jang Su

2014-01-01

Properties of programming languages, such as reliability, traceability, etc., play important roles in software development to improve safety. Several researches are proposed guidelines about programming to increase the dependability of software which is developed for safety critical systems. Misra-c is a widely accepted programming guidelines for the C language especially in the sector of vehicle industry. NUREG/CR-6463 helps engineers in nuclear industry develop software in nuclear power plant systems more dependably. FBD (Function Block Diagram), which is one of programming languages defined in IEC 61131-3 standard, is often used for software development of PLC (programmable logic controllers) in nuclear power plants. Software development for critical systems using FBD needs strict guidelines, because FBD is a general language and has easily mistakable elements. There are researches about guidelines for IEC 61131-3 programming languages. They, however, do not specify details about how to use languages. This paper proposes new guidelines for the FBD based on NUREG/CR-6463. The paper introduces a CASE (Computer-Aided Software Engineering) tool to check FBD programs with the new guidelines and shows availability with a case study using a FBD program in a reactor protection system. The paper is organized as follows

Programming Guidelines for FBD Programs in Reactor Protection System Software

Energy Technology Data Exchange (ETDEWEB)

Jung, Se Jin; Lee, Dong Ah; Kim, Eui Sub; Yoo, Jun Beom [Division of Computer Science and Engineering College of Information and Communication, Konkuk University, Seoul (Korea, Republic of); Lee, Jang Su [Man-Machine Interface System team Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2014-10-15

Properties of programming languages, such as reliability, traceability, etc., play important roles in software development to improve safety. Several researches are proposed guidelines about programming to increase the dependability of software which is developed for safety critical systems. Misra-c is a widely accepted programming guidelines for the C language especially in the sector of vehicle industry. NUREG/CR-6463 helps engineers in nuclear industry develop software in nuclear power plant systems more dependably. FBD (Function Block Diagram), which is one of programming languages defined in IEC 61131-3 standard, is often used for software development of PLC (programmable logic controllers) in nuclear power plants. Software development for critical systems using FBD needs strict guidelines, because FBD is a general language and has easily mistakable elements. There are researches about guidelines for IEC 61131-3 programming languages. They, however, do not specify details about how to use languages. This paper proposes new guidelines for the FBD based on NUREG/CR-6463. The paper introduces a CASE (Computer-Aided Software Engineering) tool to check FBD programs with the new guidelines and shows availability with a case study using a FBD program in a reactor protection system. The paper is organized as follows.

Guideline for collection, analysis and presentation of safety data in clinical trials of vaccines in pregnant women

Science.gov (United States)

Jones, Christine E.; Munoz, Flor M.; Spiegel, Hans M.L.; Heininger, Ulrich; Zuber, Patrick L.F.; Edwards, Kathryn M.; Lambach, Philipp; Neels, Pieter; Kohl, Katrin S.; Gidudu, Jane; Hirschfeld, Steven; Oleske, James M.; Khuri-Bulos, Najwa; Bauwens, Jorgen; Eckert, Linda O.; Kochhar, Sonali; Bonhoeffer, Jan; Heath, Paul T.

2017-01-01

Vaccination during pregnancy is increasingly being used as an effective approach for protecting both young infants and their mothers from serious infections. Drawing conclusions from published studies in this area can be difficult because of the inability to compare vaccine trial results across different studies and settings due to the heterogeneity in the definitions of terms used to assess the safety of vaccines in pregnancy and the data collected in such studies. The guidelines proposed in this document have been developed to harmonize safety data collection in all phases of clinical trials of vaccines in pregnant women and apply to data from the mother, fetus and infant. Guidelines on the prioritization of the data to be collected is also provided to allow applicability in various geographic, cultural and resource settings, including high, middle and low-income countries. PMID:27481360

Nuclear space power safety and facility guidelines study

International Nuclear Information System (INIS)

Mehlman, W.F.

1995-01-01

This report addresses safety guidelines for space nuclear reactor power missions and was prepared by The Johns Hopkins University Applied Physics Laboratory (JHU/APL) under a Department of Energy grant, DE-FG01-94NE32180 dated 27 September 1994. This grant was based on a proposal submitted by the JHU/APL in response to an open-quotes Invitation for Proposals Designed to Support Federal Agencies and Commercial Interests in Meeting Special Power and Propulsion Needs for Future Space Missionsclose quotes. The United States has not launched a nuclear reactor since SNAP 10A in April 1965 although many Radioisotope Thermoelectric Generators (RTGs) have been launched. An RTG powered system is planned for launch as part of the Cassini mission to Saturn in 1997. Recently the Ballistic Missile Defense Office (BMDO) sponsored the Nuclear Electric Propulsion Space Test Program (NEPSTP) which was to demonstrate and evaluate the Russian-built TOPAZ II nuclear reactor as a power source in space. As of late 1993 the flight portion of this program was canceled but work to investigate the attributes of the reactor were continued but at a reduced level. While the future of space nuclear power systems is uncertain there are potential space missions which would require space nuclear power systems. The differences between space nuclear power systems and RTG devices are sufficient that safety and facility requirements warrant a review in the context of the unique features of a space nuclear reactor power system

Scandinavian clinical practice guidelines on general anaesthesia for emergency situations

DEFF Research Database (Denmark)

Gadegaard Jensen, Anders; Callesen, T; Hagemo, J S

2010-01-01

Emergency patients need special considerations and the number and severity of complications from general anaesthesia can be higher than during scheduled procedures. Guidelines are therefore needed. The Clinical Practice Committee of the Scandinavian Society of Anaesthesiology and Intensive Care...... Medicine appointed a working group to develop guidelines based on literature searches to assess evidence, and a consensus meeting was held. Consensus opinion was used in the many topics where high-grade evidence was unavailable. The recommendations include the following: anaesthesia for emergency patients...... breathing for 3 min or eight deep breaths over 60 s and oxygen flow 10 l/min should be used. Pre-oxygenation in the obese patients should be performed in the head-up position. The use of cricoid pressure is not considered mandatory, but can be used on individual judgement. The hypnotic drug has a minor...

UMTRA Project environmental, health, and safety plan

International Nuclear Information System (INIS)

1989-02-01

The basic health and safety requirements established in this plan are designed to provide guidelines to be applied at all Uranium Mill Tailings Remedial Action (UMTRA) Project sites. Specific restrictions are given where necessary. However, an attempt has been made to provide guidelines which are generic in nature, and will allow for evaluation of site-specific conditions. Health and safety personnel are expected to exercise professional judgment when interpreting these guidelines to ensure the health and safety of project personnel and the general population. This UMTRA Project Environmental, Health, and Safety (EH ampersand S) Plan specifies the basic Federal health and safety standards and special DOE requirements applicable to this program. In addition, responsibilities in carrying out this plan are delineated. Some guidance on program requirements and radiation control and monitoring is also included. An Environmental, Health, and Safety Plan shall be developed as part of the remedial action plan for each mill site and associated disposal site. Special conditions at the site which may present potential health hazards will be described, and special areas that should should be addressed by the Remedial Action Contractor (RAC) will be indicated. Site-specific EH ampersand S concerns will be addressed by special contract conditions in RAC subcontracts. 2 tabs

Guidelines for safety related telecommunications systems on normally unattended fixed offshore installations

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-12-01

Guidance is given on the design of telecommunications systems required for safety purposes on normally unattended offshore installations associated with oil and gas production on the United Kingdom continental shelf. The guidelines are mainly concerned with ensuring that: while the installation is unattended, its operation can be remotely monitored and controlled effectively to prevent the escalation of any abnormal situation; the installation can be safely approached when it is necessary to transfer personnel on board; persons on board, for example for inspection or maintenance activities, are safe. (UK)

K-Basins design guidelines

International Nuclear Information System (INIS)

Roe, N.R.; Mills, W.C.

1995-06-01

The purpose of the design guidelines is to enable SNF and K Basin personnel to complete fuel and sludge removal, and basin water mitigation by providing engineering guidance for equipment design for the fuel basin, facility modifications (upgrades), remote tools, and new processes. It is not intended to be a purchase order reference for vendors. The document identifies materials, methods, and components that work at K Basins; it also Provides design input and a technical review process to facilitate project interfaces with operations in K Basins. This document is intended to compliment other engineering documentation used at K Basins and throughout the Spent Nuclear Fuel Project. Significant provisions, which are incorporated, include portions of the following: General Design Criteria (DOE 1989), Standard Engineering Practices (WHC-CM-6-1), Engineering Practices Guidelines (WHC 1994b), Hanford Plant Standards (DOE-RL 1989), Safety Analysis Manual (WHC-CM-4-46), and Radiological Design Guide (WHC 1994f). Documents (requirements) essential to the engineering design projects at K Basins are referenced in the guidelines

LFR safety approach and main ELFR safety analysis results

International Nuclear Information System (INIS)

Bubelis, E.; Schikorr, M.; Frogheri, M.; Mansani, L.; Bandini, G.; Burgazzi, L.; Mikityuk, K.; Zhang, Y.; Lo Frano, R.; Forgione, N.

2013-01-01

LFR safety approach: → A global safety approach for the LFR reference plant has been assessed and the safety analyses methodology has been developed. → LFR follows the general guidelines of the Generation IV safety concept recommendations. Thus, improved safety and higher reliability are recognized as an essential priority. → The fundamental safety objectives and the Defence-in-Depth (DiD) approach, as described by IAEA Safety Guides, have been preserved. → The recommendations of the Risk and Safety Working Group (RSWG) of GEN-IV IF has been taken into account: • safety is to be “built-in” in the fundamental design rather than “added on”; • full implementation of the Defence-in-Depth principles in a manner that is demonstrably exhaustive, progressive, tolerant, forgiving and well-balanced; • “risk-informed” approach - deterministic approach complemented with a probabilistic one; • adoption of an integrated methodology that can be used to evaluate and document the safety of Gen IV nuclear systems - ISAM. In particular the OPT tool is the fundamental methodology used throughout the design process

Fatal Exertional Heat Stroke and American Football Players: The Need for Regional Heat-Safety Guidelines.

Science.gov (United States)

Grundstein, Andrew J; Hosokawa, Yuri; Casa, Douglas J

2018-01-01

  Weather-based activity modification in athletics is an important way to minimize heat illnesses. However, many commonly used heat-safety guidelines include a uniform set of heat-stress thresholds that do not account for geographic differences in acclimatization.   To determine if heat-related fatalities among American football players occurred on days with unusually stressful weather conditions based on the local climate and to assess the need for regional heat-safety guidelines.   Cross-sectional study.   Data from incidents of fatal exertional heat stroke (EHS) in American football players were obtained from the National Center for Catastrophic Sport Injury Research and the Korey Stringer Institute.   Sixty-one American football players at all levels of competition with fatal EHSs from 1980 to 2014.   We used the wet bulb globe temperature (WBGT) and a z-score WBGT standardized to local climate conditions from 1991 to 2010 to assess the absolute and relative magnitudes of heat stress, respectively.   We observed a poleward decrease in exposure WBGTs during fatal EHSs. In milder climates, 80% of cases occurred at above-average WBGTs, and 50% occurred at WBGTs greater than 1 standard deviation from the long-term mean; however, in hotter climates, half of the cases occurred at near average or below average WBGTs.   The combination of lower exposure WBGTs and frequent extreme climatic values in milder climates during fatal EHSs indicates the need for regional activity-modification guidelines with lower, climatically appropriate weather-based thresholds. Established activity-modification guidelines, such as those from the American College of Sports Medicine, work well in the hotter climates, such as the southern United States, where hot and humid weather conditions are common.

From Clinical Practice Guidelines to Computer-interpretable Guidelines. A Literature Overview

NARCIS (Netherlands)

Latoszek-Berendsen, A.; Tange, H.; van den Herik, H. J.; Hasman, A.

2010-01-01

Background: Guidelines are among us for over 30 years. Initially they were used as algorithmic protocols by nurses and other ancillary personnel. Many physicians regarded the use of guidelines as cookbook medicine. However, quality and patient safety issues have changed the attitude towards

Comparison of the diabetes guidelines from the ADA/EASD and the AACE/ACE.

Science.gov (United States)

Cornell, Susan

To compare recent diabetes guideline updates from the American Diabetes Association-European Association for the Study of Diabetes (ADA/EASD) and the American Association of Clinical Endocrinologists-American College of Endocrinology (AACE/ACE). The ADA/EASD guideline continues to advocate a stepwise approach to glycemic control that initiates with metformin and intensifies treatment incrementally to dual and triple therapy at 3-month intervals until the patient is at their individualized goal. The AACE/ACE guideline provides a broader choice of first-line medications, with a suggested hierarchy of use, and it encourages initial dual and triple therapy if the glycated hemoglobin (A1C) level is high enough at diagnosis (7.5%-9.0% and >9.0%, respectively). Target A1C levels are higher in the ADA/EASD guideline (≤7.0%) compared with the AACE/ACE guideline (≤6.5%), although both statements indicate that targets should be adjusted to specific clinical scenarios based on safety. Both guidelines now include the new sodium-glucose cotransporter-2 inhibitors among their choices of acceptable glucose-lowering medications and endorse the overall cardiovascular and pancreatic safety of incretin therapies, and the safety of pioglitazone vis-a-vis bladder cancer. In practice, the ADA/EASD guidelines tend to be more user-friendly for general practitioners because of the simple stepwise intensification regimen, whereas the AACE/ACE guidelines are more commonly followed by specialists (endocrinologists) because of the more aggressive A1C targets. Copyright © 2017 American Pharmacists Association®. Published by Elsevier Inc. All rights reserved.

General guidelines about performance specifications for purchasing equipment for x-ray diagnostics, with comments

International Nuclear Information System (INIS)

1995-12-01

These general guidelines are intended to be used as a basis for what requirements are reasonable from a radiation protection point of view and should be part of the contract in connection with the purchase of equipment for x-ray diagnostics. Technical performance requirements are addressed as well as items like documentation, instructions for use and education and training. The guidelines are also useful for the design of quality assurance programs. In the comments in addition to these guidelines legal aspects are noted, including a list of relevant laws, regulations and directives. Standards, both national and international, within the field are referred to with a short description of their content. 40 refs

General guidelines about performance specifications for purchasing equipment for x-ray diagnostics, with comments

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-12-01

These general guidelines are intended to be used as a basis for what requirements are reasonable from a radiation protection point of view and should be part of the contract in connection with the purchase of equipment for x-ray diagnostics. Technical performance requirements are addressed as well as items like documentation, instructions for use and education and training. The guidelines are also useful for the design of quality assurance programs. In the comments in addition to these guidelines legal aspects are noted, including a list of relevant laws, regulations and directives. Standards, both national and international, within the field are referred to with a short description of their content. 40 refs.

Safety of treatments for inflammatory bowel disease: Clinical practice guidelines of the Italian Group for the Study of Inflammatory Bowel Disease (IG-IBD).

Science.gov (United States)

Biancone, Livia; Annese, Vito; Ardizzone, Sandro; Armuzzi, Alessandro; Calabrese, Emma; Caprioli, Flavio; Castiglione, Fabiana; Comberlato, Michele; Cottone, Mario; Danese, Silvio; Daperno, Marco; D'Incà, Renata; Frieri, Giuseppe; Fries, Walter; Gionchetti, Paolo; Kohn, Anna; Latella, Giovanni; Milla, Monica; Orlando, Ambrogio; Papi, Claudio; Petruzziello, Carmelina; Riegler, Gabriele; Rizzello, Fernando; Saibeni, Simone; Scribano, Maria Lia; Vecchi, Maurizio; Vernia, Piero; Meucci, Gianmichele

2017-04-01

Inflammatory bowel diseases are chronic conditions of unknown etiology, showing a growing incidence and prevalence in several countries, including Italy. Although the etiology of Crohn's disease and ulcerative colitis is unknown, due to the current knowledge regarding their pathogenesis, effective treatment strategies have been developed. Several guidelines are available regarding the efficacy and safety of available drug treatments for inflammatory bowel diseases. Nevertheless, national guidelines provide additional information adapted to local feasibility, costs and legal issues related to the use of the same drugs. These observations prompted the Italian Group for the Study of Inflammatory Bowel Disease (IG-IBD) to establish Italian guidelines on the safety of currently available treatments for Crohn's disease and ulcerative colitis. These guidelines discuss the use of aminosalicylates, systemic and low bioavailability corticosteroids, antibiotics (metronidazole, ciprofloxacin, rifaximin), thiopurines, methotrexate, cyclosporine A, TNFα antagonists, vedolizumab, and combination therapies. These guidelines are based on current knowledge derived from evidence-based medicine coupled with clinical experience of a national working group. Copyright © 2017 Editrice Gastroenterologica Italiana S.r.l. Published by Elsevier Ltd. All rights reserved.

Chapter A6. Section 6.0. General Information and Guidelines

Science.gov (United States)

Wilde, Franceska D.; Radtke, Dean B.

2005-01-01

This report summarizes information, guidelines, and minimum requirements that apply generally to the seven field-measurement sections that comprise the rest of Chapter A6 of this U.S. Geological Survey (USGS) National Field Manual for the Collection of Water-Quality Data (NFM). Protocols are specified for establishing and maintaining data records, use of field-measurement instruments and methods, and quality assurance of data-collection and reporting methods that are relevant to surface-water and ground-water field-measurement activities.

Implementing guidelines in general practice: evaluation of process and outcome of care in chronic diseases.

NARCIS (Netherlands)

Schellevis, F.G.; Eijk, J.T.M. van; Lisdonk, E.H. van de; Velden, J. van der; Weel, C. van

1994-01-01

In a prospective longitudinal study over 21 months the performance of general practitioners and the disease status of their patients was measured during the formulation and implementation of guidelines on follow-up care. Data on 15 general practitioners and on 613 patients with hypertension, 95 with

Measure Guideline: Guide to Attic Air Sealing

Energy Technology Data Exchange (ETDEWEB)

Lstiburek, Joseph [Building Science Corporation, Westford, MA (United States)

2014-09-01

The purpose of this measure guideline is to provide information and recommendations for the preparation work necessary prior to adding attic insulation. Even though the purpose of this guide is to save energy, health, safety, and durability should not be compromised by energy efficiency. Accordingly, combustion safety and ventilation for indoor air quality are addressed first. Durability and attic ventilation then follow. Finally, to maximize energy savings, air sealing is completed prior to insulating. The guide is intended for home remodelers, builders, insulation contractors, mechanical contractors, general contractors who have previously done remodeling and homeowners as a guide to the work that needs to be done.

Integrating Occupational Safety and Health into TAFE Courses: Policy Guidelines.

Science.gov (United States)

Hill, Graham L.; Mageean, Pauline

Intended to help administrators, curriculum developers, and teachers integrate occupational health and safety into Australian vocational courses on bricklaying, metal fabrication, and horticulture, this document suggests specific policies and provides further amplification concerning three general policies for that integration. The three general…

[The management of osteoarthritis by general practitioners in Germany : Comparison of self-reported behaviour with international guidelines.

NARCIS (Netherlands)

Rosemann, T.J.; Joos, S.; Szecsenyi, J.

2008-01-01

BACKGROUND: In most countries, guidelines for the treatment of osteoarthritis (OA) are available. However, in Germany, no guideline for the primary care sector is available. The care provider of most patients is the general practitioner (GP). The aim of the study was to investigate the approaches in

General safety considerations

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-09-01

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

General safety considerations

International Nuclear Information System (INIS)

2001-01-01

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

General safety considerations

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-09-01

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

General safety considerations

International Nuclear Information System (INIS)

1998-01-01

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

Patients' evaluations of patient safety in English general practices: a cross-sectional study.

Science.gov (United States)

Ricci-Cabello, Ignacio; Marsden, Kate S; Avery, Anthony J; Bell, Brian G; Kadam, Umesh T; Reeves, David; Slight, Sarah P; Perryman, Katherine; Barnett, Jane; Litchfield, Ian; Thomas, Sally; Campbell, Stephen M; Doos, Lucy; Esmail, Aneez; Valderas, Jose M

2017-07-01

Description of safety problems and harm in general practices has previously relied on information from health professionals, with scarce attention paid to experiences of patients. To examine patient-reported experiences and outcomes of patient safety in primary care. Cross-sectional study in 45 general practices across five regions in the north, centre, and south of England. A version of the Patient Reported Experiences and Outcomes of Safety in Primary Care (PREOS-PC) questionnaire was sent to a random sample of 6736 patients. Main outcome measures included 'practice activation' (what a practice does to create a safe environment); 'patient activation' (how proactive are patients in ensuring safe healthcare delivery); 'experiences of safety events' (safety errors); 'outcomes of safety' (harm); and 'overall perception of safety' (how safe patients rate their practice). Questionnaires were returned by 1244 patients (18.4%). Scores were high for 'practice activation' (mean [standard error] = 80.4 out of 100 [2.0]) and low for 'patient activation' (26.3 out of 100 [2.6]). Of the patients, 45% reported experiencing at least one safety problem in the previous 12 months, mostly related to appointments (33%), diagnosis (17%), patient provider communication (15%), and coordination between providers (14%). Twenty-three per cent of the responders reported some degree of harm in the previous 12 months. The overall assessment of level of safety of practices was generally high (86.0 out of 100 [16.8]). Priority areas for patient safety improvement in general practices in England include appointments, diagnosis, communication, coordination, and patient activation. © British Journal of General Practice 2017.

Guidelines for radiation safety in interventional cardiology (JCS 2006)

International Nuclear Information System (INIS)

Nagai, Ryozo; Awai, Kazuo; Iesaka, Yoshihito

2006-01-01

The guidelines are made for physicians in cardiovascular field who may be unfamiliar to radiation safety, to understand and know it easily. The introductory chapter describes the basic knowledge for management of radiation exposure and clinical feature of radiation-induced dermal damages like classification, clinical progress and case presentation. Following chapter is itemized, explained in a style of Q and A, and contains sections of; the fundamental knowledge's of radiation exposure management and of radiation skin damage, informed consent and measures for excessive exposure and skin damage crisis, factors influencing the exposure dose, contrivances to reduce the dose in patients, additional factors affecting the crisis of skin damage, contrivances to reduce the dose in medical personnel exposure, management of imaging instruments, methods to measure the exposure dose in patients, intervention in vessels other than the coronary artery, electro-physiological examinations and treatments, nuclear medical diagnoses, CT examinations, diagnosis and treatment of pregnant women, and present states in other countries. (T.I.)

Guidelines for the responsible management of plutonium

International Nuclear Information System (INIS)

Agrell, P.H.

1997-01-01

Since 1994 an informal group of representatives of States party to the NPT has been trying to develop agreed international guidelines for the responsible management of non-military plutonium. This paper gives a brief description of the outcome. Since the results are still subject to decision by Governments, the description must be in general terms only. The paper describes the background to, and genesis of, the discussions and the general approach taken, which was based on commitment to the NPT, national responsibility for the management of nuclear materials and the fuel cycle, upholding of the IAEA's safeguards system, and a focus on civil material. An indication is given of the development of the Group's thinking, especially the decisions that any guidelines must be capable of accommodating surplus military plutonium, as well as civil, and that the main focus should be on measures to increase transparency. The resulting guidelines are described. Their main features are a re-statement of commitments and standards for the management of non-military plutonium with regard to non-proliferation, safety, and other fields, a commitment to the management of such plutonium according to a consistent national strategy, and a commitment to the publication of information on that strategy, and of annual statistics for holdings of plutonium in a consistent format. Other aspects of the guidelines are also explained. Finally, an attempt is made to assess the possible practical effects of the guidelines if adopted by governments. (author)

Patient safety culture measurement in general care: clinimetric properties of 'SCOPE'.

NARCIS (Netherlands)

Zwart, D.L.M.; Langelaan, M.; Vooren, R.C. van de; Kuyvenhoven, M.M.; Kalkman, C.J.; Verheij, T.J.M.; Wagner, C.

2011-01-01

BACKGROUND: A supportive patient safety culture is considered to be an essential condition for improving patient safety. Assessing the current safety culture in general practice may be a first step to target improvements. To that end, we studied internal consistency and construct validity of a

Modifications of Probabilistic Safety Assessment-1 Nuclear Power Plant Dukovany based upon new version of Emergency Operating Procedures

International Nuclear Information System (INIS)

Aldorf, R.

1997-01-01

In the frame of 'living Probabilistic Safety Assessment-1 Nuclear Power Plant Dukovany Project' being performed by Nuclear Research Institute Rez during 1997 is planned to reflect on Probabilistic Safety Assessment-1 basis on impact of Emergency Response Guidelines (as one particular event from the list of other modifications) on Plant Safety. Following highlights help to orient the reader in main general aspects, findings and issues of the work that currently continues on. Older results of Probabilistic Safety Assessment-1 Nuclear Power Plant Dukovany have revealed that human behaviour during accident progression scenarios represent one of the most important aspects in plant safety. Current effort of Nuclear Power Plants Dukovany (Czech Republic) and Bohunice (Slovak Republic) is focussed on development of qualitatively new symptom-based Emergency Operating Procedures called Emergency Response Guidelines Supplier - Westinghouse Energy Systems Europe, Brussels works in cooperation with teams of specialist from both Nuclear Power Plants. In the frame of 'living Probabilistic Safety Assessment-1 Nuclear Power Plant Dukovany Project' being performed by Nuclear Research Institute Rez during 1997 is planned to prove on Probabilistic Safety Assessment -1 basis an expected - positive impact of Emergency Response Guidelines on Plant Safety, Since this contract is currently still in progress, it is possible to release only preliminary conclusions and observations. Emergency Response Guidelines compare to original Emergency Operating Procedures substantially reduce uncertainty of general human behaviour during plant response to an accident process. It is possible to conclude that from the current scope Probabilistic Safety Assessment Dukovany point of view (until core damage), Emergency Response Guidelines represent adequately wide basis for mitigating any initiating event

Preliminary safety analysis report for the TFTR

International Nuclear Information System (INIS)

Lind, K.E.; Levine, J.D.; Howe, H.J.

A Preliminary Safety Analysis Report has been prepared for the Tokamak Fusion Test Reactor. No accident scenarios have been identified which would result in exposures to on-site personnel or the general public in excess of the guidelines defined for the project by DOE

[The practice guideline 'Sore throat' (second revision) from the Dutch College of General Practitioners; a response from the perspective of otorhinolaryngology

NARCIS (Netherlands)

Marres, H.A.M.

2008-01-01

In this comment, the practice guideline 'Sore throat' (second revision) is discussed. This guideline, composed by the Dutch College of General Practitioners, offers general practitioners a well-appreciated overview of the common practices regarding diagnostic tests and treatment of pharyngitis and

ESRS guidelines for software safety reviews. Reference document for the organization and conduct of Engineering Safety Review Services (ESRS) on software important to safety in nuclear power plants

International Nuclear Information System (INIS)

2000-01-01

The IAEA provides safety review services to assist Member States in the application of safety standards and, in particular, to evaluate and facilitate improvements in nuclear power plant safety performance. Complementary to the Operational Safety Review Team (OSART) and the International Regulatory Review Team (IRRT) services are the Engineering Safety Review Services (ESRS), which include reviews of siting, external events and structural safety, design safety, fire safety, ageing management and software safety. Software is of increasing importance to safety in nuclear power plants as the use of computer based equipment and systems, controlled by software, is increasing in new and older plants. Computer based devices are used in both safety related applications (such as process control and monitoring) and safety critical applications (such as reactor protection). Their dependability can only be ensured if a systematic, fully documented and reviewable engineering process is used. The ESRS on software safety are designed to assist a nuclear power plant or a regulatory body of a Member State in the review of documentation relating to the development, application and safety assessment of software embedded in computer based systems important to safety in nuclear power plants. The software safety reviews can be tailored to the specific needs of the requesting organization. Examples of such reviews are: project planning reviews, reviews of specific issues and reviews prior final acceptance. This report gives information on the possible scope of ESRS software safety reviews and guidance on the organization and conduct of the reviews. It is aimed at Member States considering these reviews and IAEA staff and external experts performing the reviews. The ESRS software safety reviews evaluate the degree to which software documents show that the development process and the final product conform to international standards, guidelines and current practices. Recommendations are

Measure Guideline: Guide to Attic Air Sealing

Energy Technology Data Exchange (ETDEWEB)

Lstiburek, J.

2014-09-01

The Guide to Attic Air Sealing was completed in 2010 and although not in the standard Measure Guideline format, is intended to be a Measure Guideline on Attic Air Sealing. The guide was reviewed during two industry stakeholders meetings held on December 18th, 2009 and January 15th, 2010, and modified based on the comments received. Please do not make comments on the Building America format of this document. The purpose of the Guide to Attic Air Sealing is to provide information and recommendations for the preparation work necessary prior to adding attic insulation. Even though the purpose of this guide is to save energy - health, safety and durability should not be compromised by energy efficiency. Accordingly, combustion safety and ventilation for indoor air quality are addressed first. Durability and attic ventilation then follow. Finally, to maximize energy savings, air sealing is completed prior to insulating. The guide is intended for home remodelers, builders, insulation contractors, mechanical contractors, general contractors who have previously done remodeling and homeowners as a guide to the work that needs to be done.

Management of venous leg ulcers in general practice - a practical guideline.

Science.gov (United States)

Sinha, Sankar; Sreedharan, Sadhishaan

2014-09-01

Chronic venous leg ulcers are the most common wounds seen in general practice. Their management can be both challenging and time-consuming. To produce a short practical guideline incorporating the TIME concept and A2BC2D approach to help general practitioners and their practice nurses in delivering evidence-based initial care to patients with chronic venous leg ulcers. Most chronic venous leg ulcers can be managed effectively in the general practice setting by following the simple, evidence-based approach described in this article. Figure 1 provides a flow chart to aid in this process. Figure 2 illustrates the principles of management in general practice. Effective management of chronic ulcers involves the assessment of both the ulcer and the patient. The essential requirements of management are to debride the ulcer with appropriate precautions, choose dressings that maintain adequate moisture balance, apply graduated compression bandage after evaluation of the arterial circulation and address the patient's concerns, such as pain and offensive wound discharge.

European standardization activities on safety of liquid helium cryostats

CERN Multimedia

CERN. Geneva

2016-01-01

This talk gives a general overview on the challenges of designing safety units for liquid helium cryostats with regard to existing industry standards. It reviews the work of a national working group that published the technical guideline DIN SPEC 4683 in April 2015, which is dedicated to the particular conditions in liquid helium cryostats. Based on both this guideline and equivalent documents from e.g. CEA, CERN, a working group is being formed at the European Committee for Standardization, associated to CEN/TC 268, which will work on a European standard on safety of liquid helium cryostats. The actual status and the schedule of this project are presented.

77 FR 33777 - General Aviation Safety Forum: Climbing to the Next Level

Science.gov (United States)

2012-06-07

... NATIONAL TRANSPORTATION SAFETY BOARD General Aviation Safety Forum: Climbing to the Next Level The National Transportation Safety Board (NTSB) will convene a 2- day forum focused on safety issues related to... the Next Level,'' will be chaired by NTSB Chairman Deborah A. P. Hersman and all five Board Members...

Seismic Safety Guide

International Nuclear Information System (INIS)

Eagling, D.G.

1983-09-01

This guide provides managers with practical guidelines for administering a comprehensive earthquake safety program. The Guide is comprehensive with respect to earthquakes in that it covers the most important aspects of natural hazards, site planning, evaluation and rehabilitation of existing buildings, design of new facilities, operational safety, emergency planning, special considerations related to shielding blocks, non-structural elements, lifelines, fire protection and emergency facilities. Management of risk and liabilities is also covered. Nuclear facilities per se are not dealt with specifically. The principles covered also apply generally to nuclear facilities but the design and construction of such structures are subject to special regulations and legal controls

Seismic Safety Guide

Energy Technology Data Exchange (ETDEWEB)

Eagling, D.G. (ed.)

1983-09-01

This guide provides managers with practical guidelines for administering a comprehensive earthquake safety program. The Guide is comprehensive with respect to earthquakes in that it covers the most important aspects of natural hazards, site planning, evaluation and rehabilitation of existing buildings, design of new facilities, operational safety, emergency planning, special considerations related to shielding blocks, non-structural elements, lifelines, fire protection and emergency facilities. Management of risk and liabilities is also covered. Nuclear facilities per se are not dealt with specifically. The principles covered also apply generally to nuclear facilities but the design and construction of such structures are subject to special regulations and legal controls.

Recommendations to the NRC on human engineering guidelines for nuclear power plant maintainability

Energy Technology Data Exchange (ETDEWEB)

Badalamente, R.V.; Fecht, B.A.; Blahnik, D.E.; Eklund, J.D.; Hartley, C.S.

1986-03-01

This document contains human engineering guidelines which can enhance the maintainability of nuclear power plants. The guidelines have been derived from general human engineering design principles, criteria, and data. The guidelines may be applied to existing plants as well as to plants under construction. They apply to nuclear power plant systems, equipment and facilities, as well as to maintenance tools and equipment. The guidelines are grouped into seven categories: accessibility and workspace, physical environment, loads and forces, maintenance facilities, maintenance tools and equipment, operating equipment design, and information needs. Each chapter of the document details specific maintainability problems encountered at nuclear power plants, the safety impact of these problems, and the specific maintainability design guidelines whose application can serve to avoid these problems in new or existing plants.

Recommendations to the NRC on human engineering guidelines for nuclear power plant maintainability

International Nuclear Information System (INIS)

Badalamente, R.V.; Fecht, B.A.; Blahnik, D.E.; Eklund, J.D.; Hartley, C.S.

1986-03-01

This document contains human engineering guidelines which can enhance the maintainability of nuclear power plants. The guidelines have been derived from general human engineering design principles, criteria, and data. The guidelines may be applied to existing plants as well as to plants under construction. They apply to nuclear power plant systems, equipment and facilities, as well as to maintenance tools and equipment. The guidelines are grouped into seven categories: accessibility and workspace, physical environment, loads and forces, maintenance facilities, maintenance tools and equipment, operating equipment design, and information needs. Each chapter of the document details specific maintainability problems encountered at nuclear power plants, the safety impact of these problems, and the specific maintainability design guidelines whose application can serve to avoid these problems in new or existing plants

Generally Recognized as Safe: Uncertainty Surrounding E-Cigarette Flavoring Safety

OpenAIRE

Sears, Clara G.; Hart, Joy L.; Walker, Kandi L.; Robertson, Rose Marie

2017-01-01

Despite scientific uncertainty regarding the relative safety of inhaling e-cigarette aerosol and flavorings, some consumers regard the U.S. Food and Drug Administration’s “generally recognized as safe” (GRAS) designation as evidence of flavoring safety. In this study, we assessed how college students’ perceptions of e-cigarette flavoring safety are related to understanding of the GRAS designation. During spring 2017, an online questionnaire was administered to college students. Chi-square p-v...

Safety and Toxicology of Cannabinoids.

Science.gov (United States)

Sachs, Jane; McGlade, Erin; Yurgelun-Todd, Deborah

2015-10-01

There is extensive research on the safety, toxicology, potency, and therapeutic potential of cannabis. However, uncertainty remains facilitating continued debate on medical and recreational cannabis policies at the state and federal levels. This review will include a brief description of cannabinoids and the endocannabinoid system; a summary of the acute and long-term effects of cannabis; and a discussion of the therapeutic potential of cannabis. The conclusions about safety and efficacy will then be compared with the current social and political climate to suggest future policy directions and general guidelines.

Record of responses to public comments on proposed general guidelines for recommendation of sites for nuclear waste repositories

International Nuclear Information System (INIS)

1983-01-01

The Nuclear Waste Policy Act of 1982 (Public Law 97-425, referred to in this document as the Act) assigned to the US Department of Energy (DOE) the authority for the disposal of high-level radioactive waste and spent nuclear fuel. Among other provisions, the Act specifies a process and schedule for the siting of two geologic repositories for this purpose. The Act requires that the DOE issue general guidelines for the recommendation of sites for repositories. The guidelines are to be developed in consultation with three Federal agencies (the Council on Environmental Quality, the US Environmental Protection Agency, and the US Geological Survey) and with interested Governors and issued with the concurrence of the US Nuclear Regulatory Commission. To meet this directive, the DOE convened a task force of program experts to develop proposed guidelines, issued the proposed guidelines on February 7, 1983, and invited comments from the specified Federal agencies, interested Governors, and the general public. Public hearings on the proposed guidelines were held in March at the following locations: Chicago, New Orleans, Washington, DC, Salt Lake City, and Seattle. After considering the resulting comments and preparing responses to them, the task force prepared a draft of this comment-response document and a set of alternative guidelines; these documents were issued on May 27, 1983. This document summarizes the record of comments that directly led to the alternative guidelines of May 27, 1983. It contains synopses of comments, presents the responses of the task force to the comments, and briefly describes how the proposed guidelines of February 7, 1983, were revised to produce the alternative guidelines of May 27, 1983. 13 references

International common-cause failure data exchange. ICDE general coding guidelines - Technical note

International Nuclear Information System (INIS)

Johanson, Gunnar; Werner, Wolfgang; Concepcion Capote, Marina; Kreuser, Albert; Rasmuson, Dale; Jonsson, Esther; Pereira Pagan, Begona; Tirira, Jorge; Morris, Ian; Morales, Rosa; Oxberry, Anna; Kreuser, Albert

2004-01-01

Several Member countries of the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development (OECD/NEA) have established the International Common-Cause Failure Data Exchange Project (ICDE Project) to encourage multilateral co-operation in the collection and analysis of data relating to Common-Cause Failure (CCF) events. The objectives of the ICDE Project are to: a) Collect and analyse CCF events over the long term so as to better understand such events, their causes, and their prevention; b) Generate qualitative insights into the root causes of CCF events which can then be used to derive approaches or mechanisms for their prevention or for mitigating their consequences; c) Establish a mechanism for the efficient feedback of experience gained in connection with CCF phenomena, including the development of defences against their occurrence, such as indicators for risk based inspections; and d) Record event attributes to facilitate quantification of CCF frequencies when so decided by the Project Working Group. The ICDE Project is envisaged to comprise all possible events of interest, including both complete and partial ICDE events. The ICDE Project will cover the key components of the main safety systems. Presently, the components listed below are included in the ICDE Project. Data have been collected for the six first components in the list: Centrifugal pumps, Diesel generators, Motor operated valves, Safety relief valves/power operated relief valves, Check valves, Batteries, Level measurement, Breakers, Control rod drive assemblies. Others will be added to this list later on. In this component coding guidelines, explanations on the ICDE General coding format are given. The guide reflects present experience with the data format and with the collected data. Further interpretations and clarifications will be added, should they become necessary. For each component analysed in the ICDE project, separate coding guidance is provided in the appendices

Radiation Safety (General) Regulations 1983 (Western Australia)

International Nuclear Information System (INIS)

1983-01-01

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

Improving the implementation of perioperative safety guidelines using a multifaceted intervention approach: protocol of the IMPROVE study, a stepped wedge cluster randomized trial.

Science.gov (United States)

Emond, Yvette E J J M; Calsbeek, Hiske; Teerenstra, Steven; Bloo, Gerrit J A; Westert, Gert P; Damen, Johan; Wolff, André P; Wollersheim, Hub C

2015-01-08

This study is initiated to evaluate the effects, costs, and feasibility at the hospital and patient level of an evidence-based strategy to improve the use of Dutch perioperative safety guidelines. Based on current knowledge, expert opinions and expertise of the project team, a multifaceted implementation strategy has been developed. This is a stepped wedge cluster randomized trial including nine representative hospitals across The Netherlands. Hospitals are stratified into three groups according to hospital type and geographical location and randomized in terms of the period for receipt of the intervention. All adult surgical patients meeting the inclusion criteria are assessed for patient outcomes. The implementation strategy includes education, audit and feedback, organizational interventions (e.g., local embedding of the guidelines), team-directed interventions (e.g., multi-professional team training), reminders, as well as patient-mediated interventions (e.g., patient safety cards). To tailor the implementation activities, we developed a questionnaire to identify barriers for effective guideline adherence, based on (a) a theoretical framework for classifying barriers and facilitators, (b) an instrument for measuring determinants of innovations, and (c) 19 semi-structured interviews with perioperative key professionals. Primary outcome is guideline adherence measured at the hospital (i.e., cluster) and patient levels by a set of perioperative Patient Safety Indicators (PSIs), which was developed parallel to the perioperative guidelines. Secondary outcomes at the patient level are in-hospital complications, postoperative wound infections and mortality, length of hospital stay, and unscheduled transfer to the intensive care unit, non-elective readmission to the hospital and unplanned reoperation, all within 30 days after the initial surgery. Also, patient safety culture and team climate will be studied as potential determinants. Finally, a process evaluation is

Recommended general safety requirements for nuclear power plants

International Nuclear Information System (INIS)

1983-06-01

This report presents recommendations for a set of general safety requirements that could form the basis for the licensing of nuclear power plants by the Atomic Energy Control Board. In addition to a number of recommended deterministic requirements the report includes criteria for the acceptability of the design of such plants based upon the calculated probability and consequence (in terms of predicted radiation dose to members of the public) of potential fault sequences. The report also contains a historical review of nuclear safety principles and practices in Canada

General safety aspects

International Nuclear Information System (INIS)

1998-01-01

In this part next aspects are described: (1) Priority to safety; (2) Financial and human resources;; (3) Human factor; (4) Operator's quality assurance system; (5) Safety assessment and Verification; (6) Radiation protection and (7) Emergency preparedness

Commercial grade item (CGI) dedication of generators for nuclear safety related applications

International Nuclear Information System (INIS)

Das, R.K.; Hajos, L.G.

1993-01-01

The number of nuclear safety related equipment suppliers and the availability of spare and replacement parts designed specifically for nuclear safety related application are shrinking rapidly. These have made it necessary for utilities to apply commercial grade spare and replacement parts in nuclear safety related applications after implementing proper acceptance and dedication process to verify that such items conform with the requirements of their use in nuclear safety related application. The general guidelines for the commercial grade item (CGI) acceptance and dedication are provided in US Nuclear Regulatory Commission (NRC) Generic Letters and Electric Power Research Institute (EPRI) Report NP-5652, Guideline for the Utilization of Commercial Grade Items in Nuclear Safety Related Applications. This paper presents an application of these generic guidelines for procurement, acceptance, and dedication of a commercial grade generator for use as a standby generator at Salem Generating Station Units 1 and 2. The paper identifies the critical characteristics of the generator which once verified, will provide reasonable assurance that the generator will perform its intended safety function. The paper also delineates the method of verification of the critical characteristics through tests and provide acceptance criteria for the test results. The methodology presented in this paper may be used as specific guidelines for reliable and cost effective procurement and dedication of commercial grade generators for use as standby generators at nuclear power plants

ASCOT guidelines

International Nuclear Information System (INIS)

1994-05-01

These guidelines describe an approach used in conducting an Assessment of Safety Culture in Organizations Team (ASCOT) review. They are intended to assist the team members in conducting their reviews and at the same time provide guidance to hosts preparing to receive an ASCOT review. They may also be used by any organization wishing to conduct their own self-assessment of safety culture, independent of an ASCOT review

[The management of osteoarthritis by general practitioners in Germany: comparison of self-reported behaviour with international guidelines].

Science.gov (United States)

Rosemann, T; Joos, S; Szecsenyi, J

2008-01-01

In most countries, guidelines for the treatment of osteoarthritis (OA) are available. However, in Germany, no guideline for the primary care sector is available. The care provider of most patients is the general practitioner (GP). The aim of the study was to investigate the approaches in diagnosing and treating OA of German GPs and to assess adherence to international guidelines. Cross-sectional study using a structured questionnaire with a random sample of 144 GPs. Regarding diagnosis, the importance of X-rays was overestimated. Regarding treatment approaches, exercising and weight reduction were regarded as primary treatment targets. Pharmacological treatment approaches were somewhat guideline oriented, but conservative approaches such as physical therapy were overestimated as invasive treatments such as intra-articular injections were underestimated in its benefit. Establishing a guideline specifically for primary care and increasing guideline adherence could help to prevent the present overuse of X-rays and the high amount of referrals to orthopaedics, save costs and reduce inadequate treatments.

Attitude and awareness of general dental practitioners toward radiation hazards and safety.

Science.gov (United States)

Aravind, B S; Joy, E Tatu; Kiran, M Shashi; Sherubin, J Eugenia; Sajesh, S; Manchil, P Redwin Dhas

2016-10-01

The aim and objective is to evaluate the level of awareness and attitude about radiation hazards and safety practices among general dental practitioners in Trivandrum District, Kerala, India. A questionnaire-based cross-sectional study was conducted among 300 general dental practitioners in Trivandrum District, Kerala, India. Postanswering the questions, a handout regarding radiation safety and related preventive measures was distributed to encourage radiation understanding and protection. Statistical analysis were done by assessing the results using Chi-square statistical test, t -test, and other software (Microsoft excel + SPSS 20.0 trail version). Among 300 general practitioners (247 females and 53 males), 80.3% of the practitioners were found to have a separate section for radiographic examination in their clinics. Intraoral radiographic machines were found to be the most commonly (63.3%) used radiographic equipment while osteoprotegerin was the least (2%). Regarding the practitioner's safety measures, only 11.7% of them were following all the necessary steps while 6.7% clinicians were not using any safety measure in their clinic, and with respect to patient safety, only 9.7% of practitioners were following the protocol. The level of awareness of practitioners regarding radiation hazards and safety was found to be acceptable. However, implementation of their knowledge with respect to patient and personnel safety was found wanting. Insisting that they follow the protocols and take necessary safety measures by means of continuing medical education programs, pamphlets, articles, and workshops is strongly recommended.

Effects of a team-based assessment and intervention on patient safety culture in general practice

DEFF Research Database (Denmark)

Hoffmann, B; Müller, V; Rochon, J

2014-01-01

Background: The measurement of safety culture in healthcare is generally regarded as a first step towards improvement. Based on a self-assessment of safety culture, the Frankfurt Patient Safety Matrix (FraTrix) aims to enable healthcare teams to improve safety culture in their organisations....... In this study we assessed the effects of FraTrix on safety culture in general practice. Methods: We conducted an open randomised controlled trial in 60 general practices. FraTrix was applied over a period of 9 months during three facilitated team sessions in intervention practices. At baseline and after 12...... months, scores were allocated for safety culture as expressed in practice structure and processes (indicators), in safety climate and in patient safety incident reporting. The primary outcome was the indicator error management. Results: During the team sessions, practice teams reflected on their safety...

Diet during pregnancy: Women's knowledge of and adherence to food safety guidelines.

Science.gov (United States)

Bryant, Jamie; Waller, Amy; Cameron, Emilie; Hure, Alexis; Sanson-Fisher, Rob

2017-06-01

As a precaution against acquiring food-borne illnesses, guidelines recommend women avoid some foods during pregnancy. To examine among women receiving antenatal care: (i) level of knowledge and self-reported adherence to guidelines about foods that should be avoided during pregnancy; and (ii) associated socio-demographic characteristics. Women attending a public outpatient clinic who were: pregnant or had recently given birth; 18 years or older; able to complete an English language survey with minimal assistance; and had at least one prior antenatal appointment for their current pregnancy, were asked to complete a cross-sectional survey. In total 223 women (64% consent rate) participated. Knowledge of foods to avoid during pregnancy was poor, with 83% of women incorrectly identifying at least one unsafe food as safe to consume. The average knowledge score for foods to avoid during pregnancy was 7.9 (standard deviation = 3.4; median = 9; interquartile range: 6-11; n = 218) out of a possible score of 12. Having more general practice (GP) visits for antenatal care and fewer tertiary antenatal visits were significantly associated with higher knowledge. Women with a higher number of GP visits and those receiving care in a high-risk clinic were more likely to be adherent to guidelines. The majority of pregnant women have poor knowledge of food avoidance guidelines and continue to consume foods that put them at risk. © 2016 The Royal Australian and New Zealand College of Obstetricians and Gynaecologists.

The role of post-earthquake structural safety in pre-earthquake retrof in decision: guidelines and applications

International Nuclear Information System (INIS)

Bazzurro, P.; Telleen, K.; Maffei, J.; Yin, J.; Cornell, C.A.

2009-01-01

Critical structures such as hospitals, police stations, local administrative office buildings, and critical lifeline facilities, are expected to be operational immediately after earthquakes. Any rational decision about whether these structures are strong enough to meet this goal or whether pre-empitive retrofitting is needed cannot be made without an explicit consideration of post-earthquake safety and functionality with respect to aftershocks. Advanced Seismic Assessment Guidelines offer improvement over previous methods for seismic evaluation of buildings where post-earthquake safety and usability is a concern. This new method allows engineers to evaluate the like hood that a structure may have restricted access or no access after an earthquake. The building performance is measured in terms of the post-earthquake occupancy classifications Green Tag, Yellow Tag, and Red Tag, defining these performance levels quantitatively, based on the structure's remaining capacity to withstand aftershocks. These color-coded placards that constitute an established practice in US could be replaced by the standard results of inspections (A to E) performed by the Italian Dept. of Civil Protection after an event. The article also shows some applications of these Guidelines to buildings of the largest utility company in California, Pacific Gas and Electric Company (PGE). [it

Sedation in a radiology department--do radiologists follow their own guidelines?

Science.gov (United States)

Eason, D; Chakraverty, S; Wildsmith, J A W

2011-05-01

The Royal College of Radiologists (RCR) published guidelines in 2003 which aimed to standardise and improve the safety of sedation in the modern Radiology department. As sedation requirements increase, we decided to audit our own departments understandings and practice with respect to sedation. A repeat audit cycle was performed following a re-educational lecture, one year later. Three common sedation case scenarios were incorporated into a questionnaire which detailed questioning on requirements for fasting, monitoring and the order and use of sedation drugs alongside analgesics. These were compared to the 2003 RCR guidelines. The audit was recycled at one year. Despite the RCR guidelines, freely available on the RCR website, there was a persisting variation in practice which revealed a lack of awareness of the requirements for adequate fasting and the importance of giving the opiate before the benzodiazepine (sedative) agent in cases where a combination are chosen. The audit did show a trend towards using shorter acting benzodiazepines, which is in keeping with the guidelines. Monitoring of vital signs was generally, well carried out. General awareness of the RCR guidelines for safe sedation in the Radiology department was initially low and practice found to be variable. Re-education saw some improvements but also, some persisting habitual deviations from the guidelines, particularly with respect to the order in which the opiate and sedative benzodiazepine were given.

General guidelines for the assessment of internal dose from monitoring data: Progress of the IDEAS project

International Nuclear Information System (INIS)

Doerfel, H.; Andrasi, A.; Bailey, M.; Blanchardon, E.; Cruz-Suarez, R.; Berkovski, V.; Castellani, C. M.; Hurtgenv, C.; Leguen, B.; Malatova, I.; Marsh, J.; Stather, J.; Zeger, J.

2007-01-01

In recent major international intercomparison exercises on intake and internal dose assessments from monitoring data, the results calculated by different participants varied significantly. Based on this experience the need for harmonisation of the procedures has been formulated within an EU 5. Framework Programme research project. The aim of the project, IDEAS, is to develop general guidelines for standardising assessments of intakes and internal doses. The IDEAS project started in October 2001 and ended in June 2005. The project is closely related to some goals of the work of Committee 2 of the ICRP and since 2003 there has been close cooperation between the two groups. To ensure that the guidelines are applicable to a wide range of practical situations, the first step was to compile a database of well-documented cases of internal contamination. In parallel, an improved version of an existing software package was developed and distributed to the partners for further use. A large number of cases from the database was evaluated independently by the partners and the results reviewed. Based on these evaluations, guidelines were drafted and discussed with dosimetry professionals from around the world by means of a virtual workshop on the Internet early in 2004. The guidelines have been revised and refined on the basis of the experiences and discussions in this virtual workshop. The general philosophy of the Guidelines is presented here, focusing on the principles of harmonisation, optimisation and proportionality. Finally, the proposed Levels of Task to structure the approach of internal dose evaluation are reported. (authors)

75 FR 22631 - Notice of Continuance for General Clearance for Guidelines, Applications, and Reporting Forms

Science.gov (United States)

2010-04-29

... NATIONAL FOUNDATION FOR THE ARTS AND HUMANITIES Notice of Continuance for General Clearance for Guidelines, Applications, and Reporting Forms AGENCY: Institute of Museum and Library Services. ACTION... of higher education, library and museum professional associations, and museum and library...

Addressing implementation challenges during guideline development - a case study of Swedish national guidelines for methods of preventing disease.

Science.gov (United States)

Richter-Sundberg, Linda; Kardakis, Therese; Weinehall, Lars; Garvare, Rickard; Nyström, Monica E

2015-01-22

Many of the world's life threatening diseases (e.g. cancer, heart disease, stroke) could be prevented by eliminating life-style habits such as tobacco use, unhealthy diet, physical inactivity and excessive alcohol use. Incorporating evidence-based research on methods to change unhealthy lifestyle habits in clinical practice would be equally valuable. However gaps between guideline development and implementation are well documented, with implications for health care quality, safety and effectiveness. The development phase of guidelines has been shown to be important both for the quality in guideline content and for the success of implementation. There are, however, indications that guidelines related to general disease prevention methods encounter specific barriers compared to guidelines that are diagnosis-specific. In 2011 the Swedish National board for Health and Welfare launched guidelines with a preventive scope. The aim of this study was to investigate how implementation challenges were addressed during the development process of these disease preventive guidelines. Seven semi-structured interviews were conducted with members of the guideline development management group. Archival data detailing the guideline development process were also collected and used in the analysis. Qualitative data were analysed using content analysis as the analytical framework. The study identified several strategies and approaches that were used to address implementation challenges during guideline development. Four themes emerged from the analysis: broad agreements and consensus about scope and purpose; a formalized and structured development procedure; systematic and active involvement of stakeholders; and openness and transparency in the specific guideline development procedure. Additional factors concerning the scope of prevention and the work environment of guideline developers were perceived to influence the possibilities to address implementation issues. This case study

Barriers to the implementation of preconception care guidelines as perceived by general practitioners: a qualitative study

Directory of Open Access Journals (Sweden)

Mazza Danielle

2013-01-01

Full Text Available Abstract Background Despite strong evidence of the benefits of preconception interventions for improving pregnancy outcomes, the delivery and uptake of preconception care and periconceptional folate supplementation remain low. General practitioners play a central role in the delivery of preconception care. Understanding general practitioners’ perceptions of the barriers and enablers to implementing preconception care allows for more appropriate targeting of quality improvement interventions. Consequently, the aim of this study was to examine the barriers and enablers to the delivery and uptake of preconception care guidelines from general practitioners’ perspective using theoretical domains related to behaviour change. Methods We conducted a qualitative study using focus groups consisting of 22 general practitioners who were recruited from three regional general practice support organisations. Questions were based on the theoretical domain framework, which describes 12 domains related to behaviour change. General practitioners’ responses were classified into predefined themes using a deductive process of thematic analysis. Results Beliefs about capabilities, motivations and goals, environmental context and resources, and memory, attention and decision making were the key domains identified in the barrier analysis. Some of the perceived barriers identified by general practitioners were time constraints, the lack of women presenting at the preconception stage, the numerous competing preventive priorities within the general practice setting, issues relating to the cost of and access to preconception care, and the lack of resources for assisting in the delivery of preconception care guidelines. Perceived enablers identified by general practitioners included the availability of preconception care checklists and patient brochures, handouts, and waiting room posters outlining the benefits and availability of preconception care consultations

Leadership and Management for Safety. General Safety Requirements

International Nuclear Information System (INIS)

2016-01-01

This Safety Requirements publication establishes requirements that support Principle 3 of the Fundamental Safety Principles in relation to establishing, sustaining and continuously improving leadership and management for safety and an integrated management system. It emphasizes that leadership for safety, management for safety, an effective management system and a systemic approach (i.e. an approach in which interactions between technical, human and organizational factors are duly considered) are all essential to the specification and application of adequate safety measures and to the fostering of a strong safety culture. Leadership and an effective management system will integrate safety, health, environmental, security, quality, human-and-organizational factor, societal and economic elements. The management system will ensure the fostering of a strong safety culture, regular assessment of performance and the application of lessons from experience. The publication is intended for use by regulatory bodies, operating organizations (registrants and licensees) and other organizations concerned with facilities and activities that give rise to radiation risks

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

DEFF Research Database (Denmark)

Town, Graham; Ash, C; Dierickx, C

2012-01-01

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

International Common Cause Failure Data Exchange (ICDE). General Coding Guidelines - Updated Version, October 2011

International Nuclear Information System (INIS)

Johanson, Gunnar; Werner, Wolfgang; Capote, Marina Concepcion; Kreuser, Albert

2012-01-01

Several OECD/NEA member countries have established the International Common-Cause Failure Data Exchange Project ('ICDE Project') to encourage multilateral cooperation in the collection and analysis of data relating to Common-Cause Failure (CCF) events. The objectives of the ICDE Project are to: a) Collect and analyse CCF events over the long term so as to better understand such events, their causes, and their prevention. b) Generate qualitative insights into the root causes of CCF events which can then be used to derive approaches or mechanisms for their prevention or for mitigating their consequences. c) Establish a mechanism for the efficient feedback of experience gained in connection with CCF phenomena, including the development of defenses against their occurrence, such as indicators for risk based inspections. d) Record event attributes to facilitate quantification of CCF frequencies when so decided by the Project Working Group. The ICDE Project is envisaged to comprise all possible events of interest, including both complete and partial ICDE events. The ICDE Project will cover the key components of the main safety systems. Presently, the components listed below are included in the ICDE Project. Data have been collected for the six first components in the list: Centrifugal pumps, Diesel generators, Motor operated valves, Safety relief valves/power operated relief valves, Check valves, Batteries, Level measurement, Breakers, Control rod drive assemblies. Others will be added to this list later on. In this component coding guidelines, explanations on the ICDE general coding format are given. The guide reflects present experience with the data format and with the collected data. Further interpretations and clarifications will be added, should they become necessary. For each component analysed in the ICDE project, separate coding guidance is provided in the appendices ICDECG 01-06, specifying details relevant to the respective components

General aviation crash safety program at Langley Research Center

Science.gov (United States)

Thomson, R. G.

1976-01-01

The purpose of the crash safety program is to support development of the technology to define and demonstrate new structural concepts for improved crash safety and occupant survivability in general aviation aircraft. The program involves three basic areas of research: full-scale crash simulation testing, nonlinear structural analyses necessary to predict failure modes and collapse mechanisms of the vehicle, and evaluation of energy absorption concepts for specific component design. Both analytical and experimental methods are being used to develop expertise in these areas. Analyses include both simplified procedures for estimating energy absorption capabilities and more complex computer programs for analysis of general airframe response. Full-scale tests of typical structures as well as tests on structural components are being used to verify the analyses and to demonstrate improved design concepts.

Nuclear safety policy working group recommendations on nuclear propulsion safety for the space exploration initiative

Science.gov (United States)

Marshall, Albert C.; Lee, James H.; Mcculloch, William H.; Sawyer, J. Charles, Jr.; Bari, Robert A.; Cullingford, Hatice S.; Hardy, Alva C.; Niederauer, George F.; Remp, Kerry; Rice, John W.

1993-01-01

An interagency Nuclear Safety Working Group (NSPWG) was chartered to recommend nuclear safety policy, requirements, and guidelines for the Space Exploration Initiative (SEI) nuclear propulsion program. These recommendations, which are contained in this report, should facilitate the implementation of mission planning and conceptual design studies. The NSPWG has recommended a top-level policy to provide the guiding principles for the development and implementation of the SEI nuclear propulsion safety program. In addition, the NSPWG has reviewed safety issues for nuclear propulsion and recommended top-level safety requirements and guidelines to address these issues. These recommendations should be useful for the development of the program's top-level requirements for safety functions (referred to as Safety Functional Requirements). The safety requirements and guidelines address the following topics: reactor start-up, inadvertent criticality, radiological release and exposure, disposal, entry, safeguards, risk/reliability, operational safety, ground testing, and other considerations.

Management of spontaneous pneumothorax compared to British Thoracic Society (BTS) 2003 guidelines: a district general hospital audit.

Science.gov (United States)

Medford, Andrew Rl; Pepperell, Justin Ct

2007-10-01

In 1993, the British Thoracic Society (BTS) issued guidelines for the management of spontaneous pneumothorax (SP). These were refined in 2003. To determine adherence to the 2003 BTS SP guidelines in a district general hospital. An initial retrospective audit of 52 episodes of acute SP was performed. Subsequent intervention involved a junior doctor educational update on both the 2003 BTS guidelines and the initial audit results, and the setting up of an online guideline hyperlink. After the educational intervention a further prospective re-audit of 28 SP episodes was performed. Management of SP deviated considerably from the 2003 BTS guidelines in the initial audit - deviation rate 26.9%. After the intervention, a number of clinical management deviations persisted (32.1% deviation rate); these included failure to insert a chest drain despite unsuccessful aspiration, and attempting aspiration of symptomatic secondary SPs. Specific tools to improve standards might include a pneumothorax proforma to improve record keeping and a pneumothorax care pathway to reduce management deviations compared to BTS guidelines. Successful change also requires identification of the total target audience for any educational intervention.

General re-evaluation of the safety on the nuclear ship 'Mutsu' and its repair work

International Nuclear Information System (INIS)

1980-01-01

According to the proposition by the Committee for Investigation Radiation Leak on Mutsu, the works of the general re-evaluation of safety were started after the approval by the Committee for Investigating General Re-evaluation and Repair Techniques for Mutsu. The contents of the general re-evaluation of safety are the inspection of the machines and equipments in the nuclear reactor plant, the review of the design of the nuclear reactor plant, the analysis of the nuclear reactor plant behavior in accidents, and the related experimental researches. These works have been carried out for five years, and problem did not arise at all regarding the nuclear reactor so far, but from the viewpoint of improving the safety and reliability further, it was decided to carry out the repair work based on the general re-evaluation of safety. The contents of the repair work are the improvement of the emergency core-cooling system, the improvement of the safety protection system, the improvement of the radiation monitoring equipments, the improvement of the containment vessel boundary, the improvement of the actuators for technological safety facilities, the improvement of the method controlling secondary water quality, and other repair works. The progress of the general re-evaluation of safety is reported. (Kako, I.)

Safety assessment for facilities and activities. General safety requirements. Pt. 4

International Nuclear Information System (INIS)

2009-01-01

The Safety Fundamentals publication, Fundamental Safety Principles, establishes principles for ensuring the protection of workers, the public and the environment, now and in the future, from harmful effects of ionizing radiation. The objective of this Safety Requirements publication is to establish the generally applicable requirements to be fulfilled in safety assessment for facilities and activities, with special attention paid to defence in depth, quantitative analyses and the application of a graded approach to the ranges of facilities and of activities that are addressed. The publication also addresses the independent verification of the safety assessment that needs to be carried out by the originators and users of the safety assessment. This publication is intended to provide a consistent and coherent basis for safety assessment across all facilities and activities, which will facilitate the transfer of good practices between organizations conducting safety assessments and will assist in enhancing the confidence of all interested parties that an adequate level of safety has been achieved for facilities and activities. The requirements, which are derived from the Fundamental Safety Principles, relate to any human activity that may cause people to be exposed to radiation risks arising from facilities and activities, as follows: Facilities includes: (a) Nuclear power plants; (b) Other reactors (such as research reactors and critical assemblies); (c) Enrichment facilities and fuel fabrication facilities; (d) Conversion facilities used to generate UF 6 ; (e) Storage and reprocessing plants for irradiated fuel; (f) Facilities for radioactive waste management where radioactive waste is treated, conditioned, stored or disposed of; (g) Any other places where radioactive materials are produced, processed, used, handled or stored; (h) Irradiation facilities for medical, industrial, research and other purposes, and any places where radiation generators are installed; (i

Safety Assessment for Facilities and Activities. General Safety Requirements. Pt. 4

International Nuclear Information System (INIS)

2009-01-01

The Safety Fundamentals publication, Fundamental Safety Principles, establishes principles for ensuring the protection of workers, the public and the environment, now and in the future, from harmful effects of ionizing radiation. The objective of this Safety Requirements publication is to establish the generally applicable requirements to be fulfilled in safety assessment for facilities and activities, with special attention paid to defence in depth, quantitative analyses and the application of a graded approach to the ranges of facilities and of activities that are addressed. The publication also addresses the independent verification of the safety assessment that needs to be carried out by the originators and users of the safety assessment. This publication is intended to provide a consistent and coherent basis for safety assessment across all facilities and activities, which will facilitate the transfer of good practices between organizations conducting safety assessments and will assist in enhancing the confidence of all interested parties that an adequate level of safety has been achieved for facilities and activities. The requirements, which are derived from the Fundamental Safety Principles, relate to any human activity that may cause people to be exposed to radiation risks arising from facilities and activities, as follows: Facilities includes: (a) Nuclear power plants; (b) Other reactors (such as research reactors and critical assemblies); (c) Enrichment facilities and fuel fabrication facilities; (d) Conversion facilities used to generate UF6; (e) Storage and reprocessing plants for irradiated fuel; (f) Facilities for radioactive waste management where radioactive waste is treated, conditioned, stored or disposed of; (g) Any other places where radioactive materials are produced, processed, used, handled or stored; (h) Irradiation facilities for medical, industrial, research and other purposes, and any places where radiation generators are installed; (i

Safety Assessment for Facilities and Activities. General Safety Requirements. Pt. 4

International Nuclear Information System (INIS)

2010-01-01

The Safety Fundamentals publication, Fundamental Safety Principles, establishes principles for ensuring the protection of workers, the public and the environment, now and in the future, from harmful effects of ionizing radiation. The objective of this Safety Requirements publication is to establish the generally applicable requirements to be fulfilled in safety assessment for facilities and activities, with special attention paid to defence in depth, quantitative analyses and the application of a graded approach to the ranges of facilities and of activities that are addressed. The publication also addresses the independent verification of the safety assessment that needs to be carried out by the originators and users of the safety assessment. This publication is intended to provide a consistent and coherent basis for safety assessment across all facilities and activities, which will facilitate the transfer of good practices between organizations conducting safety assessments and will assist in enhancing the confidence of all interested parties that an adequate level of safety has been achieved for facilities and activities. The requirements, which are derived from the Fundamental Safety Principles, relate to any human activity that may cause people to be exposed to radiation risks arising from facilities and activities, as follows: Facilities includes: (a) Nuclear power plants; (b) Other reactors (such as research reactors and critical assemblies); (c) Enrichment facilities and fuel fabrication facilities; (d) Conversion facilities used to generate UF6; (e) Storage and reprocessing plants for irradiated fuel; (f) Facilities for radioactive waste management where radioactive waste is treated, conditioned, stored or disposed of; (g) Any other places where radioactive materials are produced, processed, used, handled or stored; (h) Irradiation facilities for medical, industrial, research and other purposes, and any places where radiation generators are installed; (i

Safety Assessment for Facilities and Activities. General Safety Requirements. Pt. 4

International Nuclear Information System (INIS)

2009-01-01

The Safety Fundamentals publication, Fundamental Safety Principles, establishes principles for ensuring the protection of workers, the public and the environment, now and in the future, from harmful effects of ionizing radiation.? read more The objective of this Safety Requirements publication is to establish the generally applicable requirements to be fulfilled in safety assessment for facilities and activities, with special attention paid to defence in depth, quantitative analyses and the application of a graded approach to the ranges of facilities and of activities that are addressed. The publication also addresses the independent verification of the safety assessment that needs to be carried out by the originators and users of the safety assessment. This publication is intended to provide a consistent and coherent basis for safety assessment across all facilities and activities, which will facilitate the transfer of good practices between organizations conducting safety assessments and will assist in enhancing the confidence of all interested parties that an adequate level of safety has been achieved for facilities and activities. The requirements, which are derived from the Fundamental Safety Principles, relate to any human activity that may cause people to be exposed to radiation risks arising from facilities and activities, as follows: Facilities includes: (a) Nuclear power plants; (b) Other reactors (such as research reactors and critical assemblies); (c) Enrichment facilities and fuel fabrication facilities; (d) Conversion facilities used to generate UF6; (e) Storage and reprocessing plants for irradiated fuel; (f) Facilities for radioactive waste management where radioactive waste is treated, conditioned, stored or disposed of; (g) Any other places where radioactive materials are produced, processed, used, handled or stored; (h) Irradiation facilities for medical, industrial, research and other purposes, and any places where radiation generators are

General principles of nuclear safety management related to research reactor decommissioning

International Nuclear Information System (INIS)

Banciu, Ortenzia; Vladescu, Gabriela

2003-01-01

The paper contents the general principles applicable to the decommissioning of research reactors to ensure a proper nuclear safety management, during both decommissioning activities and post decommissioning period. The main objective of decommissioning is to ensure the protection of workers, population and environment against all radiological and non-radiological hazards that could result after a reactor shutdown and dismantling. In the same time, it is necessary, by some proper provisions, to limit the effect of decommissioning for the future generation, according to the new Romanian, IAEA and EU Norms and Regulations. Assurance of nuclear safety during decommissioning process involves, in the first step, to establish of some safety principles and requirements to be taken into account during whole process. In the same time, it is necessary to perform a series of analyses to ensure that the whole process is conducted in a planned and safe manner. The general principles proposed for a proper management of safety during research reactor decommissioning are as follows: - Set-up of all operations included in a Decommissioning Plan; - Set-up and qualitative evaluation of safety problems, which could appear during normal decommissioning process, both radiological and nonradiological risks for workers and public; - Set-up of accident list related to decommissioning process the events that could appear both due to some abnormal working conditions and to some on-site and off-site events like fires, explosions, flooding, earthquake, etc.); - Development and qualitative/ quantitative evaluation of scenarios for each incidents; - Development (and evaluation) of safety indicator system. The safety indicators are the most important tools used to assess the level of nuclear safety during decommissioning process, to discover the weak points and to establish safety measures. The paper contains also, a safety case evaluation (description of facility according to the decommissioning

Swiss guideline: Protection objectives for the disposal of radioactive waste

International Nuclear Information System (INIS)

Zurkinden, A.

1994-01-01

The Swiss guideline R-21 establishing the protection objectives for the disposal of radioactive waste has been reviewed and amended in order to adapt it to improvements made in the field of radioactive waste disposal. In an introductory part, the new guideline states the overall objective of radioactive waste disposal and the associated principles which have to be observed. The guideline then establishes the safety requirements applied to a geological disposal facility. These safety requirements are formulated as protection goals for the whole disposal system and not as specific criteria applying to the system components. The guideline gives finally a series of explanatory comments and indications concerning the conduct of the safety assessment for a disposal facility

Safe Use of Pesticides, Guidelines. Occupational Safety and Health Series No. 38.

Science.gov (United States)

International Labour Office, Geneva (Switzerland).

This document provides guidance on the safe use of pesticides in agricultural work. General principles are given and followed by more detailed safety requirements for the various pesticide application techniques. Finally, the medical aspects of pesticides are considered. (BB)

Generalized railway tank car safety design optimization for hazardous materials transport: Addressing the trade-off between transportation efficiency and safety

International Nuclear Information System (INIS)

Saat, Mohd Rapik; Barkan, Christopher P.L.

2011-01-01

North America railways offer safe and generally the most economical means of long distance transport of hazardous materials. Nevertheless, in the event of a train accident releases of these materials can pose substantial risk to human health, property or the environment. The majority of railway shipments of hazardous materials are in tank cars. Improving the safety design of these cars to make them more robust in accidents generally increases their weight thereby reducing their capacity and consequent transportation efficiency. This paper presents a generalized tank car safety design optimization model that addresses this tradeoff. The optimization model enables evaluation of each element of tank car safety design, independently and in combination with one another. We present the optimization model by identifying a set of Pareto-optimal solutions for a baseline tank car design in a bicriteria decision problem. This model provides a quantitative framework for a rational decision-making process involving tank car safety design enhancements to reduce the risk of transporting hazardous materials.

Prevention of generalized reactions to contrast media: a consensus report and guidelines

International Nuclear Information System (INIS)

Morcos, S.K.; Thomsen, H.S.; Webb, J.A.W.

2001-01-01

The aim of this study was to document, using consensus methodology, current practice for prevention of generalized reactions to contrast media, to identify areas where there is disagreement or confusion and to draw up guidelines for reducing the risk of generalized contrast media reactions based on the survey and a review of the literature. A document with 165 questions was mailed to 202 members of the European Society of Urogenital Radiology. The questions covered risk factors and prophylactic measures for generalized contrast media reactions. Sixty-eight members (34%) responded. The majority indicated that a history of moderate and severe reaction(s) to contrast media and asthma are important risk factors. The survey also indicated that patients with risk factors should receive non-ionic contrast media. In patients at high risk of reaction, if the examination is deemed absolutely necessary, a resuscitation team should be available at the time of the procedure. The majority (91%) used corticosteroid prophylaxis given at least 11 h before contrast medium to patients at increased risk of reaction. The frequency of the dosage varied from one to three times. Fifty-five percent also use antihistamine Hl, mainly administered orally and once. Antihistamine H2 and ephedrine are rarely used. All essential drugs are available on the emergency resuscitation trolley. Patients with risk factors are observed up to 30 min by 48% and up to 60 min by 43% of the responders. Prophylactic measures are not taken before extravascular use of contrast media. Prophylactic drugs are given to patients with a history of moderate or severe generalized reaction to contrast media. In patients with asthma, opinion is divided with only half of the responders giving prophylactic drugs. Aspirin, β-blockers, interleukin-2 and non-steroid anti-inflammatory drugs are not considered risk factors and therefore are not stopped before injection of contrast media. The survey showed some variability in

Prevention of generalized reactions to contrast media: a consensus report and guidelines

Energy Technology Data Exchange (ETDEWEB)

Morcos, S.K. [Dept. of Diagnostic Imaging, Northern General Hospital, Sheffield (United Kingdom); Thomsen, H.S. [Dept. of Diagnostic Radiology, Herlev Hospital, University of Copenhagen (Denmark); Webb, J.A.W. [Diagnostic Radiology Department, St. Bartholomew' s Hospital, London (United Kingdom)

2001-09-01

The aim of this study was to document, using consensus methodology, current practice for prevention of generalized reactions to contrast media, to identify areas where there is disagreement or confusion and to draw up guidelines for reducing the risk of generalized contrast media reactions based on the survey and a review of the literature. A document with 165 questions was mailed to 202 members of the European Society of Urogenital Radiology. The questions covered risk factors and prophylactic measures for generalized contrast media reactions. Sixty-eight members (34%) responded. The majority indicated that a history of moderate and severe reaction(s) to contrast media and asthma are important risk factors. The survey also indicated that patients with risk factors should receive non-ionic contrast media. In patients at high risk of reaction, if the examination is deemed absolutely necessary, a resuscitation team should be available at the time of the procedure. The majority (91%) used corticosteroid prophylaxis given at least 11 h before contrast medium to patients at increased risk of reaction. The frequency of the dosage varied from one to three times. Fifty-five percent also use antihistamine Hl, mainly administered orally and once. Antihistamine H2 and ephedrine are rarely used. All essential drugs are available on the emergency resuscitation trolley. Patients with risk factors are observed up to 30 min by 48% and up to 60 min by 43% of the responders. Prophylactic measures are not taken before extravascular use of contrast media. Prophylactic drugs are given to patients with a history of moderate or severe generalized reaction to contrast media. In patients with asthma, opinion is divided with only half of the responders giving prophylactic drugs. Aspirin, {beta}-blockers, interleukin-2 and non-steroid anti-inflammatory drugs are not considered risk factors and therefore are not stopped before injection of contrast media. The survey showed some variability in

Nuclear power plants: a unique challenge to fire safety

International Nuclear Information System (INIS)

Nowlen, S.P.

1992-01-01

The evaluation of fire safety in a nuclear power plant must include the consideration of the impact of a fire on the operability of plant safety equipment and systems. This issue is not typical of the life safety and property protection issues which dominate traditional fire safety concerns. This paper provides a general discussion of the issue of nuclear power plant fire safety as it currently exists in the USA. Included is a discussion of the past history of nuclear power plant fire events, the development of nuclear industry specific fire safety guidelines, the adverse experience associated with the inadvertent operation of fire suppression systems, and the anticipated direction of fire safety requirements for future reactor designs in the USA. (Author)

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

Science.gov (United States)

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

2012-08-01

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

Patient safety in primary care: a survey of general practitioners in The Netherlands.

NARCIS (Netherlands)

Gaal, S.; Verstappen, W.H.J.M.; Wensing, M.J.P.

2010-01-01

BACKGROUND: Primary care encompasses many different clinical domains and patient groups, which means that patient safety in primary care may be equally broad. Previous research on safety in primary care has focused on medication safety and incident reporting. In this study, the views of general

Evaluation of the League General Insurance Company child safety seat distribution program

Science.gov (United States)

1982-05-01

This report presents an evaluation of the child safety seat distribution initiated by the League General Insurance Company in June 1979. The program provides child safety seats as a benefit under the company's auto insurance policies to policy-holder...

Interaction of national and foreign safety guidelines

International Nuclear Information System (INIS)

Domaratzki, Z.

1991-01-01

A commercial contract for a nuclear power plant includes an agreement on the appropriate safety requirements with which the plant must conform. This may involve adopting the safety requirements of the exporting country, the importing country or a combination of the two sets of safety requirements. To ensure that a high level of safety is achieved it is appropriate that the regulatory authorities in the two countries should establish a co-operative arrangement which will extend for the life of the plant. The regulatory authority in the importing country will need to develop a good understanding of the design, safety analysis and operating history of the reactor type which is being purchased. The regulator in the exporting country can be of great assistance in this regard. The co-operative arrangement should extend into the commissioning and operating stage at which point there will be a two way flow of information. During the operating stage information exchange should include significant operating events, operating problems, new safety related research information, necessary design changes and the results of periodic updating of the safety analysis. In some cases the co-operation should extend to training of regulatory staff. The choice of national versus foreign safety requirements may be important. However, if the two regulatory authorities are to discharge their legal and moral safety responsibilities it is at least equally important to maintain a co-operative arrangement for the life of the plant. (author)

General guidelines for recommendation of sites for nuclear waste repositories

International Nuclear Information System (INIS)

1983-01-01

These guidelines were developed in accordance with the requirements of Section 112(a) of the Nuclear Waste Policy Act of 1982 for use by the Secretary of Energy in evaluating the suitability of sites for the development of repositories. The guidelines will be used for suitability evaluations and determinations made pursuant to Section 112(b) and any preliminary suitability determinations required by Section 114(f). The guidelines set forth in this Part are intended to complement the requirements set forth in the Act, 10 CFR Part 60, and 40 CFR Part 191. In applying these guidelines, the DOE will resolve any inconsistencies between these guidelines and the above documents in a manner determined by the DOE to most closely agree with the intent of the Act

Methodological guidelines for developing accident modification functions

DEFF Research Database (Denmark)

Elvik, Rune

2015-01-01

This paper proposes methodological guidelines for developing accident modification functions. An accident modification function is a mathematical function describing systematic variation in the effects of road safety measures. The paper describes ten guidelines. An example is given of how to use...... limitations in developing accident modification functions are the small number of good evaluation studies and the often huge variation in estimates of effect. It is therefore still not possible to develop accident modification functions for very many road safety measures. © 2015 Elsevier Ltd. All rights...... the guidelines. The importance of exploratory analysis and an iterative approach in developing accident modification functions is stressed. The example shows that strict compliance with all the guidelines may be difficult, but represents a level of stringency that should be strived for. Currently the main...

[Summary of the practice guideline 'TIA' (first revision) from the Dutch College of General Practitioners

NARCIS (Netherlands)

Wiersma, T.; Binsbergen, J.J. van; Verhoeven, S.; Bentum, S.T.B. van; Goudswaard, A.N.

2005-01-01

The new practice guideline of the Dutch College of General Practitioners on the management of patients with a TIA resembles the first version, but there are some important changes: The concept TIA has been narrowed to a neurological deficit that has resolved spontaneously by the time the patient

Mexican Asthma Guidelines: GUIMA 2017

Directory of Open Access Journals (Sweden)

Désirée Larenas-Linnemann

2017-04-01

Full Text Available Background: The need for a national guideline, with a broad basis among specialists and primary care physicians was felt in Mexico, to try unifying asthma management. As several high-quality asthma guidelines exist worldwide, it was decided to select the best three for transculturation. Methods: Following the internationally recommended methodology for guideline transculturation, ADAPTE, a literature search for asthma guidelines, published 1-1-2007 through 31-12-2015 was conducted. AGREE-II evaluations yielded 3/40 most suitable for transculturation. Their compound evidence was fused with local reality, patient preference, cost and safety considerations to draft the guideline document. Subsequently, this was adjusted by physicians from 12 national medical societies in several rounds of a Delphi process and 3 face-to-face meetings to reach the final version. Results: Evidence was fused from British Thoracic Society Asthma Guideline 2014, Global Initiative on Asthma 2015, and Guía Española del Manejo del Asma 2015 (2016 updates included. After 3 Delphi-rounds we developed an evidence-based document taking into account patient characteristics, including age, treatment costs and safety and best locally available medication. Conclusion: In cooperation pulmonologists, allergists, ENT physicians, paediatricians and GPs were able to develop an evidence-based document for the prevention, diagnosis and treatment of asthma and its exacerbations in Mexico.

SARIS Guidelines. 2014 Ed

International Nuclear Information System (INIS)

2014-01-01

The IAEA fundamental safety principles provide the basis for IAEA safety standards and IAEA related programmes. IAEA safety standards reflect an international consensus on what constitutes a high level of safety for protecting people and the environment, and therefore represent what all regulators should achieve. These standards, in particular IAEA Safety Standards Series No. GSR Part 1, Governmental, Legal and Regulatory Framework for Safety, provide the basics for establishing, maintaining and continuously improving the governmental, legal and regulatory framework for safety. Additional IAEA requirements and guidance, such as the IAEA Safety Standards Series No. GSR Part 3 (Interim), Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards, and IAEA Safety Standards Series No. GS-R-3, The Management System for Facilities and Activities, are also used to establish and develop the national infrastructure for safety and for establishing and implementing a management system. Assessment of the regulatory framework for safety with respect to the IAEA safety standards can be made either through an external review or through internal self-assessment. Self-assessment offers a mechanism by which an organization can assess its performance against established standards and models and thereby identify areas for improvement. The IAEA has developed a methodology and tool for Self-assessment of the Regulatory Infrastructure for Safety (SARIS), to assist States in undertaking self-assessment of their national safety framework in accordance with the requirements and recommendations of the IAEA safety standards, and to develop an action plan for improvement. The IAEA self-assessment methodology and the associated tools are fully compatible with the IAEA safety standards and are also used in the preparation for regulatory review missions, such as the Integrated Regulatory Review Service and advisory missions. These guidelines have been developed to

Guidelines on Building Regulations 2008

DEFF Research Database (Denmark)

Thse guidelines clarify and intepret the provisions of the Building Regulations of 2008 (BR08). The Guidelines, which match BR08 in terms of organisation into Parts, are accompanied by the full text of the regulations and the explanatory notes issued by the Danish Enterprise and Construction...... Authority. The Guidelines refer the reader to sources such as relevant standards, instructions and other background material which provides more detailed information. The Guidelines cover the same ground as BR08, including building control regulations, layout, fitting out, structures, fire safety, indoor...... climate, energy consumotion and services. The Guidelines are aimed at all professionals involved in building projects, particularly building design consultants, contractors and municipal application officers....

7 CFR 1724.55 - Dam safety.

Science.gov (United States)

2010-01-01

... 7 Agriculture 11 2010-01-01 2010-01-01 false Dam safety. 1724.55 Section 1724.55 Agriculture... § 1724.55 Dam safety. (a) The provisions of this section apply only to RUS financed electric system... for Dam Safety,”(Guidelines), as applicable. A dam, as more fully defined in the Guidelines, is...

49 CFR 350.339 - What are tolerance guidelines?

Science.gov (United States)

2010-10-01

... 49 Transportation 5 2010-10-01 2010-10-01 false What are tolerance guidelines? 350.339 Section 350... MOTOR CARRIER SAFETY ASSISTANCE PROGRAM Funding § 350.339 What are tolerance guidelines? Tolerance guidelines set forth the limited deviations from the FMCSRs allowed in your State's laws and regulations...

Car Seat Safety

Science.gov (United States)

... Staying Safe Videos for Educators Search English Español Car Seat Safety KidsHealth / For Parents / Car Seat Safety ... certified child passenger safety technician.) Guidelines for Choosing Car Seats Choose a seat with a label that ...

Safety of Sodium-Glucose Co-Transporter 2 Inhibitors during Ramadan Fasting: Evidence, Perceptions and Guidelines

Directory of Open Access Journals (Sweden)

Salem A. Beshyah

2016-06-01

Full Text Available Sodium-glucose co-transporter 2 (SGLT2 inhibitors are a new glucose-lowering therapy for T2DM with documented benefits on blood glucose, hypertension, weight reduction and long term cardiovascular benefit. They have an inherent osmotic diuretic effect and lead to some volume loss and possible dehydration. There is some concern about the safety of using SGLT2 inhibitors in Muslim type 2 diabetes mellitus (T2DM patients during the fast during Ramadan. Currently, there is a dearth of research data to help guide physicians and reassure patients.  One study confirmed good glycemic control with less risk of hypoglycemia and no marked volume depletion. Data in the elderly and in combination with diuretics are reassuring of their safe to use in Ramadan in general. SGLT2 inhibitor-related diabetic ketoacidosis has not been reported during Ramadan and is unlikely to be relevant. Survey of physicians revealed that the majority felt that SGLT2 inhibitors are generally safe in T2DM patients during Ramadan fasting but should be discontinued in certain high risk patients. Some professional groups with interest in diabetes and Ramadan fasting included SGLT2 inhibitors in their guidelines on management of diabetes during Ramadan. They acknowledged the lack of trial data, recommended caution in high risk groups, advised regular monitoring and emphasized pre-Ramadan patients’ education. In conclusion, currently, knowledge, data and experience with SGLT2 inhibitors in Ramadan are limited. Nonetheless, stable patients with normal kidney function and low risk of dehydration may safely use the SGLT2 inhibitors therapy. Higher risk patients should be observed carefully and managed on individual basis.

Bathroom safety - children

Science.gov (United States)

Well child - bathroom safety ... be put in charge of a younger child's safety. There should be an adult in the bathroom ... sure grandparents, friends, and other caretakers follow bathroom safety guidelines. Make sure your child's daycare also follows ...

It’s all about safety signs!

CERN Multimedia

2013-01-01

Their first occurrence may date back to the Egyptian hieroglyphs, but today they can be found everywhere: on our clothes labels as care labels, in train stations and airports to guide us, during the Olympics to identify various sports, on our dashboards, etc.   Safety wise, they are used to indicate a danger, a prohibition, an obligation, a safety exit, firefighting equipment, etc. The HSE Unit has decided to update the 150 safety signs used on the CERN site and, to correspond with this, recently published a Safety Guideline GS-1-0-1, available on the Safety Unit website. The Guideline contains more than 150 safety signs as well as diverse information regarding the meaning of the signs, their location and how to use them. The Guideline will shortly be completed with a new Safety Rule that will replace the former Security Code A3, “Safety colours and safety signs”. Please be informed that you also have the option to create new safety signs, provided that you first g...

General Guidelines on Criteria for Adoption or Rejection of Evaluated Libraries and Data by the Nuclear Data Team

Energy Technology Data Exchange (ETDEWEB)

Neudecker, Denise [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Conlin, Jeremy Lloyd [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Gray, Mark Girard [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); McCartney, Austin Paul [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Parsons, Donald Kent [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); White, Morgan Curtis [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-04-12

This memo contains general guidelines on what documentation and tools need to be in place as well as format and data testing requirements such that evaluated nuclear data sets or entire libraries can be adopted by the nuclear data team. Additional requirements beyond this memo might apply for specific nuclear data observables. These guidelines were established based on discussions between J.L. Conlin, M.G. Gray, A.P. McCartney, D. Neudecker, D.K. Parsons and M.C. White.

Executing Medical Guidelines on the Web: Towards Next Generation Healthcare

Science.gov (United States)

Argüello, M.; Des, J.; Fernandez-Prieto, M. J.; Perez, R.; Paniagua, H.

There is still a lack of full integration between current Electronic Health Records (EHRs) and medical guidelines that encapsulate evidence-based medicine. Thus, general practitioners (GPs) and specialised physicians still have to read document-based medical guidelines and decide among various options for managing common non-life-threatening conditions where the selection of the most appropriate therapeutic option for each individual patient can be a difficult task. This paper presents a simulation framework and computational test-bed, called V.A.F. Framework, for supporting simulations of clinical situations that boosted the integration between Health Level Seven (HL7) and Semantic Web technologies (OWL, SWRL, and OWL-S) to achieve content layer interoperability between online clinical cases and medical guidelines, and therefore, it proves that higher integration between EHRs and evidence-based medicine can be accomplished which could lead to a next generation of healthcare systems that provide more support to physicians and increase patients' safety.

Development of human factors design review guidelines

International Nuclear Information System (INIS)

Lee, Jung Woon; Oh, In Suk; Suh, Sang Moon; Lee, Hyun Chul

1997-10-01

The Objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: '25, Human factors engineering program review model' and '26, Review criteria for human actors aspects of advanced controls and instrumentation', which are related to the development of human factors safety regulation guides be ing performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and reviewing the reference documents of NUREG-0711. We also computerized the Korean version of NUREG-0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm systems. Then we well update the guidelines by reviewing the literature related to alarm design published after 1994

Development of human factors design review guidelines

Energy Technology Data Exchange (ETDEWEB)

Lee, Jung Woon; Oh, In Suk; Suh, Sang Moon; Lee, Hyun Chul [Korea Atomic Energy Research Institute, Taejon (Korea)

1997-10-01

The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: 25. Human Factors Engineering Program Review Model and 26. Review Criteria for Human Factors Aspects of Advanced Controls and Instrumentation, which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and reviewing the reference documents of NUREG-0711. We also computerized the Korean version of NUREG-0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm systems. Then we will update the guidelines by reviewing the literature related to alarm design published after 1994. (author). 12 refs., 5 figs., 2 tabs.

Guidelines for environmental monitoring after acute oil spill in the marine environment; Retningslinjer for miljoeundersoekelser i marint miljoe etter akutt oljeforurensning

Energy Technology Data Exchange (ETDEWEB)

Joergensen, N.M.; Camus, L.-H.; Larsen, B.; Voegele, G.M.; Spikkerud, C.; Anker-Nilsen, T.; Dijk, J van; Lorentsen, S.-H.; Stabbetorp, O.; Bjoerge, A.; Boitsov, S.; Klungsoeyr, J.

2012-07-01

Contents of environmental damage assessments and monitoring of acute oil spills in the marine environment are outlined. The guideline provides general advice on timing, contents and scope of post spill surveys for documenting biological recovery and food safety.(Author)

Joint IAEA/NEA IRS guidelines

International Nuclear Information System (INIS)

1997-01-01

The Incident Reporting System (IRS) is an international system jointly operated by the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency of the Organization for Economic Cooperation and Development (OECD/NEA). The fundamental objective of the IRS is to contribute to improving the safety of commercial nuclear power plants (NPPs) which are operated worldwide. This objective can be achieved by providing timely and detailed information on both technical and human factors related to events of safety significance which occur at these plants. The purpose of these guidelines, which supersede the previous IAEA Safety Series No. 93 (Part II) and the NEA IRS guidelines, is to describe the system and to give users the necessary background and guidance to enable them to produce IRS reports meeting a high standard of quality while retaining the high efficiency of the system expected by all Member States operating nuclear power plants

7 CFR 622.5 - Guidelines.

Science.gov (United States)

2010-01-01

... 7 Agriculture 6 2010-01-01 2010-01-01 false Guidelines. 622.5 Section 622.5 Agriculture... AGRICULTURE WATER RESOURCES WATERSHED PROJECTS General § 622.5 Guidelines. Guidelines for carrying out... Environmental Principles and Guidelines for Water and Related Land Resources Implementation Studies issued by...

Safety training and safe operating procedures written for PBFA (Particle Beam Fusion Accelerator) II and applicable to other pulsed power facilities

Energy Technology Data Exchange (ETDEWEB)

Donovan, G.L.; Goldstein, S.A.

1986-12-01

To ensure that work in advancing pulsed power technology is performed with an acceptably low risk, pulsed power research facilities at Sandia National Laboratories must satisfy general safety guidelines established by the Department of Energy, policies and formats of the Environment, Safety, and Health (ES and H) Department, and detailed procedures formulated by the Pulsed Power Sciences Directorate. The approach to safety training and to writing safe operating procedures, and the procedures presented here are specific to the Particle Beam Fusion Accelerator II (PBFA II) Facility but are applicable as guidelines to other research and development facilities which have similar hazards.

Safety training and safe operating procedures written for PBFA [Particle Beam Fusion Accelerator] II and applicable to other pulsed power facilities

International Nuclear Information System (INIS)

Donovan, G.L.; Goldstein, S.A.

1986-12-01

To ensure that work in advancing pulsed power technology is performed with an acceptably low risk, pulsed power research facilities at Sandia National Laboratories must satisfy general safety guidelines established by the Department of Energy, policies and formats of the Environment, Safety, and Health (ES and H) Department, and detailed procedures formulated by the Pulsed Power Sciences Directorate. The approach to safety training and to writing safe operating procedures, and the procedures presented here are specific to the Particle Beam Fusion Accelerator II (PBFA II) Facility but are applicable as guidelines to other research and development facilities which have similar hazards

Methods of checking general safety criteria in UML statechart specifications

International Nuclear Information System (INIS)

Pap, Zsigmond; Majzik, Istvan; Pataricza, Andras; Szegi, Andras

2005-01-01

This paper describes methods and tools for safety analysis of UML statechart specifications. A comprehensive set of general safety criteria including completeness and consistency is applied in automated analysis. Analysis techniques are based on OCL expressions, graph transformations and reachability analysis. Two canonical intermediate representations of the statechart specification are introduced. They are suitable for straightforward implementation of checker methods and for the support of the proof of the correctness and soundness of the applied analysis. One of them also serves as a basis of the metamodel of a variant of UML statecharts proposed for the specification of safety-critical control systems. The analysis is extended to object-oriented specifications. Examples illustrate the application of the checker methods implemented by an automated tool-set

Guideline Adherence of Antithrombotic Treatment Initiated by General Practitioners in Patients With Nonvalvular Atrial Fibrillation: A Danish Survey

DEFF Research Database (Denmark)

Brandes, Axel; Overgaard, Mikkel; Plauborg, Liane

2013-01-01

with a mean age of 74.811.2 years. The mean CHADS(2) and CHA(2)DS(2)-VASc scores were 1.9 +/- 1.3 and 3.5 +/- 1.8, respectively. Of the patients, 12.4% and 4.04%, respectively, were at truly low risk, with a CHADS(2) and CHA(2)DS(2)-VASc score 0 (P ... proportion of patients with nonvalvular AF do not receive guideline-adherent antithrombotic treatment in primary care. MethodsWe performed a cross-sectional survey of antithrombotic treatment using data of AF patients from general practices. ResultsSixty-four general practitioners enrolled 1743 patients......) score. Applying the CHA(2)DS(2)-VASc score, this proportion was only 53.4%. Antiplatelet drug treatment was in adherence to the guidelines (CHADS(2) and CHA(2)DS(2)-VASc score of 1) in only 31% and 12% of the patients, respectively. ConclusionsAntithrombotic treatment of AF patients is in general well...

Chemical Hazards and Safety Issues in Fusion Safety Design

International Nuclear Information System (INIS)

Cadwallader, L.C.

2003-01-01

Radiological inventory releases have dominated accident consequences for fusion; these consequences are important to analyze and are generally the most severe result of a fusion facility accident event. However, the advent of, or plan for, large-scale usage of some toxic materials poses the additional hazard of chemical exposure from an accident event. Examples of toxic chemicals are beryllium for magnetic fusion and fluorine for laser fusion. Therefore, chemical exposure consequences must also be addressed in fusion safety assessment. This paper provides guidance for fusion safety analysis. US Department of Energy (DOE) chemical safety assessment practices for workers and the public are reviewed. The US Environmental Protection Agency (EPA) has published some guidance on public exposure to releases of mixtures of chemicals, this guidance has been used to create an initial guideline for treating mixed radiological and toxicological releases in fusion; for example, tritiated hazardous dust from a tokamak vacuum vessel. There is no convenient means to judge the hazard severity of exposure to mixed materials. The chemical fate of mixed material constituents must be reviewed to determine if there is a separate or combined radiological and toxicological carcinogenesis, or if other health threats exist with radiological carcinogenesis. Recommendations are made for fusion facility chemical safety evaluation and safety guidance for protecting the public from chemical releases, since such levels are not specifically identified in the DOE fusion safety standard

Safety system status monitoring

International Nuclear Information System (INIS)

Lewis, J.R.; Morgenstern, M.H.; Rideout, T.H.; Cowley, P.J.

1984-03-01

The Pacific Northwest Laboratory has studied the safety aspects of monitoring the preoperational status of safety systems in nuclear power plants. The goals of the study were to assess for the NRC the effectiveness of current monitoring systems and procedures, to develop near-term guidelines for reducing human errors associated with monitoring safety system status, and to recommend a regulatory position on this issue. A review of safety system status monitoring practices indicated that current systems and procedures do not adequately aid control room operators in monitoring safety system status. This is true even of some systems and procedures installed to meet existing regulatory guidelines (Regulatory Guide 1.47). In consequence, this report suggests acceptance criteria for meeting the functional requirements of an adequate system for monitoring safety system status. Also suggested are near-term guidelines that could reduce the likelihood of human errors in specific, high-priority status monitoring tasks. It is recommended that (1) Regulatory Guide 1.47 be revised to address these acceptance criteria, and (2) the revised Regulatory Guide 1.47 be applied to all plants, including those built since the issuance of the original Regulatory Guide

Safety system status monitoring

Energy Technology Data Exchange (ETDEWEB)

Lewis, J.R.; Morgenstern, M.H.; Rideout, T.H.; Cowley, P.J.

1984-03-01

The Pacific Northwest Laboratory has studied the safety aspects of monitoring the preoperational status of safety systems in nuclear power plants. The goals of the study were to assess for the NRC the effectiveness of current monitoring systems and procedures, to develop near-term guidelines for reducing human errors associated with monitoring safety system status, and to recommend a regulatory position on this issue. A review of safety system status monitoring practices indicated that current systems and procedures do not adequately aid control room operators in monitoring safety system status. This is true even of some systems and procedures installed to meet existing regulatory guidelines (Regulatory Guide 1.47). In consequence, this report suggests acceptance criteria for meeting the functional requirements of an adequate system for monitoring safety system status. Also suggested are near-term guidelines that could reduce the likelihood of human errors in specific, high-priority status monitoring tasks. It is recommended that (1) Regulatory Guide 1.47 be revised to address these acceptance criteria, and (2) the revised Regulatory Guide 1.47 be applied to all plants, including those built since the issuance of the original Regulatory Guide.

ASSET guidelines

International Nuclear Information System (INIS)

1990-11-01

The IAEA Assessment of Safety Significant Events Team (ASSET) Service provides advice and assistance to Member States to enhance the overall level of plant safety while dealing with the policy of prevention of incidents at nuclear power plants. The ASSET programme, initiated in 1986, is not restricted to any particular group of Member States, whether developing or industrialized, but is available to all countries with nuclear power plants in operation or approaching commercial operation. The IAEA Safety Series publications form common basis for the ASSET reviews, including the Nuclear Safety Standards (NUSS) and the Basic Safety Principles (Recommendations of Safety Series No. 75-INSAG-3). The ASSET Guidelines provide overall guidance for the experts to ensure the consistency and comprehensiveness of their review of incident investigations. Additional guidance and reference material is provided by the IAEA to complement the expertise of the ASSET members. ASSET reviews accept different approaches that contribute to ensuring an effective prevention of incidents at plants. Suggestions are offered to enhance plant safety performance. Commendable good practices are identified and generic lessons are communicated to other plants, where relevant, for long term improvement

Technical Issues and Proposes on the Legislation of Probabilistic Safety Assessment in Periodic Safety Review

International Nuclear Information System (INIS)

Hwang, Seok-Won; Jeon, Ho-Jun; Na, Jang-Hwan

2015-01-01

Korean Nuclear Power Plants have performed a comprehensive safety assessment reflecting design and procedure changes and using the latest technology every 10 years. In Korea, safety factors of PSR are revised to 14 by revision of IAEA Safety Guidelines in 2003. In the revised safety guidelines, safety analysis field was subdivided into deterministic safety analysis, PSA (Probabilistic safety analysis), and hazard analysis. The purpose to examine PSA as a safety factor on PSR is to make sure that PSA results and assumptions reflect the latest state of NPPs, validate the level of computer codes and analytical models, and evaluate the adequacy of PSA instructions. In addition, its purpose is to derive the plant design change, operating experience of other plants and safety enhancement items as well. In Korea, PSA is introduced as a new factor. Thus, the overall guideline development and long-term implementation strategy are needed. Today in Korea, full-power PSA model revision and low-power and shutdown (LPSD) PSA model development is being performed as a part of the post Fukushima action items for operating plants. The scope of the full-power PSA is internal/external level 1, 2 PSA. But in case of fire PSA, the scope is level 1 PSA using new method, NUREG/CR-6850. In case of LPSD PSA, level 1 PSA for all operating plants, and level 2 PSA for 2 demonstration plants are under development. The result of the LPSD PSA will be used as major input data for plant specific SAMG (Severe Accident Management Guideline). The scope of PSA currently being developed in Korea cannot fulfill 'All Mode, All Scope' requirements recommended in the IAEA Safety Guidelines. Besides the legislation of PSA, step-by-step development strategy for non-performed scopes such as level 3 PSA and new fire PSA is one of the urgent issues in Korea. This paper suggests technical issues and development strategies for each PSA technical elements.

Inspector qualification guidelines

International Nuclear Information System (INIS)

Batty, A.C.; Van Binnebeek, J.J.; Ericsson, P.O.; Fisher, J.C.; Geiger, P.; Grandame, M.; Grimes, B.K.; Joode, A. de; Kaufer, B.; Kinoshita, M.; Klonk, H.; Koizumi, H.; Maeda, N.; Maqua, M.; Perez del Moral, C.; Roselli, F.; Warren, T.; Zimmerman, R.

1994-07-01

The OECD Nuclear Energy Agency Committee on Nuclear Regulatory Activities (CNRA) has a Working Group on Inspection Practices (WGIP). The WGIP provides a forum for the exchange of Information and experience on the safety Inspection practices of regulatory authorities In the CNRA member countries. A consistent qualification process and well defined level of training for all Inspectors who participate In the safety Inspections are needed to provide consistent Inspections and reliable Inspection results. The WGIP organized in 1992 a workshop on the conduct of inspections, inspector qualification and training, and shutdown inspections at the Technical Training Center of the US NRC in Chattanooga, Tennessee. In the connection of workshop the WGIP identified a need to develop guidance for inspector qualification which could be used as a model by those who are developing their qualification practices. The inspector qualification journals of US NRC provided a good basis for the work. The following inspector qualification guideline has been developed for guidance of qualification of a new inspector recruited to the regulatory body. This guideline has been developed for helping the supervisors and training officers to give the initial training and familiarization to the duties of a new inspector in a controlled manner. US NRC inspector qualification journals have been used to define the areas of attention. This guideline provides large flexibility for application in different type organizations. Large organizations can develop separate qualification journals for each inspector positions. Small regulatory bodies can develop individual training programmes by defining the necessary training topics on case by case basis. E.g. the guideline can be used to define the qualifications of contracted inspectors used in some countries. The appropriate part would apply. Annex 1 gives two examples how this guideline could be applied

Inspector qualification guidelines

Energy Technology Data Exchange (ETDEWEB)

Batty, A. C.; Van Binnebeek, J. J.; Ericsson, P. O.; Fisher, J. C.; Geiger, P.; Grandame, M.; Grimes, B. K.; Joode, A. de; Kaufer, B.; Kinoshita, M.; Klonk, H.; Koizumi, H.; Maeda, N.; Maqua, M.; Perez del Moral, C.; Roselli, F.; Warren, T.; Zimmerman, R.

1994-07-15

The OECD Nuclear Energy Agency Committee on Nuclear Regulatory Activities (CNRA) has a Working Group on Inspection Practices (WGIP). The WGIP provides a forum for the exchange of Information and experience on the safety Inspection practices of regulatory authorities In the CNRA member countries. A consistent qualification process and well defined level of training for all Inspectors who participate In the safety Inspections are needed to provide consistent Inspections and reliable Inspection results. The WGIP organized in 1992 a workshop on the conduct of inspections, inspector qualification and training, and shutdown inspections at the Technical Training Center of the US NRC in Chattanooga, Tennessee. In the connection of workshop the WGIP identified a need to develop guidance for inspector qualification which could be used as a model by those who are developing their qualification practices. The inspector qualification journals of US NRC provided a good basis for the work. The following inspector qualification guideline has been developed for guidance of qualification of a new inspector recruited to the regulatory body. This guideline has been developed for helping the supervisors and training officers to give the initial training and familiarization to the duties of a new inspector in a controlled manner. US NRC inspector qualification journals have been used to define the areas of attention. This guideline provides large flexibility for application in different type organizations. Large organizations can develop separate qualification journals for each inspector positions. Small regulatory bodies can develop individual training programmes by defining the necessary training topics on case by case basis. E.g. the guideline can be used to define the qualifications of contracted inspectors used in some countries. The appropriate part would apply. Annex 1 gives two examples how this guideline could be applied.

[Guidelines for management of epilepsy--commentary on Scottish ("SIGN") guidelines].

Science.gov (United States)

Planjar-Prvan, Miljenka; Granić, Davorka

2005-01-01

The choice of AED (antiepileptic drug), worldwide and in Croatia, is been still based on the physician's subjective decision, personal experience, knowledge and marketing pressure made by big pharmaceutical industries. Therefore, according to some opinions, there is a need of treatment guidelines for epilepsy that would provide relevant information based on scientific evidence on the efficacy, tolerability and safety of AEDs. The guidelines, published by a competent source, should be designed as to allow for easy access to the information on the best practice in specific cases. An extensive background literature review was made to identify such a type of guidelines for the management of epilepsy. The literature review revealed a number of references with the recommendations for treating epilepsy in different groups of patients and from various, specific aspects of epilepsy treatment. However, only one comprehensive set of guidelines for the diagnosis and treatment of epilepsy treatment was found, i.e. the evidence-based guidelines published by the Scottish Intercollegiate Guidelines Network (SIGN). The development of this set of guidelines is quite extensively described in order to illustrate how rigorous and long-lasting the process was, including a great number of health professionals at the national level. Such a type of well designed guidelines facilitates access to highest educational standards for all professionals involved in the primary and secondary care of people with epilepsy. However, it is clear that guidelines can fully replace the standards of clinical practice based on critical evaluation and integration of all clinical data of each individual patient. No guidelines can replace the physician's obligation to keep informed of the novel achievements in the epileptology either.

EDF - The Inspector General's report on Nuclear Safety and Radiation Protection 2012

International Nuclear Information System (INIS)

2013-01-01

After a first chapter in which the Inspector General states his own vision of facts and results regarding nuclear safety and radiation protection for 2012, the next chapters address the following topics: the contrasted results of nuclear operating safety, the need to remain vigilant in nuclear safety management, the challenge of occupational safety, the need of new ambitious goals for radiation protection, an updated training which must be better led by line management, maintenance as a strategic issue, the long road ahead for nuclear technical information system (SDIN), the need of better attention to chemistry in operations, the new impetus of EPRs, plant life extension conditioned by nuclear safety, the mobilization of nuclear operators after Fukushima, and noteworthy operating events

General guidelines for the Assessment of Internal Dose from Monitoring Data (Project IDEAS)

International Nuclear Information System (INIS)

Doerfel, H.; Andrasi, A.; Bailey, M.; Blanchardon, E.; Berkovski, V.; Castellani, C. M.; Hurtgen, C.; Jourdain, J. R.; LeGuen, B.; Puncher, M.

2004-01-01

In recent major international intercomparison exercises on intake and internal dose assessments from monitoring data the results calculated by different participants varied significantly. This was mainly due to the broad variety of methods and assumptions applied in the assessment procedure. Based on these experiences the need for harmonisation of the procedures has been formulated within an EU research project under the 5th Framework Programme. The aim of the project, IDEAS, is to develop general guidelines for standardising assessments of intakes and internal doses. The IDEAS project started in October 2001 and will end in March 2005. Eight institutions from seven European countries are participating. Inputs from internal dosimetry professionals from across Europe are also being used to ensure a broad consensus in the outcome of the project. The IDEAS project is closely related to some goals of the work of Committee 2 of the ICRP and since 2003 there has been close cooperation between the two groups. To ensure that the guidelines are applicable to a wide range of practical situations, the first step has been to compile a database of well-documented cases of internal contamination. In parallel, an improved version of an existing software package has been developed and distributed to the partners for further use. A large number of cases from the database have been evaluated independently by partners in the project using the same software and the results have been reviewed. Based on these evaluations guidelines are being drafted and will be discussed with dosimetry professionals from around the world by means of a virtual workshop on the Internet early in 2004. The guidelines will be revised and refined on the basis of the experiences and discussions of this virtual workshop and the outcome of an intercomparison exercise organised as part of the project. This will be open to all internal dosimetry professionals. (Author) 10 refs

Training Requirements in OSHA Standards and Training Guidelines. Revised.

Science.gov (United States)

Occupational Safety and Health Administration, Washington, DC.

This guide provides an overview of Occupational Safety and Health Act (OSHA) standards and training guidelines for various industries. The first section introduces the concept of voluntary training guidelines, explaining that the guidelines are designed to help employers determine whether a worksite problem can be solved by training, what training…

10 CFR 960.3 - Implementation guidelines.

Science.gov (United States)

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Implementation guidelines. 960.3 Section 960.3 Energy DEPARTMENT OF ENERGY GENERAL GUIDELINES FOR THE PRELIMINARY SCREENING OF POTENTIAL SITES FOR A NUCLEAR WASTE REPOSITORY Implementation Guidelines § 960.3 Implementation guidelines. The guidelines of this subpart...

21 CFR 170.20 - General principles for evaluating the safety of food additives.

Science.gov (United States)

2010-04-01

... food additives. 170.20 Section 170.20 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) FOOD FOR HUMAN CONSUMPTION (CONTINUED) FOOD ADDITIVES Food Additive Safety § 170.20 General principles for evaluating the safety of food additives. (a) In reaching a...

Leadership and Management for Safety. General Safety Requirements (Arabic Edition)

International Nuclear Information System (INIS)

2016-01-01

This Safety Requirements publication establishes requirements that support Principle 3 of the Fundamental Safety Principles in relation to establishing, sustaining and continuously improving leadership and management for safety and an integrated management system. It emphasizes that leadership for safety, management for safety, an effective management system and a systemic approach (i.e. an approach in which interactions between technical, human and organizational factors are duly considered) are all essential to the specification and application of adequate safety measures and to the fostering of a strong safety culture. Leadership and an effective management system will integrate safety, health, environmental, security, quality, human-and-organizational factors, societal and economic elements. The management system will ensure the fostering of a strong safety culture, regular assessment of performance and the application of lessons from experience. The publication is intended for use by regulatory bodies, operating organizations and other organizations concerned with facilities and activities that give rise to radiation risks.

Leadership and Management for Safety. General Safety Requirements (Chinese Edition)

International Nuclear Information System (INIS)

2016-01-01

This Safety Requirements publication establishes requirements that support Principle 3 of the Fundamental Safety Principles in relation to establishing, sustaining and continuously improving leadership and management for safety and an integrated management system. It emphasizes that leadership for safety, management for safety, an effective management system and a systemic approach (i.e. an approach in which interactions between technical, human and organizational factors are duly considered) are all essential to the specification and application of adequate safety measures and to the fostering of a strong safety culture. Leadership and an effective management system will integrate safety, health, environmental, security, quality, human-and-organizational factors, societal and economic elements. The management system will ensure the fostering of a strong safety culture, regular assessment of performance and the application of lessons from experience. The publication is intended for use by regulatory bodies, operating organizations and other organizations concerned with facilities and activities that give rise to radiation risks.

Leadership and Management for Safety. General Safety Requirements (French Edition)

International Nuclear Information System (INIS)

2016-01-01

This Safety Requirements publication establishes requirements that support Principle 3 of the Fundamental Safety Principles in relation to establishing, sustaining and continuously improving leadership and management for safety and an integrated management system. It emphasizes that leadership for safety, management for safety, an effective management system and a systemic approach (i.e. an approach in which interactions between technical, human and organizational factors are duly considered) are all essential to the specification and application of adequate safety measures and to the fostering of a strong safety culture. Leadership and an effective management system will integrate safety, health, environmental, security, quality, human-and-organizational factors, societal and economic elements. The management system will ensure the fostering of a strong safety culture, regular assessment of performance and the application of lessons from experience. The publication is intended for use by regulatory bodies, operating organizations and other organizations concerned with facilities and activities that give rise to radiation risks.

Leadership and Management for Safety. General Safety Requirements (Spanish Edition)

International Nuclear Information System (INIS)

2017-01-01

his Safety Requirements publication establishes requirements that support Principle 3 of the Fundamental Safety Principles in relation to establishing, sustaining and continuously improving leadership and management for safety and an integrated management system. It emphasizes that leadership for safety, management for safety, an effective management system and a systemic approach (i.e. an approach in which interactions between technical, human and organizational factors are duly considered) are all essential to the specification and application of adequate safety measures and to the fostering of a strong safety culture. Leadership and an effective management system will integrate safety, health, environmental, security, quality, human-and-organizational factors, societal and economic elements. The management system will ensure the fostering of a strong safety culture, regular assessment of performance and the application of lessons from experience. The publication is intended for use by regulatory bodies, operating organizations and other organizations concerned with facilities and activities that give rise to radiation risks.

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

International Nuclear Information System (INIS)

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

2013-06-01

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

Metrics design for safety assessment

NARCIS (Netherlands)

Luo, Yaping; van den Brand, M.G.J.

2016-01-01

Context:In the safety domain, safety assessment is used to show that safety-critical systems meet the required safety objectives. This process is also referred to as safety assurance and certification. During this procedure, safety standards are used as development guidelines to keep the risk at an

Generally Recognized as Safe: Uncertainty Surrounding E-Cigarette Flavoring Safety

Directory of Open Access Journals (Sweden)

Clara G. Sears

2017-10-01

Full Text Available Despite scientific uncertainty regarding the relative safety of inhaling e-cigarette aerosol and flavorings, some consumers regard the U.S. Food and Drug Administration’s “generally recognized as safe” (GRAS designation as evidence of flavoring safety. In this study, we assessed how college students’ perceptions of e-cigarette flavoring safety are related to understanding of the GRAS designation. During spring 2017, an online questionnaire was administered to college students. Chi-square p-values and multivariable logistic regression were employed to compare perceptions among participants considering e-cigarette flavorings as safe and those considering e-cigarette flavorings to be unsafe. The total sample size was 567 participants. Only 22% knew that GRAS designation meant that a product is safe to ingest, not inhale, inject, or use topically. Of participants who considered flavorings to be GRAS, the majority recognized that the designation meant a product is safe to ingest but also considered it safe to inhale. Although scientific uncertainty on the overall safety of flavorings in e-cigarettes remains, health messaging can educate the public about the GRAS designation and its irrelevance to e-cigarette safety.

Guidelines for safely changing to S.I. radiological units

International Nuclear Information System (INIS)

Canada is adopting the International System of Units (SI) in all sectors of the economy. The basic radiological units formerly in use, the curie, rad, rem, and roentgen are being replaced by the becquerel, gray, sievert, and coulomb per kilogram. During the transition period for conversion to SI units some problems may arise concerning received or administered radiation doses. These guidelines exaiine the occupational safety ramifications of of the change to SI by identifying the major safety concerns and providing guidelines for applying a model method within individual organizations for analyzing safety implicatikns during the changeover period

10 CFR 960.5 - Preclosure guidelines.

Science.gov (United States)

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Preclosure guidelines. 960.5 Section 960.5 Energy DEPARTMENT OF ENERGY GENERAL GUIDELINES FOR THE PRELIMINARY SCREENING OF POTENTIAL SITES FOR A NUCLEAR WASTE REPOSITORY Preclosure Guidelines § 960.5 Preclosure guidelines. The guidelines in this subpart specify the...

10 CFR 960.4 - Postclosure guidelines.

Science.gov (United States)

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Postclosure guidelines. 960.4 Section 960.4 Energy DEPARTMENT OF ENERGY GENERAL GUIDELINES FOR THE PRELIMINARY SCREENING OF POTENTIAL SITES FOR A NUCLEAR WASTE REPOSITORY Postclosure Guidelines § 960.4 Postclosure guidelines. The guidelines in this subpart specify the...

21 CFR 570.20 - General principles for evaluating the safety of food additives.

Science.gov (United States)

2010-04-01

... food additives. 570.20 Section 570.20 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) ANIMAL DRUGS, FEEDS, AND RELATED PRODUCTS FOOD ADDITIVES Food Additive Safety § 570.20 General principles for evaluating the safety of food additives. (a) In reaching a...

Human factors design review guidelines for advanced nuclear control room technologies

International Nuclear Information System (INIS)

O'Hara, J.; Brown, W.; Granda, T.; Baker, C.

1991-01-01

Advanced control rooms (ACRs) for future nuclear power plants are being designed utilizing computer-based technologies. The US Nuclear Regulatory Commission reviews the human engineering aspects of such control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported in order to protect public health and safety. This paper describes the rationale, general approach, and initial development of an NRC Advanced Control Room Design Review Guideline. 20 refs., 1 fig

Development of human factors design review guidelines(II)

Energy Technology Data Exchange (ETDEWEB)

Lee, Jung Woon; Oh, In Suk; Suh, Sang Moon; Lee, Hyun Chul [Korea Atomic Energy Research Institute, Taejon (Korea)

1998-06-01

The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: 25. Human Factors Engineering Program Review Model and 26. Review Criteria for Human Factors Aspects of Advanced Controls and Instrumentation, which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and reviewing the reference documents of NUREG-0711. We also computerized the Korean version of NUREG-0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm systems. Then we will update the guidelines by reviewing the literature related to alarm design published after 1994. (author). 11 refs., 2 figs., 2 tabs.

General Quality Control (QC) Guidelines for SAM Methods

Science.gov (United States)

Learn more about quality control guidelines and recommendations for the analysis of samples using the methods listed in EPA's Selected Analytical Methods for Environmental Remediation and Recovery (SAM).

Advanced control room evaluation: General approach and rationale

International Nuclear Information System (INIS)

O'Hara, J.M.; Wachtel, J.

1991-01-01

Advanced control rooms (ACRs) for future nuclear power plants (NPPs) are being designed utilizing computer-based technologies. The US Nuclear Regulatory Commission reviews the human engineering aspects of such control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported in order to protect public health and safety. This paper describes the rationale and general approach to the development of a human factors review guideline for ACRs. The factors influencing the guideline development are discussed, including the review environment, the types of advanced technologies being addressed, the human factors issues associated with advanced technology, and the current state-of-the-art of human factors guidelines for advanced human-system interfaces (HSIs). The proposed approach to ACR review would track the design and implementation process through the application of review guidelines reflecting four review modules: planning, design process analysis, human factors engineering review, and dynamic performance evaluation. 21 refs

Reactor Safety Commission Code of Practice for Pressurized Water Reactors

International Nuclear Information System (INIS)

1990-01-01

The Reactor Safety Commission of the Federal German Republic has summarized in the form of Official Guidelines the safety requirements which, in the Commission's view, have to be met in the design, construction and operation of a nuclear power station equipped with a pressurized water reactor. The Third Edition of the RSK Guidelines for pressurized water reactors dated 14.10.81. is a revised and expanded version of the Second Edition dated 24.1.79. The Reactor Safety Commission will with effect from October 1981 use these Guidelines in consultations on the siting of and safety concept for the installation approval of future pressurized water reactors and will assess these nuclear power stations during their erection in the light of these Guidelines. They have not however been immediately conceived for the adaptation of existing nuclear power stations, whether under construction or in operation. The scope of application of these Guidelines to such nuclear power stations will have to be examined for each individual case. The main aim of the Guidelines is to simplify the consultation process within the reactor Safety Commission and to provide early advice on the safety requirements considered necessary by the Commission. (author)

Best Practice Guidelines for the Use of CFD in Nuclear Reactor Safety Applications - Revision

International Nuclear Information System (INIS)

Mahaffy, J.; Chung, B.; Song, C.; Dubois, F.; Graffard, E.; Ducros, F.; Heitsch, M.; Scheuerer, M.; Henriksson, M.; Komen, E.; Moretti, F.; Morii, T.; Muehlbauer, P.; Rohde, U.; Smith, B.L.; Watanabe, T.; Zigh, G.

2015-01-01

This document is intended to provide an internally complete set of guidelines for a range of single phase applications of CFD to NRS problems. However, it is not meant to be comprehensive. We recognize that for any specific application a higher level of specificity is possible on questions of nodalization, model selection, and validation. This document should provide direct guidance on the key considerations in known single phase applications, and general directions for resolving remaining details. After review of other Best Practice Guidelines, and discussion with many CFD practitioners and developers, we have assembled guidance covering a fully verified and validated NRS analysis. The document begins with a summary of NRS related CFD analysis in countries represented by the authors, to give a feeling for the existing range of experience. Some key terminology in the field is defined in the field. These definitions are not meant simply for novices, but also provide experienced users with an understanding of how some terms (e.g. verification and validation) are used within this document. Chapter 3 deals with definition of the problem and its solution approach. This includes isolation of the portion of the NRS problem most in need of CFD, and use of a classic thermal-hydraulic (TH) safety code to provide boundary conditions for the CFD based upon less detailed simulation of the balance of plant. The chapter discusses the Phenomena Identification and Ranking Table (PIRT) process, which identifies phenomena critical to the problem, provides a basis for selection of an appropriate simulation tool, and establishes the foundation for the validation process needed for confidence in final results. The chapter also discusses theory and modelling needs associated with a number of special phenomena important to NRS but not commonly modelled in the CFD community. Chapter 5 discusses selection of physical models available as user options. As is appropriate for single phase CFD

Nuclear Waste Policy Act of 1982; proposed general guidelines for recommendation of sites for nuclear waste repositories

International Nuclear Information System (INIS)

Anon.

1983-01-01

In accordance with the requirements of the Nuclear Waste Policy Act of 1982 (Pub. L. 97-425), hereinafter referred to as the Act, the Department of Energy is proposing general guidelines for the recommendation of sites for repositories for disposal of high-level radioactive waste and spent nuclear fuel in geologic formations. These guidelines are based on the criteria that the Department has used in its National Waste Terminal Storage program, the criteria proposed by the Nuclear Regulatory Commission (NRC), and the environmental standards proposed by the Environmental Protection Agency. These guidelines establish the performance requirements for a geologic repository system, specify how the Department will implement its site-selection program, and define the technical qualifications that candidate sites must meet in the various steps of the site-selection process mandated by the Act. After considering comments from the public; consulting with the Council on Environmental Quality, the Administrator of the Environmental Protection Agency, the Director of the Geological Survey, and interested Governors; and obtaining NRC concurrence, the Department will issue these guidelines in final form as a new Part 960 to Title 10 of the Code of Federal Regulations (10 CFR Part 960)

Evidence-based guidelines

DEFF Research Database (Denmark)

Wattjes, Mike P; Rovira, Àlex; Miller, David

2015-01-01

. This use of MRI can help predict treatment response and assess the efficacy and safety of new therapies. In the second part of the MAGNIMS (Magnetic Resonance Imaging in MS) network's guidelines on the use of MRI in MS, we focus on the implementation of this technique in prognostic and monitoring tasks. We...

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

International Nuclear Information System (INIS)

2013-05-01

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

AREVA General Inspectorate 2010 Annual Report. Status of safety in nuclear facilities

International Nuclear Information System (INIS)

2010-01-01

After messages by different managers, this report proposes a description of the context for nuclear safety: group's policy in matters of nuclear safety and radiation protection, regulatory changes (in France, with respect to information, changes in administrative organization, overhaul of general technical regulations, international context). It describes the organizational changes which occurred within the company. It reports actions regarding transparency, briefly describes actions and principles aimed at improving safety, indicates and comments noteworthy nuclear events, discusses their assessment from a HOF (human and organizational factors) perspective, comments lessons learned from inspections, comments data regarding radiation protection and actions aimed at improving radiation protection. It discusses environmental impact issues. It addresses the different processes and factors which transversely appear in nuclear safety: safety management, human and organizational factors, safety in design, project management, and emergency management. Several specific risks are discussed: criticality control, nuclear materials safeguards, fire, spill prevention, transportation, radioactive waste, shutdown and dismantling, service operations, mining, and environmental liabilities. Document in French and in English

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

International Nuclear Information System (INIS)

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

2010-06-01

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

Safety Review related to Commercial Grade Digital Equipment in Safety System

International Nuclear Information System (INIS)

Yu, Yeongjin; Park, Hyunshin; Yu, Yeongjin; Lee, Jaeheung

2013-01-01

The upgrades or replacement of I and C systems on safety system typically involve digital equipment developed in accordance with non-nuclear standards. However, the use of commercial grade digital equipment could include the vulnerability for software common-mode failure, electromagnetic interference and unanticipated problems. Although guidelines and standards for dedication methods of commercial grade digital equipment are provided, there are some difficulties to apply the methods to commercial grade digital equipment for safety system. This paper focuses on regulatory guidelines and relevant documents for commercial grade digital equipment and presents safety review experiences related to commercial grade digital equipment in safety system. This paper focuses on KINS regulatory guides and relevant documents for dedication of commercial grade digital equipment and presents safety review experiences related to commercial grade digital equipment in safety system. Dedication including critical characteristics is required to use the commercial grade digital equipment on safety system in accordance with KEPIC ENB 6370 and EPRI TR-106439. The dedication process should be controlled in a configuration management process. Appropriate methods, criteria and evaluation result should be provided to verify acceptability of the commercial digital equipment used for safety function

International standardization of safety requirements for fast reactors

International Nuclear Information System (INIS)

2011-06-01

Japan Atomic Energy Agency (JAEA) is conducting the FaCT (Fast Reactor Cycle Technology Development) project in cooperation with Japan Atomic Power Company (JAPC) and Mitsubishi FBR systems inc. (MFBR), where an advanced loop-type fast reactor named JSFR (Japan Sodium-cooled Fast Reactor) is being developed. It is important to develop software technologies (a safety guideline, safety design criteria, safety design standards etc.) of FBRs as well as hardware ones (a reactor plant itself) in order to address prospective worldwide utilization of FBR technology. Therefore, it is expected to establish a rational safety guideline applicable to the JSFR and harmonized with national nuclear-safety regulations as well, including Japan, the United States and the European Union. This report presents domestic and international status of safety guideline development for sodium-cooled fast reactors (SFRs), results of comparative study for safety requirements provided in existing documents and a proposal for safety requirements of future SFRs with a roadmap for their refinement and worldwide utilization. (author)

Guidelines for Biosafety Training Programs for Workers Assigned to BSL-3 Research Laboratories.

Science.gov (United States)

Homer, Lesley C; Alderman, T Scott; Blair, Heather Ann; Brocard, Anne-Sophie; Broussard, Elaine E; Ellis, Robert P; Frerotte, Jay; Low, Eleanor W; McCarthy, Travis R; McCormick, Jessica M; Newton, JeT'Aime M; Rogers, Francine C; Schlimgen, Ryan; Stabenow, Jennifer M; Stedman, Diann; Warfield, Cheryl; Ntiforo, Corrie A; Whetstone, Carol T; Zimmerman, Domenica; Barkley, Emmett

2013-03-01

The Guidelines for Biosafety Training Programs for Workers Assigned to BSL-3 Research Laboratories were developed by biosafety professionals who oversee training programs for the 2 national biocontainment laboratories (NBLs) and the 13 regional biocontainment laboratories (RBLs) that participate in the National Institute of Allergy and Infectious Diseases (NIAID) NBL/RBL Network. These guidelines provide a general training framework for biosafety level 3 (BSL-3) high-containment laboratories, identify key training concepts, and outline training methodologies designed to standardize base knowledge, understanding, and technical competence of laboratory personnel working in high-containment laboratories. Emphasis is placed on building a culture of risk assessment-based safety through competency training designed to enhance understanding and recognition of potential biological hazards as well as methods for controlling these hazards. These guidelines may be of value to other institutions and academic research laboratories that are developing biosafety training programs for BSL-3 research.

The safety of phosphodiesterase type 5 inhibitors for erectile dysfunction.

Science.gov (United States)

Ventimiglia, Eugenio; Capogrosso, Paolo; Montorsi, Francesco; Salonia, Andrea

2016-01-01

Phosphodiesterase type 5 inhibitors (PDE5Is) are the leading drugs for the treatment of erectile dysfunction (ED), being recommended as a first line treatment by both the European and US urological guidelines. PDE5Is are highly effective as compared to placebo, well tolerated and have a very low, though not negligible, rate of severe treatment-related adverse events. This paper reviews the safety profile of currently available PDE5Is, comparing them in a broad spectrum ED population and outlining a number of real-life aspects of importance in the real-life everyday clinical setting. Guidelines unanimously agree in considering PDE5Is as first line treatments for ED when well-tolerated and not contraindicated. Despite the fact that no high-grade evidence comparing the efficacy and the safety for PDE5Is is currently available, published data seem to suggest that there are no major differences in their safety profiles. Moreover, although oral PDE5Is were shown to cause more AEs than placebo, they were generally mild and well tolerated.

ASSET guidelines. Revised 1991 Edition

International Nuclear Information System (INIS)

1991-12-01

The present publication is an updated version of the IAEA Assessment of Safety Significant Events Team (ASSET) Guidelines, IAEA-TECDOC-573, published in 1990. Sections 5 and 6 include revised definitions and investigation guidelines for identification of both direct and root causes. These revisions were recommended by a Consultants Meeting held in Vienna on 3-7 December 1990. This guidance is not intended to infringe an expert's prerogative to investigate additional items. Its main purpose is to provide a basic structure and ensure consistency in the assessments. Use of the ASSET guidelines should also facilitate comparison between the observations made in different nuclear power plants and harmonize the reporting of generic ASSET results. The guidelines should always be used with a critical attitude and a view to possible improvements

ECORA - Evaluation of Computational Methods for Reactor Safety Analysis

International Nuclear Information System (INIS)

Scheuerer, Martina

2002-01-01

There were three motivations behind the ECORA Project: - the shortcomings of 0-D system codes in the simulation of 3-D, local flow and heat transfer phenomena, - increased interest in the application of 3-D CFD software as supplement to system codes, - high safety requirements in the nuclear industry required consistent standards for the use and assessment of CFD software. The purpose of ECORA was therefore: - to establish performance criteria for the assessment of CFD software, - to establish Best Practice Guidelines for application and use of CFD software, with the following objectives: - assessment of CFD applications in reactor safety: flows in containment (PANDA experiments) and flows in primary system (UPTF experiments) - Best Practice Guidelines for reactor safety: starting point (ERCOFTAC Best Practice Guidelines), adaptation to CFD application for nuclear safety, extension to assessment of experimental data - recommendations for improvements of CFD software, - network of European 'Centres of Competence for CFD Applications in Reactor Safety'. Currently, there were twelve partners in the ECORA Project, representing nine European countries. The Project was scheduled to last until September 2004. Ms Scheuerer then described the work programme and project structure, the Best Practice Guidelines for CFD simulations, the procedures for quantifying errors, applications of Best Practice Guidelines, Best Practice Guidelines for experimental data, applications to primary system, UPTF and PANDA data. Her conclusions were the following: - the Project had led to the improvement of the quality of CFD calculations in reactor safety, through: the ECORA Best Practice Guidelines, the assessment of shortcomings and the improvement of mathematical models. - It had also led to higher acceptance of CFD in reactor safety. - The next step was the establishment of European 'Centres of Competence for CFD Applications in reactor Safety'

The Inspector General's report on Nuclear Safety and Radiation Protection 2013

International Nuclear Information System (INIS)

2014-01-01

This report, written for the Chairman of EDF, gives the Inspector General's assessment of nuclear safety and radiation protection within the EDF Group. The report is also intended for all those in the company who contribute in any way to nuclear safety and radiation protection through their day-to-day actions and decisions. It also aims to identify any early warning signs and recommend areas for improvement. It therefore focuses on difficulties and weaknesses rather than strengths and progress. It is based on information gathered and observations made during the year, both in France and the UK, whether from workers in the field, or during visits to plants and meetings with the main stakeholders: managers, staff representatives, members of the medical profession, chairmen of local information commissions in France and of Site stakeholder groups (British equivalent of the French Local Information Commissions) in the UK, and contractors. It also makes use of visits and comparisons with other international players on the nuclear scene, and of dialogue with WANO (World Association of Nuclear Operators) and the nuclear safety authorities. Content: 1 - the Inspector General's view of 2013 2 - Safety in operation: good standing of results; 3 - Management of safety priority; 4 - Occupational safety: managers mobilization is necessary in France; 5 - Radiation protection: a new dynamics to initiate; 6 - Maintenance: regaining the essentials for the great careening; 7 - Fostering occupations to improve safety; 8 - A new momentum to the EPRs; 9 - Nuclear fuel, a major contribution to safety; 10 - Research-development: a lever to anticipate; 11 - Japan: safety under reconstruction; 12 - Noteworthy operational events; 13- Appendices: Results for the nuclear fleets (EDF SA, EDF Energy; Maps of the nuclear power plants(EDF SA, EDF Energy); Key dates for the nuclear units (EDF SA, EDF Energy); Abbreviations

Practice guidelines for endoscopic ultrasound-guided celiac plexus neurolysis

DEFF Research Database (Denmark)

Wyse, Jonathan M; Battat, Robert; Sun, Siyu

2017-01-01

OBJECTIVES: The objective of guideline was to provide clear and relevant consensus statements to form a practical guideline for clinicians on the indications, optimal technique, safety and efficacy of endoscopic ultrasound guided celiac plexus neurolysis (EUS-CPN). METHODS: Six important clinical...

Practice guidelines for endoscopic ultrasound-guided celiac plexus neurolysis

NARCIS (Netherlands)

Wyse, J.M. (Jonathan M.); Battat, R. (Robert); Sun, S. (Siyu); A. Saftoiu (Adrian); Siddiqui, A.A. (Ali A.); Leong, A.T. (Ang Tiing); Arias, B.L.A. (Brenda Lucia Arturo); Fabbri, C. (Carlo); Adler, D.G. (Douglas G.); Santo, E. (Erwin); Kalaitzakis, E. (Evangelos); Artifon, E. (Everson); Mishra, G. (Girish); Okasha, H.H. (Hussein Hassan); J.-W. Poley (Jan-Werner); Guo, J. (Jintao); Vila, J.J. (Juan J.); Lee, L.S. (Linda S.); Sharma, M. (Malay); Bhutani, M.S. (Manoop S.); M. Giovannini (Marcello); Kitano, M. (Masayuki); Eloubeidi, M.A. (Mohamad Ali); Khashab, M.A. (Mouen A.); Nguyen, N.Q. (Nam Q.); Saxena, P. (Payal); Vilmann, P. (Peter); Fusaroli, P. (Pietro); Garg, P.K. (Pramod Kumar); Ho, S. (Sammy); Mukai, S. (Shuntaro); Carrara, S. (Silvia); Sridhar, S. (Subbaramiah); S. Lakhtakia (S.); Rana, S.S. (Surinder S.); Dhir, V. (Vinay); Sahai, A.V. (Anand V.)

2017-01-01

textabstractObjectives: The objective of guideline was to provide clear and relevant consensus statements to form a practical guideline for clinicians on the indications, optimal technique, safety and efficacy of endoscopic ultrasound guided celiac plexus neurolysis (EUS-CPN). Methods: Six important

Elements of safety and non proliferation

International Nuclear Information System (INIS)

Jalouneix, Jean; Aurelle, Jacques; Funk, Pierre; Ladsous, David; Bon Nguyen, Romuald; Goue, Georges; Lefevre, Odile

2015-01-01

This book on nuclear safety and non proliferation is based on knowledge and expertise of the IRSN. The first chapter addresses the safety of nuclear materials, of their installations and of their transportations. It proposes some contextual elements, presents the general guidelines of the French nuclear safety arrangement, the approach to take risks into account, the involved governmental and public bodies, the legal framework, and the protection and control arrangement (in terms of planning of safety-related activities, in terms of operator obligations, in terms of exercises and management crisis). The second part addresses the safety of radioactive sources: context (peculiarity, losses and thefts), international framework (source categories, Euratom directive), and the French organisation. The third chapter addresses nuclear non proliferation: historical background (creation and role of the IAEA and of the EAEC, definitions), principle of statements, inspection process, and French organisation (legal framework, governmental bodies, the IRSN). The last chapter addresses the issue of chemical non proliferation: historical background, international context (Convention on chemical weapons, organisation for their ban), and the French organisation

Development of human factors design review guidelines(III)

Energy Technology Data Exchange (ETDEWEB)

Lee, Jung Woon; Oh, In Suk; Suh, Sang Moon; Lee, Hyun Chul [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1999-02-15

The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: '25, human factors engineering program review model' and '26, review criteria for human factors aspects of advanced controls and instrumentation', which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and reviewing the reference documents NUREG--0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm system. Then we will update the guidelines by reviewing the literature related to alarm design published after 1994.

Development of human factors design review guidelines(III)

International Nuclear Information System (INIS)

Lee, Jung Woon; Oh, In Suk; Suh, Sang Moon; Lee, Hyun Chul

1999-02-01

The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: '25, human factors engineering program review model' and '26, review criteria for human factors aspects of advanced controls and instrumentation', which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and reviewing the reference documents NUREG--0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm system. Then we will update the guidelines by reviewing the literature related to alarm design published after 1994

Development of human factors design review guidelines(II)

International Nuclear Information System (INIS)

Lee, Jung Woon; Oh, In Suk; Suh, Sang Moon; Lee, Hyun Chul

1998-06-01

The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: '25, human factors engineering program review model' and '26, review criteria for human factors aspects of advanced controls and instrumentation', which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and reviewing the reference documents NUREG--0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm system. Then we will update the guidelines by reviewing the literature related to alarm design published after 1994

Development of human factors design review guidelines(III)

Energy Technology Data Exchange (ETDEWEB)

Lee, Jung Woon; Oh, In Suk; Suh, Sang Moon; Lee, Hyun Chul [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1999-02-15

The objective of this study is to develop human factors engineering program review guidelines and alarm system review guidelines in order to resolve the two major technical issues: '25, human factors engineering program review model' and '26, review criteria for human factors aspects of advanced controls and instrumentation', which are related to the development of human factors safety regulation guides being performed by KINS. For the development of human factors program review guidelines, we made a Korean version of NUREG-0711 and added our comments by considering Korean regulatory situation and reviewing the reference documents NUREG--0711, additional comments, and selected portion of the reference documents for the developer of safety regulation guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guides in KINS to see the contents comparatively at a glance and use them easily. For the development of alarm system review guidelines, we made a Korean version of NUREG/CR-6105, which was published by NRC in 1994 as a guideline document for the human factors review of alarm system. Then we will update the guidelines by reviewing the literature related to alarm design published after 1994.

Safety class methodology

International Nuclear Information System (INIS)

Donner, E.B.; Low, J.M.; Lux, C.R.

1992-01-01

DOE Order 6430.1A, General Design Criteria (GDC), requires that DOE facilities be evaluated with respect to ''safety class items.'' Although the GDC defines safety class items, it does not provide a methodology for selecting safety class items. The methodology described in this paper was developed to assure that Safety Class Items at the Savannah River Site (SRS) are selected in a consistent and technically defensible manner. Safety class items are those in the highest of four categories determined to be of special importance to nuclear safety and, merit appropriately higher-quality design, fabrication, and industrial test standards and codes. The identification of safety class items is approached using a cascading strategy that begins at the 'safety function' level (i.e., a cooling function, ventilation function, etc.) and proceeds down to the system, component, or structure level. Thus, the items that are required to support a safety function are SCls. The basic steps in this procedure apply to the determination of SCls for both new project activities, and for operating facilities. The GDC lists six characteristics of SCls to be considered as a starting point for safety item classification. They are as follows: 1. Those items whose failure would produce exposure consequences that would exceed the guidelines in Section 1300-1.4, ''Guidance on Limiting Exposure of the Public,'' at the site boundary or nearest point of public access 2. Those items required to maintain operating parameters within the safety limits specified in the Operational Safety Requirements during normal operations and anticipated operational occurrences. 3. Those items required for nuclear criticality safety. 4. Those items required to monitor the release of radioactive material to the environment during and after a Design Basis Accident. Those items required to achieve, and maintain the facility in a safe shutdown condition 6. Those items that control Safety Class Item listed above

Test and evaluation on safety relating to biotechnology; Biotechnology ni kansuru anzensei no shiken to hyoka

Energy Technology Data Exchange (ETDEWEB)

Okada, M. [Bio-Oriented Technology Research Advancement Inst., Saitama (Japan)

1996-09-05

This paper describes the current status and how works are being carried out on safety tests and evaluation of gene recombinants in plants and microorganisms. In the field of plants, Flavr Savr tomato which has been improved in fully ripe fruit distribution and keeping quality was commercialized as the world`s first recombinant food in May 1994 by Calgene, Inc. of America. Other vegetables, such as soybean, corn, potato, and pumpkin have been completed of all items of safety evaluation, and are approaching the commercialization phase. The safety evaluation system for living organisms created by using recombinant DNA technologies has been established internationally with regard to its general framework and contents based on accumulated knowledeges and experiences as a result of utilization of over twenty years. Industrial utilization guidelines for recombinants in Japan have been established in correspondence with the OECD recommendation in 1986. Experiments to verify recombinants to be safe in environment, and cultivation of the recombinants for utilization are performed based on the experimental guidelines and utilization guidelines. 15 refs., 1 fig., 5 tabs.

Current safety practices in nano-research laboratories in China.

Science.gov (United States)

Zhang, Can; Zhang, Jing; Wang, Guoyu

2014-06-01

China has become a key player in the global nanotechnology field, however, no surveys have specifically examined safety practices in the Chinese nano-laboratories in depth. This study reports results of a survey of 300 professionals who work in research laboratories that handle nanomaterials in China. We recruited participants at three major nano-research laboratories (which carry out research in diverse fields such as chemistry, material science, and biology) and the nano-chemistry session of the national meeting of the Chinese Chemical Society. Results show that almost all nano-research laboratories surveyed had general safety regulations, whereas less than one third of respondents reported having nanospecific safety rules. General safety measures were in place in most surveyed nano-research laboratories, while nanospecific protective measures existed or were implemented less frequently. Several factors reported from the scientific literature including nanotoxicology knowledge gaps, technical limitations on estimating nano-exposure, and the lack of nano-occupational safety legislation may contribute to the current state of affairs. With these factors in mind and embracing the precautionary principle, we suggest strengthening or providing nanosafety training (including raising risk awareness) and establishing nanosafety guidelines in China, to better protect personnel in the nano-workplace.

Development application guidelines : Newfoundland offshore area

Energy Technology Data Exchange (ETDEWEB)

NONE

1988-12-01

The Canada-Newfoundland Offshore Petroleum Board has created a set of guidelines which describe the information needed by the Board to process a development application by a proponent of an offshore hydrocarbon development project. The guidelines also describe the review process that will be followed in considering a proponent`s application. Proponents must also refer to the Canada-Newfoundland Atlantic Accord Implementation Act and the Canada-Newfoundland Atlantic Accord Implementation (Newfoundland) Act. These guidelines also describe the requirements for the Canada-Newfoundland benefits plan, the environmental impact statement, the socio-economic impact statement, the safety plan, and the environmental protection plan.

Health protection guidelines for electromagnetic field exposures

International Nuclear Information System (INIS)

Taki, Masao

1999-01-01

In order to protect human health from excessive exposure to electromagnetic fields safety guidelines have been established by national and international organizations. The International Commission on Nonionization Radiation Protection is one of these organizations, whose guidelines are briefly regarded as typical. The activities on this issue in various countries are reviewed. Recent situations and the problems still unsolved are also discussed. (author)

Nuclear safety in France: Extracts from 'Revue Generale Nucleaire'

International Nuclear Information System (INIS)

1979-07-01

Translations of 3 articles are included in this report. The first covers briefly the tasks and organisation of the Institute of Nuclear Protection and Safety (IPSN) in France. In the second article the principles of cost effectiveness are described and the applications of the general methodology to radiation protection is outlined. A study by the US Environmental Protection Agency is summarised. Methods for risk estimation in nuclear energy are presented in the final article

10 CFR 960.4-2 - Technical guidelines.

Science.gov (United States)

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Technical guidelines. 960.4-2 Section 960.4-2 Energy DEPARTMENT OF ENERGY GENERAL GUIDELINES FOR THE PRELIMINARY SCREENING OF POTENTIAL SITES FOR A NUCLEAR WASTE REPOSITORY Postclosure Guidelines § 960.4-2 Technical guidelines. The technical guidelines in this subpart...

Adherence to COPD guidelines in general practice: impact of an educational programme delivered on location in Danish general practices.

Science.gov (United States)

Ulrik, Charlotte Suppli; Sørensen, Tina Brandt; Højmark, Torben Brunse; Olsen, Kim Rose; Vedsted, Peter

2013-03-01

The general practitioner (GP) is often the first healthcare contact for patients with chronic obstructive pulmonary disease (COPD). To determine whether participating in a standardised educational programme delivered in the GP's own practice is associated with adherence to COPD guidelines. A nationwide register-based observational before and after study was undertaken with a control group of propensity-matched practices (follow-up period 6 months). COPD was defined as age 40+ years and at least two prescriptions for inhaled medication. The educational programme consisted of a 3-hr teaching lesson with a respiratory specialist and five visits by a representative from the sponsoring pharmaceutical company focusing on assessment and management of patients including written algorithms. A one-to-one propensity-matched control group of practices was selected. Register data were used to compare the rate of spirometry testing, preventive consultations, and influenza vaccinations provided to COPD patients and the rate of spirometry testing in non-COPD individuals, assumed to reflect diagnostic activity. Data for 102 participating GP practices were analysed. Participating clinics had a significant increase in preventive consultations and influenza vaccinations (peducation of GPs and their staff delivered in the GPs' own practices may improve adherence to COPD guidelines, not least for clinics with a high potential for improvement.

[The practice guideline 'Vaginal discharge' (first revision) from the Dutch College of General Practitioners; a response from the perspective of gynaecology].

Science.gov (United States)

Hogewoning, C J A; Ottervanger, H P; Adriaanse, A H; Trum, J W

2007-06-16

The Dutch College of General Practitioners (NHG) revised their practice guideline on vaginal discharge. From a gynaecological point of view, relocation of cervix problems from this guideline to the NHG guideline 'The STD consultation' is not practical. Moreover, the role of simple, but effective diagnosis with a microscope in the primary-care setting cannot be overemphasized. The reluctance to oral treatment is rather inopportune, because once-only ingestion has the advantage of promoting compliance. As physical examination is not always necessary in a recurrent Candida infection, treatment performed by the patient with imidazole compounds is a possibility that does not always result in abuse or increased resistance.

10 CFR 960.5-2 - Technical guidelines.

Science.gov (United States)

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Technical guidelines. 960.5-2 Section 960.5-2 Energy DEPARTMENT OF ENERGY GENERAL GUIDELINES FOR THE PRELIMINARY SCREENING OF POTENTIAL SITES FOR A NUCLEAR WASTE REPOSITORY Preclosure Guidelines § 960.5-2 Technical guidelines. The technical guidelines in this subpart set...

Safety assessment of research reactors and preparation of the safety analysis report

International Nuclear Information System (INIS)

1994-01-01

This Safety Guide presents guidelines, approved by international consensus, for the preparation, review and assessment of safety documentation for research reactors such as the Safety Analysis Report. While the Guide is most applicable to research reactors in the design and construction stage, it is also recommended for use during relicensing or reassessment of existing reactors

MORT: a safety management program developed for ERDA

International Nuclear Information System (INIS)

1977-03-01

ERDA's System Safety Development Center (SSDC) is located at the Idaho National Engineering Laboratory under the EG and G Idaho, Inc., contract administered by the Idaho Operations Office. The SSDC performs a variety of tasks for ERDA's Division of Safety, Standards, and Compliance, for the purpose of improvement and application of safety program elements. Primary among these tasks are development and demonstration of new methodologies, training, consultation, and technical writing. This information package (ERDA 77-38) is an example of the later task, aimed at communicating to a general audience the nature and purpose of major features of the Management Oversight and Risk Tree (MORT) program. The SSDC also originates a guideline series of monographs (the ERDA 76-45 series) for individuals who desire more specific explanations of the MORT program

Report of the tunnel safety working group

International Nuclear Information System (INIS)

Gannon, J.

1991-04-01

On 18 February 1991 the Project Manager formed a working group to address the safety guidelines and requirements for the underground facilities during the period of accelerator construction, installation, and commissioning. The following report summarizes the research and discussions conducted by the group and the recommended guidelines for safety during this phase of the project

Conformity to the surviving sepsis campaign international guidelines among physicians in a general intensive care unit in Nairobi.

Science.gov (United States)

Mung'ayi, V; Karuga, R

2010-08-01

There are emerging therapies for managing septic critically-ill patients. There is little data from the developing world on their usage. To determine the conformity rate for resuscitation and management bundles for septic patients amongst physicians in a general intensive care unit. Cross sectional observational study. The general intensive care unit, Aga Khan University Hospital,Nairobi. Admitting physicians from all specialties in the general intensive care unit. The physicians had high conformity rates of 92% and 96% for the fluid resuscitation and use of va so pressors respectively for the initial resuscitation bundle. They had moderate conformity rates for blood cultures prior to administering antibiotics (57%) and administration of antibiotics within first hour of recognition of septic shock (54%). There was high conformity rate to the glucose control policy (81%), use of protective lung strategy in acute lung injury/Acute respiratory distress syndrome, venous thromboembolism prophylaxis (100%) and stress ulcer prophylaxis (100%) in the management bundle. Conformity was moderate for use of sedation, analgesia and muscle relaxant policy (69%), continuous renal replacement therapies (54%) and low for steroid policy (35%), administration ofdrotrecogin alfa (0%) and selective digestive decontamination (15%). There is varying conformity to the international sepsis guidelines among physicians caring for patients in our general ICU. Since increased conformity would improve survival and reduce morbidity, there is need for sustained education and guideline based performance improvement.

Interconnection Guidelines

Science.gov (United States)

The Interconnection Guidelines provide general guidance on the steps involved with connecting biogas recovery systems to the utility electrical power grid. Interconnection best practices including time and cost estimates are discussed.

Whitebark pine planting guidelines

Science.gov (United States)

Ward McCaughey; Glenda L. Scott; Kay L. Izlar

2009-01-01

This article incorporates new information into previous whitebark pine guidelines for planting prescriptions. Earlier 2006 guidelines were developed based on review of general literature, research studies, field observations, and standard US Forest Service survival surveys of high-elevation whitebark pine plantations. A recent study of biotic and abiotic factors...

40 CFR 766.12 - Testing guidelines.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 30 2010-07-01 2010-07-01 false Testing guidelines. 766.12 Section 766... DIBENZO-PARA-DIOXINS/DIBENZOFURANS General Provisions § 766.12 Testing guidelines. Analytical test methods must be developed using methods equivalent to those described or reviewed in Guidelines for the...

OPG waterways public safety program

Energy Technology Data Exchange (ETDEWEB)

Bennett, T [Ontario Power Generation Inc., Niagara Falls, ON (Canada)

2009-07-01

Ontario Power Generation (OPG) has 64 hydroelectric generating stations, 241 dams, and 109 dams in Ontario's registry with the International Commission on Large Dams (ICOLD). In 1986, it launched a formal dam safety program. This presentation addressed the importance of public safety around dams. The safety measures are timely because of increasing public interaction around dams; the public's unawareness of hazards; public interest in extreme sports; easier access by recreational vehicles; the perceived right of public to access sites; and the remote operation of hydroelectric stations. The presentation outlined the OPG managed system approach, with particular reference to governance; principles; standards and procedures; and aspects of implementation. Specific guidelines and governing documents for public safety around dams were identified, including guidelines for public safety of waterways; booms and buoys; audible warning devices and lights; public safety signage; fencing and barricades; and risk assessment for public safety around waterways. The presentation concluded with a discussion of audits and management reviews to determine if safety objectives and targets have been met. figs.

Heat exchanger performance monitoring guidelines

International Nuclear Information System (INIS)

Stambaugh, N.; Closser, W. Jr.; Mollerus, F.J.

1991-12-01

Fouling can occur in many heat exchanger applications in a way that impedes heat transfer and fluid flow and reduces the heat transfer or performance capability of the heat exchanger. Fouling may be significant for heat exchanger surfaces and flow paths in contact with plant service water. This report presents guidelines for performance monitoring of heat exchangers subject to fouling. Guidelines include selection of heat exchangers to monitor based on system function, safety function and system configuration. Five monitoring methods are discussed: the heat transfer, temperature monitoring, temperature effectiveness, delta P and periodic maintenance methods. Guidelines are included for selecting the appropriate monitoring methods and for implementing the selected methods. The report also includes a bibliography, example calculations, and technical notes applicable to the heat transfer method

Nuclear Installation Safety: General Observations and Trends from IAEA Peer Reviews

International Nuclear Information System (INIS)

Rzentkowski, G.

2016-01-01

The Safety Review Services (SRSs) for nuclear installations address the needs of Member States at all stages of installations’ lifecycle. SRSs are based on the IAEA Safety Standards and are provided on Member States’ request to peer review national regulatory frameworks and safety provisions for nuclear installations. They result in recommendations and suggestions to improve national regulations and operational safety, and serve to exert peer pressure to ensure that that every Member State with nuclear installations recognizes its safety responsibility and the need to comply with the IAEA Safety Standards. This presentation provides an overview of SRSs for Nuclear Installations, including their structure and main subject areas. The presentation also summarizes general findings and trends which clearly demonstrate that there is continuous improvement in regulation of nuclear installations and in safety of their operation. Nevertheless, there is the need to further enhance the efficiency and effectiveness of SRSs through review of the overall governance model and service delivery to better serve the needs of Member States. The presentation points out some areas of improvements which have already been implemented or are being considered for implementation. Just as important, SRSs are conducted by teams of experts from around the world to strengthening international cooperation, ensure diversity and impartiality, and improve the overall quality of the safety review being conducted. The review team members are also provided with the opportunity for mutual learning and sharing good practices among themselves and with the Member State undergoing the review. As a result, SRAs play an important role in a quest to harmonize regulatory requirements and approaches globally. (author)

Impact of a clinical guideline for prescribing antibiotics to inpatients reporting penicillin or cephalosporin allergy.

Science.gov (United States)

Blumenthal, Kimberly G; Shenoy, Erica S; Varughese, Christy A; Hurwitz, Shelley; Hooper, David C; Banerji, Aleena

2015-10-01

Self-reported penicillin allergy infrequently reflects an inability to tolerate penicillins. Inpatients reporting penicillin allergy receive alternative antibiotics that might be broader spectrum, more toxic, or less effective. To develop and assess a clinical guideline for the general inpatient provider that directs taking a history and prescribing antibiotics for patients with penicillin or cephalosporin allergy. A guideline was implemented to assist providers with assessing allergy history and prescribing antibiotics for patients with reported penicillin or cephalosporin allergy. The guideline used a standard 2-step graded challenge or test dose. A quasi-experimental study was performed to assess safety, feasibility, and impact on antibiotic use by comparing treatment 21 months before guideline implementation with 12 months after guideline implementation. Significantly more test doses to β-lactam antibiotics were performed monthly after vs before guideline implementation (median 14.5, interquartile range 13-16.25, vs 2, interquartile range 1-3.25, P  .5) between periods. Guideline-driven test doses decreased alternative antimicrobial therapy after the test dose, including vancomycin (68.3% vs 37.2%, P penicillin or cephalosporin allergy was associated with an almost 7-fold increase in the number of test doses to β-lactams without increased adverse drug reactions. Patients assessed with guideline-driven test doses were observed to have significantly decreased alternative antibiotic exposure. Copyright © 2015 American College of Allergy, Asthma & Immunology. Published by Elsevier Inc. All rights reserved.

Relationship between general safety requirements and safety culture in the improvement of safe operation of I.N.R. TRIGA reactor facilities

International Nuclear Information System (INIS)

Ciocanescu, M.; Preda, M.; Chiritescu, M.; Dumitru, M.

1996-01-01

Acquiring of the basic principles of ''safety culture'' by a large number of profesionals in the nuclear field drew the attention of the decision factors in the INR managerial structure, who decided to promote certain practical actions at each level in order to improve nuclear safety. Starting from the ''Republican Standards for Nuclear Safety'' issued by CSEN in 1975, where general safety criteria are defined for nuclear reactors and NPPs, the specialists at the TRIGA reactor originated and implemented a coherent and secure system to ensure nuclear safety over all steps of nuclear activities: research, conception, execution, commissioning and operation. This system has been continuosly corrected so that now it is completely integrated in a modern safety system. The paper presents the way in which a modern system for nuclear safety at the TRIGA reactor has been implemented and developed, in accordance to specific criteria and requirements imposed by related National Regulations and with the principles of safety culture. Starting from the definition of specific responsabilities, there are presented the internal stipulations and practical actions at all levels in order to enhance nuclear safety. (orig.)

AREVA General Inspectorate Annual Report 2013 - Status of safety in nuclear facilities

International Nuclear Information System (INIS)

Oursel, Luc; Riou, Jean

2014-06-01

This annual report by AREVA's General Inspectorate deals with the status of nuclear safety and radiation protection in the group's facilities and operations over the course of 2013. Based on the findings made during implementation of the annual inspection program, this annual report also includes the results of the analysis of significant events and the observations and assessments of specialists in the Safety Health Security Sustainable Development Department (SHSSDD), supplemented by regular interaction with the safety regulators, different government agencies, stakeholders and other nuclear operators. Additionally, this report presents the action plans put into motion and the directions taken for continuous improvement in risk prevention for operations conducted in France and internationally. In 2013, the level of safety in the group's nuclear facilities and operations remained satisfactory, although improvements are necessary in some domains. This report is based on established indicators, analyses of reported events, responses to commitments made to the regulators, and the results of different improvement actions reported on in the inspected and supported entities. In 2013, no level 2 event on the International Nuclear and Radiological Event Scale (INES) was reported, the bottom-up reporting of weak signals was confirmed, dose levels were low and there were no radiological impacts on the environment. The General Inspectorate conducted 45 inspections in 30 of the group's entities in 2013. Of these, 10 concerned sites outside France and 7 were conducted following events or particular situations. These inspections gave rise to 176 recommendations, which the inspected entities have translated into action plans. Verification of these different action plans according to planned procedures and announced schedules gave rise to 16 follow-up inspections. The major lessons learned from these inspections relate to project management, facility compliance and operational

The healing arts radiation protection guidelines

International Nuclear Information System (INIS)

Yaffe, M.

1987-06-01

The objective of these guidelines is to help the health professional render the risks associated with diagnostic radiation as low as reasonably achievable. The guidelines contain advice and recommendations, but no mandatory requirements. They assist radiation protection officers in establishing and maintaining a Quality Assurance Program and in carrying out other duties required by the Healing Arts Radiation Protection Act; assist staff to comply with the X-ray Safety Code in a way that will raise the standards of x-ray diagnosis and patient safety; address the relationship between the radiation exposure of the patient and the quality of the image; address the problem of protecting the patient in x-ray examinations; summarize x-ray safety problems from the point of view of the operator and other staff; indicate what remedial measures can be taken; define the quality assurance needs of x-ray users; and encourage the users of x-rays for diagnostic purposes to go beyond the scope of the Act and comply with the ALARA principle

technical guidelines for the design and construction of the next generation of nuclear power plants with pressurized water reactors

International Nuclear Information System (INIS)

2009-01-01

These technical guidelines present the opinion of the French 'Groupe Permanent charge des Reacteurs nucleaires' (GPR) concerning the safety philosophy and approach as well as the general safety requirements to be applied for the design and construction of the next generation of nuclear power plants of the PWR (pressurized water reactor) type, assuming the construction of the first units of this generation would start at the beginning of the 21. century. These technical guidelines are based on common work of the French Institut de Protection et de Surete Nucleaire (IPSN) and of the German Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS). Moreover, these technical guidelines were extensively discussed with members of the German Reaktor Sicherheitskommission (RSK) until the end of 1998 and further with German experts. The context of these technical guidelines must be clearly understood. Faced with the current situation of nuclear energy in the world, the various nuclear steam supply system designers are developing new products, all of them claiming their intention of obtaining a higher safety level, by various ways. GPR believes that, for the operation of a new series of nuclear power plants at the beginning of the next century, the adequate way is to derive the design of these plants in an 'evolutionary' way from the design of existing plants, taking into account the operating experience and the in-depth studies conducted for such plants. Nevertheless, introduction of innovative features must also be considered in the frame of the design of the new generation of plants, especially in preventing and mitigating severe accidents. GPR underlines here that a significant improvement of the safety of the next generation of nuclear power plants at the design stage is necessary, compared to existing plants. If the search for improvement is a permanent concern in the field of safety, the necessity of a significant step at the design stage clearly derives from better

The Inspector General's report on Nuclear Safety and Radiation Protection 2016

International Nuclear Information System (INIS)

2017-01-01

This report, written for the Chairman of EDF, gives the Inspector General's assessment of nuclear safety and radiation protection within the EDF Group. The report is also intended for all those in the company who contribute in any way to nuclear safety and radiation protection through their day-to-day actions and decisions. It also aims to identify any early warning signs and recommend areas for improvement. It therefore focuses on difficulties and weaknesses rather than strengths and progress. It is based on information gathered and observations made during the year, both in France and the UK, whether from workers in the field, or during visits to plants and meetings with the main stakeholders: managers, staff representatives, members of the medical profession, chairmen of local information commissions in France and of Site stakeholder groups (British equivalent of the French Local Information Commissions) in the UK, and contractors. It also makes use of visits and comparisons with other international players on the nuclear scene, and of dialogue with WANO (World Association of Nuclear Operators) and the nuclear safety authorities. Content: 1 - the Inspector General's view of 2016; 2 - Operational safety: encouraging results; 3 - High-profile focus on safety; 4 - Risk prevention: effort must be intensified; 5 - Team skills and commitment; 6 - Simplification; 7 - Maintenance quality; 8 - Nuclear fuel; 9 - New build; 10 - Protection against site security threats; 11 - Appendices

10 CFR 960.5-1 - System guidelines.

Science.gov (United States)

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false System guidelines. 960.5-1 Section 960.5-1 Energy DEPARTMENT OF ENERGY GENERAL GUIDELINES FOR THE PRELIMINARY SCREENING OF POTENTIAL SITES FOR A NUCLEAR WASTE REPOSITORY Preclosure Guidelines § 960.5-1 System guidelines. (a) Qualifying conditions—(1) Preclosure...

Human Factors Engineering Guidelines for Overhead Cranes

Science.gov (United States)

Chandler, Faith; Delgado, H. (Technical Monitor)

2001-01-01

This guideline provides standards for overhead crane cabs that can be applied to the design and modification of crane cabs to reduce the potential for human error due to design. This guideline serves as an aid during the development of a specification for purchases of cranes or for an engineering support request for crane design modification. It aids human factors engineers in evaluating existing cranes during accident investigations or safety reviews.

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

International Nuclear Information System (INIS)

2017-10-01

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

Public announcement of guidelines for the packing and safe stowing of cargo in freight containers and vehicles for ocean transport (Container Stowage Guidelines)

International Nuclear Information System (INIS)

1987-01-01

The IMO and ILO guidelines are given, which help to meet the requirements of the Maritime Safety Ordinance and the Ordinance on Ocean Transport of Dangerous Goods. The guidelines explain the principles of safe packing and stowing of cargo in freight containers and vehicles for ocean transports. Further information and practical hints are given in international publications referred to in the annex. The guidelines are also meant for training purposes. (orig./HSCH) [de

Reliability Based Calibration of Fatigue Design Guidelines for Ship Structures

DEFF Research Database (Denmark)

Folsø, Rasmus; Otto, S.; Parmentier, G.

2002-01-01

A simple reliability based framework is applied to calibrate a new set of fatigue design guidelines. This new guideline considers two different approaches for the assessment of both loads, stresses and local stress raising effects, and partial safety factors must be given for any combination...

The design of the SAFE or SORRY? study: a cluster randomised trial on the development and testing of an evidence based inpatient safety program for the prevention of adverse events

Directory of Open Access Journals (Sweden)

Koopmans Raymond TCM

2009-04-01

Full Text Available Abstract Background Patients in hospitals and nursing homes are at risk of the development of, often preventable, adverse events (AEs, which threaten patient safety. Guidelines for prevention of many types of AEs are available, however, compliance with these guidelines appears to be lacking. Besides general barriers that inhibit implementation, this non-compliance is associated with the large number of guidelines competing for attention. As implementation of a guideline is time-consuming, it is difficult for organisations to implement all available guidelines. Another problem is lack of feedback about performance using quality indicators of guideline based care and lack of a recognisable, unambiguous system for implementation. A program that allows organisations to implement multiple guidelines simultaneously may facilitate guideline use and thus improve patient safety. The aim of this study is to develop and test such an integral patient safety program that addresses several AEs simultaneously in hospitals and nursing homes. This paper reports the design of this study. Methods and design The patient safety program addresses three AEs: pressure ulcers, falls and urinary tract infections. It consists of bundles and outcome and process indicators based on the existing evidence based guidelines. In addition it includes a multifaceted tailored implementation strategy: education, patient involvement, and a computerized registration and feedback system. The patient safety program was tested in a cluster randomised trial on ten hospital wards and ten nursing home wards. The baseline period was three months followed by the implementation of the patient safety program for fourteen months. Subsequently the follow-up period was nine months. Primary outcome measure was the incidence of AEs on every ward. Secondary outcome measures were the utilization of preventive interventions and the knowledge of nurses regarding the three topics. Randomisation took

GENERAL CONSIDERATIONS ON REGULATIONS AND SAFETY REQUIREMENTS FOR QUADRICYCLES

Directory of Open Access Journals (Sweden)

Ana Pavlovic

2015-12-01

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

Occupational radiation protection. Safety guide

International Nuclear Information System (INIS)

2002-01-01

Occupational exposure to ionizing radiation can occur in a range of industries, medical institutions, educational and research establishments and nuclear fuel cycle facilities. Adequate radiation protection of workers is essential for the safe and acceptable use of radiation, radioactive materials and nuclear energy. In 1996, the Agency published Safety Fundamentals on Radiation Protection and the Safety of Radiation Sources (IAEA Safety Series No. 120) and International Basic Safety Standards for Protection against Ionizing, Radiation and for the Safety of Radiation Sources (IAEA Safety Series No. 115), both of which were jointly sponsored by the Food and Agriculture Organization of the United Nations, the IAEA, the International Labour Organisation, the OECD Nuclear Energy Agency, the Pan American Health Organization and the World Health Organization. These publications set out, respectively, the objectives and principles for radiation safety and the requirements to be met to apply the principles and to achieve the objectives. The establishment of safety requirements and guidance on occupational radiation protection is a major component of the support for radiation safety provided by the IAEA to its Member States. The objective of the IAEA's occupational protection programme is to promote an internationally harmonized approach to the optimization of occupational radiation protection, through the development and application of guidelines for restricting radiation exposures and applying current radiation protection techniques in the workplace. Guidance on meeting the requirements of the Basic Safety Standards for occupational protection is provided in three interrelated Safety Guides, one giving general guidance on the development of occupational radiation protection programmes and two giving more detailed guidance on the monitoring and assessment of workers' exposure due to external radiation sources and from intakes of radionuclides, respectively. These Safety

Occupational radiation protection. Safety guide

International Nuclear Information System (INIS)

2006-01-01

Occupational exposure to ionizing radiation can occur in a range of industries, medical institutions, educational and research establishments and nuclear fuel cycle facilities. Adequate radiation protection of workers is essential for the safe and acceptable use of radiation, radioactive materials and nuclear energy. In 1996, the Agency published Safety Fundamentals on Radiation Protection and the Safety of Radiation Sources (IAEA Safety Series No. 120) and International Basic Safety Standards for Protection against Ionizing, Radiation and for the Safety of Radiation Sources (IAEA Safety Series No. 115), both of which were jointly sponsored by the Food and Agriculture Organization of the United Nations, the IAEA, the International Labour Organisation, the OECD Nuclear Energy Agency, the Pan American Health Organization and the World Health Organization. These publications set out, respectively, the objectives and principles for radiation safety and the requirements to be met to apply the principles and to achieve the objectives. The establishment of safety requirements and guidance on occupational radiation protection is a major component of the support for radiation safety provided by the IAEA to its Member States. The objective of the IAEA's occupational protection programme is to promote an internationally harmonized approach to the optimization of occupational radiation protection, through the development and application of guidelines for restricting radiation exposures and applying current radiation protection techniques in the workplace. Guidance on meeting the requirements of the Basic Safety Standards for occupational protection is provided in three interrelated Safety Guides, one giving general guidance on the development of occupational radiation protection programmes and two giving more detailed guidance on the monitoring and assessment of workers' exposure due to external radiation sources and from intakes of radionuclides, respectively. These Safety

Occupational radiation protection. Safety guide

International Nuclear Information System (INIS)

1999-01-01

Occupational exposure to ionizing radiation can occur in a range of industries, medical institutions, educational and research establishments and nuclear fuel cycle facilities. Adequate radiation protection of workers is essential for the safe and acceptable use of radiation, radioactive materials and nuclear energy. In 1996, the Agency published Safety Fundamentals on Radiation Protection and the Safety of Radiation Sources (IAEA Safety Series No. 120) and International Basic Safety Standards for Protection against Ionizing, Radiation and for the Safety of Radiation Sources (IAEA Safety Series No. 115), both of which were jointly sponsored by the Food and Agriculture Organization of the United Nations, the IAEA, the International Labour Organisation, the OECD Nuclear Energy Agency, the Pan American Health Organization and the World Health Organization. These publications set out, respectively, the objectives and principles for radiation safety and the requirements to be met to apply the principles and to achieve the objectives. The establishment of safety requirements and guidance on occupational radiation protection is a major component of the support for radiation safety provided by the IAEA to its Member States. The objective of the IAEA's occupational protection programme is to promote an internationally harmonized approach to the optimization of occupational radiation protection, through the development and application of guidelines for restricting radiation exposures and applying current radiation protection techniques in the workplace. Guidance on meeting the requirements of the Basic Safety Standards for occupational protection is provided in three interrelated Safety Guides, one giving general guidance on the development of occupational radiation protection programmes and two giving more detailed guidance on the monitoring and assessment of workers' exposure due to external radiation sources and from intakes of radionuclides, respectively. These Safety

Occupational radiation protection. Safety guide

International Nuclear Information System (INIS)

2004-01-01

Occupational exposure to ionizing radiation can occur in a range of industries, medical institutions, educational and research establishments and nuclear fuel cycle facilities. Adequate radiation protection of workers is essential for the safe and acceptable use of radiation, radioactive materials and nuclear energy. In 1996, the Agency published Safety Fundamentals on Radiation Protection and the Safety of Radiation Sources (IAEA Safety Series No. 120) and International Basic Safety Standards for Protection against Ionizing, Radiation and for the Safety of Radiation Sources (IAEA Safety Series No. 115), both of which were jointly sponsored by the Food and Agriculture Organization of the United Nations, the IAEA, the International Labour Organisation, the OECD Nuclear Energy Agency, the Pan American Health Organization and the World Health Organization. These publications set out, respectively, the objectives and principles for radiation safety and the requirements to be met to apply the principles and to achieve the objectives. The establishment of safety requirements and guidance on occupational radiation protection is a major component of the support for radiation safety provided by the IAEA to its Member States. The objective of the IAEA's occupational protection programme is to promote an internationally harmonized approach to the optimization of occupational radiation protection, through the development and application of guidelines for restricting radiation exposures and applying current radiation protection techniques in the workplace. Guidance on meeting the requirements of the Basic Safety Standards for occupational protection is provided in three interrelated Safety Guides, one giving general guidance on the development of occupational radiation protection programmes and two giving more detailed guidance on the monitoring and assessment of workers' exposure due to external radiation sources and from intakes of radionuclides, respectively. These Safety

The Erasmus programme for postgraduate education in orthodontics in Europe: an update of the guidelines.

Science.gov (United States)

Huggare, J; Derringer, K A; Eliades, T; Filleul, M P; Kiliaridis, S; Kuijpers-Jagtman, A; Martina, R; Pirttiniemi, P; Ruf, S; Schwestka-Polly, R

2014-06-01

In 1989, the ERASMUS Bureau of the European Cultural Foundation of the Commission of the European Communities funded the development of a new 3-year curriculum for postgraduate education in orthodontics. The new curriculum was created by directors for orthodontic education representing 15 European countries. The curriculum entitled 'Three years Postgraduate Programme in Orthodontics: the Final Report of the Erasmus Project' was published 1992. In 2012, the 'Network of Erasmus Based European Orthodontic Programmes' developed and approved an updated version of the guidelines. The core programme consists of eight sections: general biological and medical subjects; basic orthodontic subjects; general orthodontic subjects; orthodontic techniques; interdisciplinary subjects; management of health and safety; practice management, administration, and ethics; extramural educational activities. The programme goals and objectives are described and the competencies to be reached are outlined. These guidelines may serve as a baseline for programme development and quality assessment for postgraduate programme directors, national associations, and governmental bodies and could assist future residents when selecting a postgraduate programme.

Bioassay guideline 1: general guidlines for bioassay programs

International Nuclear Information System (INIS)

1980-01-01

This guideline is the first of a series of documents which elaborate criteria for bioassay programs, to be presented as recommendations to the Atomic Energy Control Board. It specifies which workers require routine bioassays, the accuracy and frequency of measurements, the dose levels at which specific actions must be taken, and the documentation required

[The German Program for Disease Management Guidelines: COPD Guideline 2006. Short review].

Science.gov (United States)

Ollenschläger, Günter; Kopp, Ina; Lelgemann, Monika

2007-01-15

In Germany, the first national consensus on evidence-based recommendations for COPD prevention and disease management was reached in spring 2006. After a development period of 9 months, the National Disease Management Guideline COPD was finalized by nominal group process under the authorship of the scientific societies for pneumology (DGP and Atemwegsliga), general internal medicine (DGIM), family medicine (DEGAM), and the Drug Commission of the German Medical Association (AKDAE). The recommendations' main sources are the NICE COPD Guideline 2004, the GOLD Recommendations as well as existing German guidelines and reviews of recent scientific evidence. The article gives an overview on authors, sources, and key recommendations of the German National Disease Management Guideline COPD 2006 (www.copd.versorgungsleitlinien.de).

Evaluation of features to support safety and quality in general practice clinical software

Science.gov (United States)

2011-01-01

Background Electronic prescribing is now the norm in many countries. We wished to find out if clinical software systems used by general practitioners in Australia include features (functional capabilities and other characteristics) that facilitate improved patient safety and care, with a focus on quality use of medicines. Methods Seven clinical software systems used in general practice were evaluated. Fifty software features that were previously rated as likely to have a high impact on safety and/or quality of care in general practice were tested and are reported here. Results The range of results for the implementation of 50 features across the 7 clinical software systems was as follows: 17-31 features (34-62%) were fully implemented, 9-13 (18-26%) partially implemented, and 9-20 (18-40%) not implemented. Key findings included: Access to evidence based drug and therapeutic information was limited. Decision support for prescribing was available but varied markedly between systems. During prescribing there was potential for medicine mis-selection in some systems, and linking a medicine with its indication was optional. The definition of 'current medicines' versus 'past medicines' was not always clear. There were limited resources for patients, and some medicines lists for patients were suboptimal. Results were provided to the software vendors, who were keen to improve their systems. Conclusions The clinical systems tested lack some of the features expected to support patient safety and quality of care. Standards and certification for clinical software would ensure that safety features are present and that there is a minimum level of clinical functionality that clinicians could expect to find in any system.

[Summary of the practice guideline 'Vaginal discharge' (first revision) from the Dutch College of General Practitioners].

Science.gov (United States)

Boukes, F S; Boeke, A J P; Dekker, J H; Wiersma, T; Goudswaard, A N

2007-06-16

The 1996 practice guideline of the Dutch College of General Practitioners (NHG) on vaginal discharge has been updated. Most women who visit their doctor with complaints about vaginal discharge do not have an increased risk of a sexually-transmitted disease. Investigations into vaginal discharge comprise history taking, physical examination and microscopic analysis in the laboratory of the general practitioner. Additional investigation into Chlamydia, gonorrhoea and Trichomonas infection is only necessary if the patient history reveals an increased risk of a sexually-transmitted disease. A Candida infection or bacterial vaginosis should only be treated if the patient experiences bothersome complaints. Treatment of a Candida infection consists of a vaginally applied imidazole compound. Bacterial vaginosis can be treated with oral administration of metronidazole. Patients with vaginal fluor can be examined and, if necessary, treated by their general practitioner. Referral to a gynaecologist is rarely necessary.

The potential carcinogenic risk of tanning beds: clinical guidelines and patient safety advice

International Nuclear Information System (INIS)

Mogensen, Mette; Jemec, Gregor BE

2010-01-01

In 2009, the WHO listed ultraviolet (UV) radiation as a group 1 carcinogen. In spite of this, each year, millions of people tan indoor in Western countries. The aim of this review is to summarize evidence of tanning bed carcinogenesis and to present guidelines for use of tanning beds and patient safety advice. A narrative review of the literature was conducted based on both PubMed and Medline searches and on literature review of the retrieved papers. Use of indoor tanning beds represents a significant and avoidable risk factor for the development of both melanoma and nonmelanoma skin cancers. Frequent tanners are more often adolescent females. Tanning beds have additional potential adverse effects such as burns, solar skin damage, infection, and possibly also addictive behavior. The effort in preventing UV light-induced carcinogenesis should currently be aimed at developing new strategies for public health information. Tanning beds are one preventable source of UV radiation. In the majority of people solar UV radiation continues to be the major factor and therefore anti-tanning campaigns must always include sunbathers

40 CFR 243.201 - Safety.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Safety. 243.201 Section 243.201 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES GUIDELINES FOR THE STORAGE... Procedures § 243.201 Safety. ...

Guidelines for testing sealed radiation sources

International Nuclear Information System (INIS)

1989-01-01

These guidelines are based on article 16(1) of the Ordinance on the Implementation of Atomic Safety and Radiation Protection dated 11 October 1984 (VOAS), in connection with article 36 of the Executory Provision to the VOAS, of 11 October 1984. They apply to the testing of sealed sources to verify their intactness, tightness and non-contamination as well as observance of their fixed service time. The type, scope and intervals of testing as well as the evaluation of test results are determined. These guidelines also apply to the testing of radiation sources forming part of radiation equipment, unless otherwise provided for in the type license or permit. These guidelines enter into force on 1 January 1990

Road safety audits: The way forward

CSIR Research Space (South Africa)

Labuschagne, FJJ

2010-08-01

Full Text Available The South African Road Safety Manual (SARSM) was published in 1999 and includes guidelines on road safety audits (RSA). The development of SARSM was a proactive process for improving the road environment with respect to road safety but was never...

Commentary on guidelines for radiation measurement and treatment of substances including naturally occurring radioactive materials

International Nuclear Information System (INIS)

Sakurai, Naoyuki; Ishiguro, Hideharu

2007-01-01

Study group on safety regulation on research reactors in Ministry of Education, Culture, Sports, Science and Technology (MEXT) reported the guidelines of 'Guidelines on radiation measurement and treatment of naturally occurring radioactive materials (NORM)' on 6 February 2006. RANDEC made the website contents 'Study on use and safety of the substances including uranium or thorium', based on the contract with MEXT to make theirs contents. This paper describes the outline of the website in MEXT homepage, background and contents of NORM guidelines in order to understand easily and visually the NORM guidelines, adding in some flowcharts and figures. (author)

Australian general practitioner attitudes to clinical practice guidelines and some implications for translating osteoarthritis care into practice.

Science.gov (United States)

Basedow, Martin; Runciman, William B; Lipworth, Wendy; Esterman, Adrian

2016-11-01

Clinical practice guidelines (CPGs) have been shown to improve processes of care and health outcomes, but there is often a discrepancy between recommendations for care and clinical practice. This study sought to explore general practitioner (GP) attitudes towards CPGs, in general and specifically for osteoarthritis (OA), with the implications for translating OA care into practice. A self-administered questionnaire was conducted in January 2013 with a sample of 228 GPs in New South Wales and South Australia. Seventy-nine GPs returned questionnaires (response rate 35%). Nearly all GPs considered that CPGs support decision-making in practice (94%) and medical education (92%). Very few respondents regarded CPGs as a threat to clinical autonomy, and most recognised that individual patient circumstances must be taken into account. Shorter CPG formats were preferred over longer and more comprehensive formats, with preferences being evenly divided among respondents for short, 2-3-page summaries, flowcharts or algorithms and single page checklists. GPs considered accessibility to CPGs to be important, and electronic formats were popular. Familiarity and use of The Royal Australian College of General Practitioners OA Guideline was poor, with most respondents either not aware of it (30%; 95% confidence interval (CI) 27 - 41%), had never used it (19%; 95% CI 12 - 29%) or rarely used it (34%; 95% CI 25-45%). If CPGs are to assist with the translation of evidence into practice, they must be easily accessible and in a format that encourages use.

[Clinical application evaluation of Guidelines for Diagnosis and Treatment of Internal Diseases in Traditional Chinese Medicine].

Science.gov (United States)

Han, Xue-Jie; Liu, Meng-Yu; Lian, Zhi-Hua; Wang, Li-Ying; Shi, Nan-Nan; Zhao, Jun

2017-09-01

To evaluate the applicability and clinical applications of Guidelines for Diagnosis and Treatment of Internal Diseases in Traditional Chinese Medicine, so as to provide the basis for the revision of the guidelines. This study was completed by the research and promotion base for traditional Chinese medicine(TCM) standard. The methods of applicability evaluation and application evaluation were used in the study. The questionnaires were filled out to evaluate applicability of the guideline, including doctor's familiarity with the guideline,the quality of the guideline, applicable conditions and clinical applications. The prospective case study analysis method was used to evaluate application of the guideline, including evaluation of clinical application compliance and application results(such as clinical effects, safety and economy). There were two parts in the guideline, which were TCM guideline and Western medicine guideline. The results of applicability evaluation showed that there were no obvious differences between TCM guideline and Western medicine guideline in doctor's familiarity with guideline(85.43%, 84.57%) and the use of the guideline(52.10%, 54.47%); the guidelines with good quality, and higher scores in the scope of application and the use of the term rationality(91.94%, 93.35%); the rationality scores of relevant contents in syndrome differentiation and treatment were more than 75%; the applicable conditions were better, and the safety score was the the highest. The comprehensive applicability evaluation showed that the proportion of the application of TCM guideline and Western medicine guideline were 77.73%, 75.46%, respectively. The results of application evaluation showed that there was high degree coincidence between the guideline with its clinical application; except for "other treatment" and "recuperation and prevention" in TCM, other items got high scores which were more than 90%; in the evaluation of application effects, safety of the guideline

Use of operational experience in fire safety assessment of nuclear power plants

International Nuclear Information System (INIS)

2000-01-01

Fire hazard has been identified as a major contributor to a plant's operational risk and the international nuclear power industry has been studying and developing tools for defending against this hazard. Considerable progress in design and regulatory requirements for fire safety, in fire protection technology and in related analytical techniques has been made in the past two decades. Substantial efforts have been undertaken worldwide to implement these advances in the interest of improving fire safety both at new and existing nuclear power plants. To assist in these efforts, the IAEA initiated a programme on fire safety that was intended to provide assistance to Member States in improving fire safety in nuclear power plants. In order to achieve this general objective, the IAEA programme aimed at the development of guidelines and good practices, the promotion of advanced fire safety assessment techniques, the exchange of state of the art information between practitioners and the provision of engineering safety advisory services and training in the implementation of internationally accepted practices. During the period 1993-1994, the IAEA activities related to fire safety concentrated on the development of guidelines and good practice documents related to fire safety and fire protection of operating plants. One of the first tasks was the development of a Safety Guide that formulates specific requirements with regard to the fire safety of operating nuclear power plants. Several documents, which provide advice on fire safety inspection, were developed to assist in its implementation. In the period 1995-1996, the programme focused on the preparation of guidelines for the systematic analysis of fire safety at nuclear power plants (NPPs). The IAEA programme on fire safety for 1997-1998 includes tasks aimed at promoting systematic assessment of fire safety related occurrences and dissemination of essential insights from this assessment. One of the topics addressed is the

The Inspector General's report on Nuclear Safety and Radiation Protection 2017

International Nuclear Information System (INIS)

2018-01-01

This report, written for the Chairman of EDF, gives the Inspector General's assessment of nuclear safety and radiation protection within the EDF Group. The report is also intended for all those in the company who contribute in any way to nuclear safety and radiation protection through their day-to-day actions and decisions. It also aims to identify any early warning signs and recommend areas for improvement. It therefore focuses on difficulties and weaknesses rather than strengths and progress. It is based on information gathered and observations made during the year, both in France and the UK, whether from workers in the field, or during visits to plants and meetings with the main stakeholders: managers, staff representatives, members of the medical profession, chairmen of local information commissions in France and of Site stakeholder groups (British equivalent of the French Local Information Commissions) in the UK, and contractors. It also makes use of visits and comparisons with other international players on the nuclear scene, and of dialogue with WANO (World Association of Nuclear Operators) and the nuclear safety authorities. Content: 1 - the Inspector General's view of 2017; 2 - Nuclear safety results; 3 - Nuclear safety priority affirmed; 4 - Risk prevention: important to remain vigilant; 5 - Adapting people skills; 6 - Operating experience: contrasting approaches; 7 - Operations fundamentals to be reaffirmed; 8 - Importance of working closely with contract partners; 9 - Engineering support for the French fleet and new-build projects; 10 - Spares: an area for greater engagement by owners on-site; 11 - Appendices

Potential safety features and safety analysis aspects for high performance light water reactor (HPLWR)

International Nuclear Information System (INIS)

Aksan, N.; Schulenberg, T.; Squarer, D.

2003-01-01

Research Activities are ongoing worldwide to develop advanced nuclear power plants with high thermal efficiency for the purpose to improve their economical competitiveness. Within the 5th Framework Programme of the European Commission, a project has been launched with the main objective to assess the technical and economical feasibility of a high efficiency LWR operating at super critical pressure conditions. Several European research institutions, industrial partners and the University of Tokyo participated and worked in this common research project. Within the aims of the development of the HPLWR is to use both passive and active safety systems for performing safety related functions in the event of transients or accidents. Consequently substantial effort has been invested in order to define the safety features of the plant in a European environment, as well as to incorporate passive safety features into the design. Throughout this process, the European Utility Requirements (EUR) and requirements known from Generation IV initiative were considered as a guideline in general terms in order to include further advanced ideas. The HPLWR general features were compared to both requirements, indicating a potential to meet these. Since, the supercritical HPLWR represents a challenge for best-estimate safety codes like RELAP5, CATHARE and TRAB due to the fact that these codes were developed for two-phase or single-phase coolant at pressures far below critical point, work on the preliminary assessment of the appropriateness of these codes have been performed for selected relevant phenomena, and application of the codes to the selected transients on the basis of defined 'reference design'. An overview on their successful upgrade to supercritical pressures and application to some plant safety analysis are provided in the paper. Further elaborations in relation to future needs are also discussed. (author)

[Summary of the practice guideline 'Viral hepatitis and other liver diseases' (second revision) from the Dutch College of General Practitioners].

Science.gov (United States)

Bouma, M; van Geldrop, W J; Numans, M E; Wiersma, Tj; Goudswaard, A N

2008-12-06

The revised Dutch College of General Practitioners' practice guideline 'Viral hepatitis and other liver diseases' offers advice in the diagnosis and management of viral hepatitis A, B and C and other liver diseases. The guideline is important for general practitioners as well as specialists in internal medicine and gastroenterology. The emphasis is on the management of chronic hepatitis B en C, because the prevalence of these diseases has increased in the Netherlands and, in addition, the treatment options for chronic hepatitis have improved. Consequently, timely recognition and adequate referral of patients with chronic hepatitis B or hepatitis C have become more important. However, many patients with a chronic liver disease have no symptoms. Therefore, the general practitioner should be aware that a patient visiting the practice with fatigue and malaise could have a liver disease if he or she belongs to a high-risk group or has had high-risk contacts. If the general practitioner repeatedly finds increased liver transaminase values during routine examination of asymptomatic patients, additional diagnostic tests should be performed. Further tests should focus on viral hepatitis as well as on non-alcoholic fatty liver disease and non-alcoholic steatohepatitis or, depending on the history-taking, liver damage due to excessive alcohol, medication or drug use.

Implementing a pediatric obesity care guideline in a freestanding children's hospital to improve child safety and hospital preparedness.

Science.gov (United States)

Porter, Renee M; Thrasher, Jodi; Krebs, Nancy F

2012-12-01

Medical and surgical care of children with severe obesity is complicated and requires recognition of the problem, appropriate equipment, and safe management. There is little literature describing patient, provider, and institutional needs for the severely obese pediatric patient. Nonetheless, the limited data suggest 3 broad categories of needs unique to this population: (a) airway management, (b) drug dosing and pharmacology, and (c) equipment and infrastructure. We describe an opportunity at the Children's Hospital Colorado to better prepare and optimize care for this patient population by creation of a Pediatric Obesity Care Guideline that focused on key areas of quality and safety. Copyright © 2012 Elsevier Inc. All rights reserved.

Safety classification of items in Tianwan Nuclear Power Plant

International Nuclear Information System (INIS)

Sun Yongbin

2005-01-01

The principle of integrality, moderation and equilibrium should be considered in the safety classification of items in nuclear power plant. The basic ways for safety classification of items is to classify the safety function based on the effect of the outside enclosure damage of the items (parts) on the safety. Tianwan Nuclear Power Plant adopts Russian VVER-1000/428 type reactor, it safety classification mainly refers to Russian Guidelines and standards. The safety classification of the electric equipment refers to IEEE-308(80) standard, including 1E and Non 1E classification. The safety classification of the instrumentation and control equipment refers to GB/T 15474-1995 standard, including safety 1E, safety-related SR and NC non-safety classification. The safety classification of Tianwan Nuclear Power Plant has to be approved by NNSA and satisfy Chinese Nuclear Safety Guidelines. (authors)

Nuclear safety management at the Wolsong NGS

Energy Technology Data Exchange (ETDEWEB)

Bong-Seob, Han [Korea Electric Power Corp., Wolson NPP no. 1 and 2 (Korea, Republic of)

1997-12-01

Nuclear safety management at the Wolsong nuclear power plant is described, including the following issues: site selection; plant history; operational goals; operational guidelines; reactor safety; safety training; plant maintenance; management of plant equipment lifetime; future tasks.

Nuclear safety management at the Wolsong NGS

International Nuclear Information System (INIS)

Han Bong-Seob

1997-01-01

Nuclear safety management at the Wolsong nuclear power plant is described, including the following issues: site selection; plant history; operational goals; operational guidelines; reactor safety; safety training; plant maintenance; management of plant equipment lifetime; future tasks

Nonreactor nuclear facilities: standards and criteria guide

International Nuclear Information System (INIS)

Brynda, W.J.; Junker, L.; Karol, R.C.; Lobner, P.R.; Goldman, L.A.

1981-09-01

This guide is a source document that identifies standards, codes, and guides that address the nuclear safety considerations pertinent to nuclear facilities as defined in DOE Order 5480.1, Chapter V, Safety of Nuclear Facilities. The guidance and criteria provided are directed toward areas of safety usually addressed in a Safety Analysis Report. The areas of safety include, but are not limited to, siting, principal design criteria and safety system design guidelines, radiation protection, accident analysis, and quality assurance. The guide is divided into two sections: general guidelines and appendices. Those guidelines that are broadly applicable to most nuclear facilities are presented in the general guidelines. These general guidelines may have limited applicability to subsurface facilities such as waste repositories. Guidelines specific to the various types or categories of nuclear facilities are presented in the appendices. These facility-specific appendices provide guidelines and identify standards and criteria that should be considered in addition to, or in lieu of, the general guidelines

Systematic tailoring for the implementation of guideline recommendations for anxiety and depressive disorders in general practice: perceived usefulness of tailored interventions

NARCIS (Netherlands)

Sinnema, H.; Terluin, B.; Wensing, M.; Volker, D.; Franx, G.; van Balkom, A.J.L.M.; de Lange, J.

2013-01-01

Background: The uptake of guideline recommendations in general practice can potentially be improved by designing implementation interventions that are tailored to prospectively identify barriers. However, there is insufficient evidence regarding the most effective and efficient approaches to

Systematic tailoring for the implementation of guideline recommendations for anxiety and depressive disorders in general practice: perceived usefulness of tailored interventions

NARCIS (Netherlands)

Sinnema, H.; Terluin, B.; Wensing, M.; Volker, D.; Franx, G.; Balkom, A. van; Lange, J.

2013-01-01

BACKGROUND: The uptake of guideline recommendations in general practice can potentially be improved by designing implementation interventions that are tailored to prospectively identify barriers. However, there is insufficient evidence regarding the most effective and efficient approaches to

[Less ethnic knowledge in the Dutch College of General Practitioner's practice guidelines on type 2 diabetes mellitus, hypertension and asthma in adults than in the supporting literature

NARCIS (Netherlands)

Manna, D.R.; Bruijnzeels, M.A.; Mokkink, H.G.A.; Berg, M. van den

2003-01-01

OBJECTIVE: To assess whether ethnic differences present in the scientific literature used as the basis for the Dutch College of General Practitioner's (NHG) practice guidelines were reflected in the ethnic-specific information the guidelines contained. DESIGN: Analysis of published information.

Safety assessment guidance in the International Atomic Energy Agency RADWASS Program

Energy Technology Data Exchange (ETDEWEB)

Vovk, I.F.; Seitz, R.R.

1995-12-31

The IAEA RADWASS programme is aimed at establishing a coherent and comprehensive set of principles and standards for the safe management of waste and formulating the guidelines necessary for their application. A large portion of this programme has been devoted to safety assessments for various waste management activities. Five Safety Guides are planned to be developed to provide general guidance to enable operators and regulators to develop necessary framework for safety assessment process in accordance with international recommendations. They cover predisposal, near surface disposal, geological disposal, uranium/thorium mining and milling waste, and decommissioning and environmental restoration. The Guide on safety assessment for near surface disposal is at the most advanced stage of preparation. This draft Safety Guide contains guidance on description of the disposal system, development of a conceptual model, identification and description of relevant scenarios and pathways, consequence analysis, presentation of results and confidence building. The set of RADWASS publications is currently undergoing in-depth review to ensure a harmonized approach throughout the Safety Series.

Report to the Attorney General on Body Armor Safety Initiative Testing and Activities

National Research Council Canada - National Science Library

2005-01-01

On November 17, 2003, Attorney General John Ashcroft announced the U.S. Department of Justice's Body Armor Safety Initiative in response to concerns from the law enforcement community regarding the effectiveness of body armor in use...

European project for developing general guidelines for harmonising internal dose assessment procedures (IDEAS)

International Nuclear Information System (INIS)

Andrasi, A.; Bailey, M.; Puncher, M.; Berkovski, V.; Eric Blanchardon, E.; Jourdain, J.-R.; Carlo-Maria Castellani, C.-M.; Doerfel, H.; Christian Hurtgen, Ch.; Le Guen, B.

2003-01-01

Several international intercomparison exercises on intake and internal dose assessments from monitoring data led to the conclusion that the results calculated by different participants varied significantly mainly because of the wide variety of methods and assumptions applied in the assessment procedure. Based on these experiences the need for harmonisation of the procedures has been formulated as an EU research project under the 5 th Framework Programme (2001-2005), with the aim of developing general guidelines for standardising assessments of intakes and internal doses. In the IDEAS project eight institutions from seven European countries are participating using inputs also from internal dosimetry professionals from across Europe to ensure broad consensus in the outcome of the project. The IDEAS project is explained

The effect of terrain slope on firefighter safety zone effectiveness

Science.gov (United States)

Bret Butler; J. Forthofer; K. Shannon; D. Jimenez; D. Frankman

2010-01-01

The current safety zone guidelines used in the US were developed based on the assumption that the fire and safety zone were located on flat terrain. The minimum safe distance for a firefighter to be from a flame was calculated as that corresponding to a radiant incident energy flux level of 7.0kW-m-2. Current firefighter safety guidelines are based on the assumption...

Modeling Guidelines for Code Generation in the Railway Signaling Context

Science.gov (United States)

Ferrari, Alessio; Bacherini, Stefano; Fantechi, Alessandro; Zingoni, Niccolo

2009-01-01

Modeling guidelines constitute one of the fundamental cornerstones for Model Based Development. Their relevance is essential when dealing with code generation in the safety-critical domain. This article presents the experience of a railway signaling systems manufacturer on this issue. Introduction of Model-Based Development (MBD) and code generation in the industrial safety-critical sector created a crucial paradigm shift in the development process of dependable systems. While traditional software development focuses on the code, with MBD practices the focus shifts to model abstractions. The change has fundamental implications for safety-critical systems, which still need to guarantee a high degree of confidence also at code level. Usage of the Simulink/Stateflow platform for modeling, which is a de facto standard in control software development, does not ensure by itself production of high-quality dependable code. This issue has been addressed by companies through the definition of modeling rules imposing restrictions on the usage of design tools components, in order to enable production of qualified code. The MAAB Control Algorithm Modeling Guidelines (MathWorks Automotive Advisory Board)[3] is a well established set of publicly available rules for modeling with Simulink/Stateflow. This set of recommendations has been developed by a group of OEMs and suppliers of the automotive sector with the objective of enforcing and easing the usage of the MathWorks tools within the automotive industry. The guidelines have been published in 2001 and afterwords revisited in 2007 in order to integrate some additional rules developed by the Japanese division of MAAB [5]. The scope of the current edition of the guidelines ranges from model maintainability and readability to code generation issues. The rules are conceived as a reference baseline and therefore they need to be tailored to comply with the characteristics of each industrial context. Customization of these

The development and evaluation of human factors guidelines for the review of advanced human-system interfaces

International Nuclear Information System (INIS)

O'Hara, J.M.

1992-01-01

Advanced control rooms for future nuclear power plants are being designed utilizing computer-based technologies. The US Nuclear Regulatory Commission reviews the human engineering of such control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are approximately supported in order to protect public health and safety. This paper describes the rationale, general approach, and initial development of an NRC Advanced Control Room Design Review Guideline

Standards and guidelines applicable for the validation of programmable automation systems

International Nuclear Information System (INIS)

Haapanen, P.; Maskuniitty, M.

1993-02-01

The validation of programmable automation system for an application important to safety in a nuclear power plant requires a comprehensive view about the system quality and reliability. One central point is to get assured that proper international guidelines and standards have been followed in the design, construction and maintenance of the system. The study was directed to locate international standards and guidelines which can support the validation of programmable systems and to evaluate their applicability for the validation of systems on different levels of requirement during their life cycle. The publication reviews the most important international standards (IAEA, ISO, IEC, IEEE) and their basic principles both for system and application program. Several nuclear standards, which have drawn the main attention, and some general programmable automation standards have been examined. In addition one practical automation system has been examined in order to find essential questions. Based on these studies a set of important items for the qualification have been identified

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

International Nuclear Information System (INIS)

2010-01-01

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

40 CFR 799.11 - Availability of test guidelines.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 31 2010-07-01 2010-07-01 true Availability of test guidelines. 799.11... General Provisions § 799.11 Availability of test guidelines. (a) The TSCA and FIFRA guidelines for the...-487-4650). (b) The OECD guidelines for the various study plans are available from the following...

Instructional materials for SARA/OSHA training. Volume 1, General site working training

Energy Technology Data Exchange (ETDEWEB)

Copenhaver, E.D.; White, D.A.; Wells, S.M. [Oak Ridge National Lab., TN (United States)

1988-04-01

This proposed 24 hour ORNL SARA/OSHA training curriculum emphasizes health and safety concerns in hazardous waste operations as well as methods of worker protection. Consistent with guidelines for hazardous waste site activities developed jointly by National Institute for Occupational Safety and Health, Occupational Safety and Health Administration, US Coast Guard, and the Envirorunental Protection Agency, the program material will address Basic Training for General Site Workers to include: ORNL Site Safety Documentation, Safe Work Practices, Nature of Anticipated Hazards, Handling Emergencies and Self-Rescue, Employee Rights and Responsibilities, Demonstration of Use, Care, and Limitations of Personal Protective, Clothing and Equipment, and Demonstration of Monitoring Equipment and Sampling Techniques. The basic training courses includes major fundamentals of industrial hygiene presented to the workers in a format that encourages them to assume responsibility for their own safety and health protection. Basic course development has focused on the special needs of ORNL facilities. Because ORNL generates chemical wastes, radioactive wastes, and mixed wastes, we have added significant modules on radiation protection in general, as well as modules on radiation toxicology and on radiation protective clothing and equipment.

National report of the Slovak Republic. Compiled in terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2003

International Nuclear Information System (INIS)

Burclova, J.; Ivan, J.; Jurina, V.

2003-04-01

A brief national safety report of the Slovak Republic in 2003 is presented. A account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD) is presented. These activities are reported under the headings: (A) Introduction; (B) Policies and practices; (C) Scope of application; (D) Inventories and lists; (E) Legislation and regulation; (F) Other general safety provisions; (G) Safety of spent fuel management; (H) Safety of radioactive waste management; (I) Transboundary movement; (J) Disused sealed sources; (K) Planned activities to improve safety; (L) Annexes: (I and II) List of SF and RAW management nuclear facilities; (III) List of nuclear facilities subject to decommissioning; (IV) Inventory of stored SF (t HM); (V) Inventory of disposed of and stored RAW; (VI) List of selected national laws, regulations and guidelines; (VII) List of international expert reports and safety analysis reports; (VIII) List of authors

National report of the Slovak Republic. Compiled in terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2003

Energy Technology Data Exchange (ETDEWEB)

Burclova, J [Nuclear Regulatory Authority of the Slovak Republic, Bratislava (Slovakia); Ivan, J [Slovenske elektrarne, a.s., Bratislava (Slovakia); Jurina, V [Health Ministry of the Slovak Republic, Bratislava (Slovakia); and others

2003-04-01

A brief national safety report of the Slovak Republic in 2003 is presented. A account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD) is presented. These activities are reported under the headings: (A) Introduction; (B) Policies and practices; (C) Scope of application; (D) Inventories and lists; (E) Legislation and regulation; (F) Other general safety provisions; (G) Safety of spent fuel management; (H) Safety of radioactive waste management; (I) Transboundary movement; (J) Disused sealed sources; (K) Planned activities to improve safety; (L) Annexes: (I and II) List of SF and RAW management nuclear facilities; (III) List of nuclear facilities subject to decommissioning; (IV) Inventory of stored SF (t HM); (V) Inventory of disposed of and stored RAW; (VI) List of selected national laws, regulations and guidelines; (VII) List of international expert reports and safety analysis reports; (VIII) List of authors.

Safety design integrated in the Building Delivery System

DEFF Research Database (Denmark)

Jørgensen, Kirsten

2012-01-01

phases of the building delivery system by using the principle of the lean construction modelling. The method for the research was to go through the lean construction building delivery system step by step and create a normative description of what to do, when to do and how to do to fully integration...... of safety in each process. The group of participants who created the description had a high experience in a combination of research, safety and health in general and especial in construction and knowledge of the lean construction processes both from the clients perspective as well as from the designers...... and the consultants. The result is a concept and guideline including control schemes for how to integrate safety design in the lean construction building delivery system including what to do and when. The concept has been tested in an educational context and found useful by the designers. The practical value...

Critical safety function guidelines for experimental fusion facilities

International Nuclear Information System (INIS)

Cadwallader, L.C.

1989-01-01

As fusion experiments proceed toward deuterium-tritium operation, more attention is being given to public safety. This paper presents the four classes of functions that fusion experiments must provide to assure safe, stable shutdown and retention of radionuclides. These functions are referred to as critical safety functions (CSFs). Selecting CSFs is an important step in probabilistic risk assessment (PRA). An example of CSF selection and usage for the Compact Ignition Tokamak (CIT) is also presented

Selective prevention of cardiometabolic diseases in general practice: attitudes and working methods of male and female general practitioners before and after the introduction of the Prevention Consultation guideline in the Netherlands

NARCIS (Netherlands)

Vos, H.M.M.; Delft, D.H. Van; Kleijn, M.J.J. de; Nielen, M.M.; Schellevis, F.G.; Lagro-Janssen, A.L.M.

2014-01-01

RATIONALE, AIMS AND OBJECTIVES: In 2011 the module cardiometabolic risk of the Prevention Consultation guideline was introduced in the Netherlands in order to prevent cardiometabolic diseases. We aimed to compare attitudes and working methods of Dutch general practitioners (GPs) towards selective

Selective prevention of cardiometabolic diseases in general practice: attitudes and working methods of male and female general practitioners before and after the introduction of the Prevention Consultation guideline in the Netherlands.

NARCIS (Netherlands)

Vos, H.M.M.; Delft, D.H.W.J.M. van; Kleijn, M.J.J. de; Nielen, M.M.J.; Schellevis, F.G.; Lagro-Janssen, A.L.M.

2014-01-01

Rationale, aims and objectives; In 2011 the module cardiometabolic risk of the Prevention Consultation guideline was introduced in the Netherlands in order to prevent cardiometabolic diseases. We aimed to compare attitudes and working methods of Dutch general practitioners (GPs) towards selective

Selective prevention of cardiometabolic diseases in general practice: attitudes and working methods of male and female general practitioners before and after the introduction of the Prevention Consultation guideline in the Netherlands

NARCIS (Netherlands)

Vos, H.M.M.; Van Delft, D.H.W.J.; de Kleijn, M.J.J.; Nielen, M.M.J.; Schellevis, F.G.; Lagro-Janssen, A.L.M.

2014-01-01

Rationale, aims and objectives In 2011 the module cardiometabolic risk of the Prevention Consultation guideline was introduced in the Netherlands in order to prevent cardiometabolic diseases. We aimed to compare attitudes and working methods of Dutch general practitioners (GPs) towards selective

Safety Culture Development : The Gap Between Industry Guidelines and Literature, and the Differences Amongst Industry Sectors.

NARCIS (Netherlands)

Karanikas, Nektarios; Soltani, Pedram; de Boer, Robert J.; Roelen, Alfred L.C.; Arezes, Pedro

2016-01-01

Reason’s typology of safety culture (i.e. Just, Informative, Learning, Flexible and Reporting cultures) is widely used in the industry and academia. Through literature review we developed a framework including 36 markers that reflect the operationalization of Reason’s sub-cultures and general

PROSPER guidelines: Guidelines for peer review and for plant self-assessment of operational experience feedback process

International Nuclear Information System (INIS)

2003-01-01

Effective use of operational performance information is an important element in any plant operator's arrangements for enhancing the operational safety of a nuclear power plant (NPP). This has been recognized in the IAEA Safety Fundamental, The Safety of Nuclear Installations (Safety Series No. 110). Under the technical aspects of safety, one of the principles of operation and maintenance is that the operating organization and the regulatory body shall establish complementary programmes to analyse operating experience to ensure that lessons are learned and acted upon. Such experience shall be shared with relevant national and international bodies. The Convention on Nuclear Safety, which entered into force in July 1996, also recognized the importance of operational experience feedback as a tool of high importance for the safety of nuclear plant operation and its further enhancement. It follows that the arrangements and results achieved under the operation experience feedback process in Member States will be covered by the national report under the Convention and will be subject to periodical review. These principles are further expanded in the IAEA Safety Standards Safety of Nuclear Power Plants: Operation (Safety Standard Series No. NS-R-2, year 2000) under the Feedback of The IAEA-led Peer Review of the effectiveness of the Operational Safety Performance Experience Review process (PROSPER) and associated guidelines have been developed to provide advice and assistance to utilities or individual power plants to strengthen and enhance the effectiveness of operational experience programmes in achieving these fundamental objectives. The objectives of the former IAEA Assessment of Significant Safety Events Team (ASSET) service have been expanded to include an evaluation of the effective use of all operating performance information available to the plant (e.g. external operating experience, internal low-level and near miss event reports and other relevant operating

[Guidelines for wise utilization of knee imaging].

Science.gov (United States)

Finestone, Aharon S; Eshed, Iris; Freedman, Yehuda; Beer, Yiftah; Bar-Sever, Zvi; Kots, Yavvgeni; Adar, Eliyahu; Mann, Gideon

2012-02-01

The knee is a complex structure afflicted with diverse pathologies. Correct management of knee complaints demands wise utilization of imaging modalities, considering their accuracy in the specific clinical situation, the patient's safety and availability and financial issues. Some of these considerations are universal, while others are local, depending on medical and insurance systems. There is controversy and unclearness regarding the best imaging modality in different clinical situations. To develop clinical guidelines for utilizing knee imaging. Leading physicians in specialties associated with knee disease and imaging were invited to participate in a panel on the guidelines. Controversies were settled in the main panel or in sub-panels. The panel agreed on the principles in choosing from the various modalities, primarily medical accuracy, followed by patient safety, availability and cost. There was agreement that the physician is responsible to choose the most appropriate diagnostic tool, consulting, when necessary, on the advantages, limitations and risks of the various imaging modalities. A comprehensive table was compiled with the importance of the different imaging modalities in various clinical situations. For the first time, Israeli guidelines on wise utilization of knee imaging are presented. They take into consideration the clinical situations and also availability and financial issues specific to Israel. These guidelines will serve physicians of several disciplines and medical insurers to improve patient management efficiently.

System safety engineering analysis handbook

Science.gov (United States)

Ijams, T. E.

1972-01-01

The basic requirements and guidelines for the preparation of System Safety Engineering Analysis are presented. The philosophy of System Safety and the various analytic methods available to the engineering profession are discussed. A text-book description of each of the methods is included.

40 CFR 240.209 - Safety.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Safety. 240.209 Section 240.209 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES GUIDELINES FOR THE THERMAL PROCESSING OF SOLID WASTES Requirements and Recommended Procedures § 240.209 Safety. ...

[Standards and guidelines of radiation protection and safety in dental X-ray examinations].

Science.gov (United States)

Guo, X L; Li, G; Cheng, Y; Yu, Q; Wang, H; Zhang, Z Y

2017-12-09

With the rapid development of imaging technology, the application of dental imaging in diagnosis, treatment planning, intraoperative surgical navigation, monitoring of treatment or lesion development and assessment of treatment outcomes is playing an essential role in oral healthcare. The increased total number of dental X-ray examinations is accompanied by a relatively significant increase in collective dose to patients as well as to dental healthcare workers, which is harmful to human bodies to a certain degree. Some radiation protection standards and guidelines in dental radiology have been published in European countries, US, Canada and Australia, etc. Adherence to these standards and guidelines helps to achieve images with diagnostic quality and avoid unnecessary and repeated exposures. However, no radiation protection standard or guideline with regard to dental X-ray examinations has been put in force so far in mainland China. Therefore, a literature review on available radiation protection standards and guidelines was conducted to provide reference to the development of radiation protection standards or guidelines in mainland China.

Guidelines for training and qualification of radiological protection technicians

International Nuclear Information System (INIS)

1987-08-01

These guidelines, used in combination with plant-specific job analysis, provide the framework for a training and qualification program for radiological protection technicians at nuclear power plants. Radiological protection technicians are defined as those individuals, both plant and contractor, who will be engaged in the evaluation of radiological conditions in the nuclear plant and the implementation of the necessary radiological safety measures as they apply to nuclear plant workers and members of the general public. An important aspect of this work is recognizing and handling unusual situations involving radioactivity, including incidents related to degraded core conditions. These guidelines incorporate the results of an industry-wide job analysis and task analysis (JTA) combined with industry operating experience review. However, the industry-wide analyses did not identify all important academic and fundamental knowledge and skills. Further in-depth analysis by subject matter experts produced additional knowledge and skills that were added to these guidelines. All utilities should use these guidelines in conjunction with plant-specific and industry-wide JTA results to develop or validate their radiological protection technician training program. Plant-specific information should be used to establish appropriate training program content. This plant-specific information should reflect unique job duties, equipment, operating experience, and trainee entry-level qualifications. Revisions to these guidelines should be reviewed for applicability and incorporated into the training program using each utility's training system development (TSD) procedures. Plant-specific job analysis and task analysis data is essential to the development of performance-based training programs. These analyses are particularly useful in selecting tasks for training and in developing on-the-job training (OJT), laboratory training, and mock-up training. Qualification programs based on these

The policies and practices of sports governing bodies in relation to assessing the safety of sports grounds.

Science.gov (United States)

Swan, Peter; Otago, Leonie; Finch, Caroline F; Payne, Warren R

2009-01-01

Sport is an important context for physical activity and it is critical that safe environments are provided for such activity. Sports safety is influenced by the presence of sports ground environmental hazards such as ground hardness, poorly maintained playing fields, surface irregularities and the presence of debris/rubbish. To reduce injury risk, sports governing bodies need to ensure regular assessment of grounds safety and the removal of identified hazards. This study describes sports ground safety guidelines and recommendations of a sample of sports governing bodies and provides recommendations for how they could be improved. Semi-structured key informant interviews were conducted with nominees of state governing bodies for Australian football, cricket, soccer and hockey. The use of matchday checklists to identify ground hazards, as mandated by insurance companies was widely promoted across all levels of play. Sports governing bodies had more direct involvement in assessing grounds used for higher level of play, than grounds used for community or junior sport. There was a general presumption that identified hazards on community grounds would be corrected by local councils or clubs before anyone played on them, but this was rarely monitored. Sports governing bodies run the risk of being negligent in their duty of care to sports participants if they do not formally monitor the implementation of their ground safety polices and guidelines. There is also further scope for sports bodies to work closely with insurers to develop ground safety assessment guidelines specific to their sport.

Critical safety function guidelines for experimental fusion facilities

International Nuclear Information System (INIS)

Cadwallader, L.C.

1989-01-01

As fusion experiments proceed toward deuterium-tritium operation, more attention is being given to public safety. This paper presents the four classes of functions that fusion experiments must provide to assure safe, stable shutdown and retention of radionuclides. These functions are referred to as critical safety functions (CSFs). Selecting CSFs is an important step in probabilistic risk assessment (PRA). An example of CSF selection and usage for the Compact Ignition Tokamak (CIT) is also presented. 10 refs., 6 figs

[The German Program for Disease Management Guidelines: CHD Guideline 2006. Short review].

Science.gov (United States)

Ollenschläger, Günter; Lelgemann, Monika; Kopp, Ina

2006-12-15

In Germany, the first national consensus on evidence-based recommendations for disease management in patients with chronic coronary heart disease was reached in summer 2006. After a development period of 4 years, the National Disease Management Guideline Chronic Coronary Heart Disease was finalized by nominal group process under the authorship of the scientific associations for cardiac rehabilitation (DGPR), cardiac surgery (DGTHG), cardiology (DGK), general internal medicine (DGIM), family medicine (DEGAM), and the Drug Commission of the German Medical Association (AKDAE). The recommendations' main sources are the ACC/AHA guidelines 2002 updates as well as existing German guidelines and reviews of recent scientific evidence. The article gives an overview on authors, sources, and key recommendations of the German National Disease Management Guideline Chronic Coronary Heart Disease 2006 (www.khk.versorgungsleitlinie.de).

Proposed Regulatory Guideline on the PSA Quality for Risk-informed Applications

International Nuclear Information System (INIS)

Lee, Chang Ju; Choi, Jong Soo

2005-01-01

In the policy statement on nuclear safety issued by the Korean government in 1994, the introduction of risk-informed regulations in licensing and regulation of nuclear power plants was emphasized for the first time. It also describes the implementation of comprehensive safety assessment utilizing PSA (probabilistic safety assessment). Since then, because risk-informed environment and fundamentals had not been strong, several R and D on PSA and risk-informed regulation have been done even though their application has been delayed. However, today it is not the case. Since the follow-up policy statement (called Severe Accident Policy) was issued, which prescribes strong items such as PSA implementation and its periodic reassessment, reliability database, and risk monitoring program to the utility, we have a chance to easily get all kinds of risk information for improving current regulatory framework. In addition, with the overall availability of PSA results for all operating nuclear power plants, it is expected that many risk-informed applications (RIAs) will be submitted to the regulatory authority. In general, there are a lot of regulatory concerns associated with the quality assurance of licensee's submittals for RIA. It is also noted that making general requirements and touching specific check points are essential for the regulatory decision making process. This paper summarizes the structure and contents of our regulatory guideline for assuring PSA quality

Vehicle recovery and towing guideline

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-01-15

This guideline was developed to provide light and medium duty vehicles operators in the oil and gas industry with a set of best practices for avoiding injury and damage during the recovery of stuck vehicles. The aim of the guideline was to increase awareness of safety issues and promote the safe usage of the vehicles by personnel throughout the petroleum industry and to establish minimum standards of practice for vehicle recovery. The guideline included a step-by-step guide for pulling out a vehicle with a recovery strap as well as vehicle-mounted winch procedures. Pre-job checklists for both procedures were provided. Issues related to the strength rating of vehicle tow hooks and hitch receivers were discussed, as well as some of the hazards associated with steep terrains and heavy mud. The guideline also included recommendations for a vehicle recovery kit with instructions on vehicle recovery, a recovery strap, a recovery hitch and shackle, a collapsible shovel, traffic cones and reflector flares, and a heavy blanket and gloves. 7 refs., 2 tabs., 13 figs.

Data Qualification guidelines

International Nuclear Information System (INIS)

Edwards, T.B.; Shine, E.P.

1992-01-01

Data Qualification (DQ) is a formal, technical process whose objective is to affirm that experimental data are suitable for their intended use. Although it is not possible to develop a fixed recipe for the DQ process to cover all test situations, these general guidelines have been developed for the Nuclear Engineering Section to establish a framework for qualifying data from steady-state processing. These guidelines outline the role of the DQ team providing insight into the planning and conducting of the DQ process

[Optimal intravascular brachytherapy: safety and radiation protection, reliability and precision guaranteed by guidelines, recommendations and regulatory requirements].

Science.gov (United States)

Quast, Ulrich; Kaulich, Theodor W; Lorenz, Joachim

2002-02-01

The success of intravascular brachytherapy relies entirely on the interdisciplinary approach. Interventional cardiologists, radiation oncologists and medical physicists must form a team from day 1. All members of the team need special knowledge and regular training in the field of vascular radiation therapy. Optimization of intravascular brachytherapy requires the use of standardized methods of dose specification, recording and reporting. This also implies using standardized methods of source calibration in terms of absorbed dose to water and having methods for simple internal control of the dosimetric quantities of new or replaced sources. Guidance is offered by international recommendations (AAPM TG 60, DGMP Report 16, NCS and EVA GEC-ESTRO). LEGAL REQUIREMENTS FOR RADIATION PROTECTION--WHAT'S NEW?: In Europe, new legal requirements on radiation protection issues have to be fulfilled. For Germany, the revised "Strahlenschutzverordnung" has been released recently. Nearly all organizational and medical processes are affected. For intravascular brachytherapy, several changes of requirements have to be considered. However, to follow these requirements does not cause serious problems. DGMP REPORT 16: GUIDELINES FOR MEDICAL PHYSICAL ASPECTS OF INTRAVASCULAR BRACHYTHERAPY: Evaluation of clinical results by comparison of intravascular brachytherapy treatment parameters is possible only if the prescribed dose and the applied dose distribution are reported clearly, completely and uniformly. The DGMP guidelines thus recommend to prescribe the dose to water at the system related reference point PRef at 2 mm radial distance for intracoronary application (and at 5 mm for peripheral vessels). The mean dose at 1 mm tissue depth (respectively at 2 mm) should be reported in addition. To safely define the planning target volume from the injured length, safety margins of at least 5 mm (10 mm) have to be taken into account on both ends. Safety margins have also to be considered for

The emergency response guidelines for the Westinghouse pressurized water reactor

International Nuclear Information System (INIS)

Dekens, J.P.; Bastien, R.; Prokopovich, S.R.

1985-01-01

The Three Mile Island accident has demonstrated that the guidance provided for mitigating the consequences of design basis accidents could be inadequate when multiple incidents, failures or errors occur during or after the accident. Westinghouse and the Westinghouse Owners Group have developed new Emergency Response Guidelines (E.R.G.). The E.R.G. are composed of two independent sets of procedures and of a systematic tool to continuously evaluate the plant safety throughout the response to an accident. a) The Optimal Recovery Guidelines are entered each time the reactor is tripped or the Emergency Core Cooling System is actuated. An immediate verification of the automatic protective actuations is performed and the accident diagnosis process is initiated. When nature of the accident is identified, the operator is transferred to the applicable recovery procedure and subprocedures. A permanent rediagnosis is performed throughout the application of the optimal Recovery Guidelines and cross connections are provided to the adequate procedure if an error in diagnosis is identified. b) Early in the course of the accident, the operating staff initiates monitoring of the Critical Safety Functions. These are defined as the set of functions ensuring the integrity of the physical barriers against radioactivity release. The review of these functions is peformed continuously through a cyclic application of the status trees. c) The Function Restoration Guidelines are entered when the Critical Safety Function monitoring identifies a challenge to one of the functions. Depending on the severity of the challenge, the transfer to a Function Restoration Guideline can be immediate for a severe challenge or delayed for a minor challenge. Those guidelines are independent of the scenario of the accident, but only based on plant parameters and equipment availability

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

International Nuclear Information System (INIS)

Tandonnet, Jean

2012-01-01

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

Current Guidelines Have Limited Applicability to Patients with Comorbid Conditions: A Systematic Analysis of Evidence-Based Guidelines

Science.gov (United States)

Lugtenberg, Marjolein; Burgers, Jako S.; Clancy, Carolyn; Westert, Gert P.; Schneider, Eric C.

2011-01-01

Background Guidelines traditionally focus on the diagnosis and treatment of single diseases. As almost half of the patients with a chronic disease have more than one disease, the applicability of guidelines may be limited. The aim of this study was to assess the extent that guidelines address comorbidity and to assess the supporting evidence of recommendations related to comorbidity. Methodology/Principal Findings We conducted a systematic analysis of evidence-based guidelines focusing on four highly prevalent chronic conditions with a high impact on quality of life: chronic obstructive pulmonary disease, depressive disorder, diabetes mellitus type 2, and osteoarthritis. Data were abstracted from each guideline on the extent that comorbidity was addressed (general comments, specific recommendations), the type of comorbidity discussed (concordant, discordant), and the supporting evidence of the comorbidity-related recommendations (level of evidence, translation of evidence). Of the 20 guidelines, 17 (85%) addressed the issue of comorbidity and 14 (70%) provided specific recommendations on comorbidity. In general, the guidelines included few recommendations on patients with comorbidity (mean 3 recommendations per guideline, range 0 to 26). Of the 59 comorbidity-related recommendations provided, 46 (78%) addressed concordant comorbidities, 8 (14%) discordant comorbidities, and for 5 (8%) the type of comorbidity was not specified. The strength of the supporting evidence was moderate for 25% (15/59) and low for 37% (22/59) of the recommendations. In addition, for 73% (43/59) of the recommendations the evidence was not adequately translated into the guidelines. Conclusions/Significance Our study showed that the applicability of current evidence-based guidelines to patients with comorbid conditions is limited. Most guidelines do not provide explicit guidance on treatment of patients with comorbidity, particularly for discordant combinations. Guidelines should be more

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

International Nuclear Information System (INIS)

Moere, Hans

2012-06-01

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

Philosophy of safety evaluation on fast breeder reactor

International Nuclear Information System (INIS)

1981-01-01

This is the report submitted from the special subcommittee on reactor safety standard to the Nuclear Safety Commission on October 14, 1980, and it was decided to temporarily apply this concept to the safety examination on fast breeder reactors. The examination and discussion of this report were performed by taking the prototype reactor ''Monju'' into consideration, which is to be the present target, referring to the philosophy of the safety evaluation on fast breeder reactors in foreign countries and based on the experiences in the fast experimental reactor ''Joyo''. The items applicable to the safety evaluation for liquid metal-cooled fast breeder reactors (LMFBR) as they are among the existing safety examination guidelines are applied. In addition to the existing guidelines, the report describes the matters to be considered specifically for core, fuel, sodium, sodium void, reactor shut-down system, reactor coolant boundary, cover gas boundary and others, intermediate cooling system, removal of decay heat, containment vessels, high temperature structures, and aseismatic property in the safety design of LMFBR's. For the safety evaluation for LMFBR's, the abnormal transient changes in operation and the phenomena to be evaluated as accidents are enumerated. In order to judge the propriety of the criteria of locating LMFBR facilities, the serious and hypothetical accidents are decided to be evaluated in accordance with the guideline for reactor location investigation. (Wakatsuki, Y.)

Implementation of safety parameter display system at VVER-440 NPPs

International Nuclear Information System (INIS)

Manninen, T.

1997-01-01

Furnishing WWER-440 nuclear power plant units with a safety parameter display system (SPDS) fulfilling the requirements of internationally recognized standards and guidelines has been ranked high on the lists of proposed safety improvement projects. Technically such an SPDS system can be implemented either as a separate stand-alone system or as a more or less closely integrated part of a process information system of the plant unit. In the paper examples of these approaches are presented. Functionally all these examples include the well proven SPDS concept developed by IVO Power Engineering Ltd, Finland. The functional design basis, the general requirements for the system platform, experience with implementation and expansion possibilities of the systems are discussed. (author)

General design safety principles for nuclear power plants

International Nuclear Information System (INIS)

1986-01-01

This Safety Guide provides the safety principles and the approach that have been used to implement the Code in the Safety Guides. These safety principles and the approach are tied closely to the safety analyses needed to assist the design process, and are used to verify the adequacy of nuclear power plant designs. This Guide also provides a framework for the use of other design Safety Guides. However, although it explains the principles on which the other Safety Guides are based, the requirements for specific applications of these principles are mostly found in the other Guides

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

International Nuclear Information System (INIS)

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

2011-08-01

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

Southern African guidelines on the safe use of pre-exposure ...

African Journals Online (AJOL)

With the flurry of data that has been generated in PrEP clinical research since the first guideline, it became evident that there was a need to revise and expand the PrEP guidelines with new evidence of safety and efficacy of PrEP in several populations, including MSM, transgender persons, heterosexual men and women, ...

The Inspector General's report on Nuclear Safety and Radiation Protection 2014

International Nuclear Information System (INIS)

2015-01-01

This report, written for the Chairman of EDF, gives the Inspector General's assessment of nuclear safety and radiation protection within the EDF Group. The report is also intended for all those in the company who contribute in any way to nuclear safety and radiation protection through their day-to-day actions and decisions. It also aims to identify any early warning signs and recommend areas for improvement. It therefore focuses on difficulties and weaknesses rather than strengths and progress. It is based on information gathered and observations made during the year, both in France and the UK, whether from workers in the field, or during visits to plants and meetings with the main stakeholders: managers, staff representatives, members of the medical profession, chairmen of local information commissions in France and of Site stakeholder groups (British equivalent of the French Local Information Commissions) in the UK, and contractors. It also makes use of visits and comparisons with other international players on the nuclear scene, and of dialogue with WANO (World Association of Nuclear Operators) and the nuclear safety authorities. Content: 1 - the Inspector General's view of 2014; 2- Contrasting trends in nuclear safety in different sets of plants; 3 - Making safety culture central to management; 4 - Towards an integrated approach to risk management; 5 - Relying on professional unified operations; 6 - The quest for robust maintenance; 7 - Nuclear engineering: a major asset for the operator; 8 - Nuclear managers - confidence builders; 9 - on course for reactor operation beyond 40 years in France; 10 - Service life challenges in the UK; 11 - Preparing the future: from the EPR to other new models; 12 - Noteworthy operational events; 13- Appendices: Results for the nuclear fleets (EDF SA, EDF Energy; Maps of the nuclear power plants(EDF SA, EDF Energy); Key dates for the nuclear units (EDF SA, EDF Energy); Abbreviations

The Inspector General's report on Nuclear Safety and Radiation Protection 2015

International Nuclear Information System (INIS)

2016-01-01

This report, written for the Chairman of EDF, gives the Inspector General's assessment of nuclear safety and radiation protection within the EDF Group. The report is also intended for all those in the company who contribute in any way to nuclear safety and radiation protection through their day-to-day actions and decisions. It also aims to identify any early warning signs and recommend areas for improvement. It therefore focuses on difficulties and weaknesses rather than strengths and progress. It is based on information gathered and observations made during the year, both in France and the UK, whether from workers in the field, or during visits to plants and meetings with the main stakeholders: managers, staff representatives, members of the medical profession, chairmen of local information commissions in France and of Site stakeholder groups (British equivalent of the French Local Information Commissions) in the UK, and contractors. It also makes use of visits and comparisons with other international players on the nuclear scene, and of dialogue with WANO (World Association of Nuclear Operators) and the nuclear safety authorities. Content: 1 - the Inspector General's view of 2015; 2 - Operational safety: mixed results; 3 - Nuclear safety clearly prioritised; 4 - Risk prevention: progress in France; 5 - Reinforced emergency preparedness post-Fukushima; 6 - Fire prevention: still a weak link; 7 - Continuous investment in training and careers; 8 - Using maintenance to leverage improved operational quality; 9 - Chemistry in France: a transition in need of strong support; 10 - Decommissioning projects are progressing; 11 - EPRs in China, France and the UK; 12 - Preparing for the future; 13 - A window on the world; 14 - Appendices: Results for the nuclear fleets (EDF SA, EDF Energy; Maps of the nuclear power plants(EDF SA, EDF Energy); Key dates for the nuclear units (EDF SA, EDF Energy); Abbreviations

Use of modern software - based instrumentation in safety critical systems

International Nuclear Information System (INIS)

Emmett, J.; Smith, B.

2005-01-01

Many Nuclear Power Plants are now ageing and in need of various degrees of refurbishment. Installed instrumentation usually uses out of date 'analogue' technology and is often no longer available in the market place. New technology instrumentation is generally un-qualified for nuclear use and specifically the new 'smart' technology contains 'firmware', (effectively 'soup' (Software of Uncertain Pedigree)) which must be assessed in accordance with relevant safety standards before it may be used in a safety application. Particular standards are IEC 61508 [1] and the British Energy (BE) PES (Programmable Electronic Systems) guidelines EPD/GEN/REP/0277/97. [2] This paper outlines a new instrument evaluation system, which has been developed in conjunction with the UK Nuclear Industry. The paper concludes with a discussion about on-line monitoring of Smart instrumentation in safety critical applications. (author)

Advanced control room design review guidelines: Integration of the NUREG-0700 guidelines and development of new human-system interface guidelines