[Prevention of medical device-related adverse events in hospitals: Specifying the recommendations of the German Coalition for Patient Safety (APS) for users and operators of anaesthesia equipment].

Science.gov (United States)

Bohnet-Joschko, Sabine; Zippel, Claus; Siebert, Hartmut

2015-01-01

The use and organisation of medical technology has an important role to play for patient and user safety in anaesthesia. Specification of the recommendations of the German Coalition for Patient Safety (APS) for users and operators of anaesthesia equipment, explore opportunities and challenges for the safe use and organisation of anaesthesia devices. We conducted a literature search in Medline/PubMed for studies dealing with the APS recommendations for the prevention of medical device-related risks in the context of anaesthesia. In addition, we performed an internet search for reports and recommendations focusing on the use and organisation of medical devices in anaesthesia. Identified studies were grouped and assigned to the recommendations. The division into users and operators was maintained. Instruction and training in anaesthesia machines is sometimes of minor importance. Failure to perform functional testing seems to be a common cause of critical incidents in anaesthesia. There is a potential for reporting to the federal authority. Starting points for the safe operation of anaesthetic devices can be identified, in particular, at the interface of staff, organisation, and (anaesthesia) technology. The APS recommendations provide valuable information on promoting the safe use of medical devices and organisation in anaesthesia. The focus will be on risks relating to the application as well as on principles and materials for the safe operation of anaesthesia equipment. Copyright © 2015. Published by Elsevier GmbH.

30 CFR 77.410 - Mobile equipment; automatic warning devices.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Mobile equipment; automatic warning devices. 77... UNDERGROUND COAL MINES Safeguards for Mechanical Equipment § 77.410 Mobile equipment; automatic warning devices. (a) Mobile equipment such as front-end loaders, forklifts, tractors, graders, and trucks, except...

Evaluation of safety requirements of erbium laser equipment used in dentistry

International Nuclear Information System (INIS)

Braga, Flavio Hamilton

2002-01-01

The erbium laser (Er:YAG) has been used in several therapeutic processes. Erbium lasers, however, operate with energies capable to produce lesions in biological tissues. Aiming the safe use, the commercialization of therapeutic laser equipment is controlled in Brazil, where the equipment should comply with quality and safety requirement prescribed in technical regulations. The objective of this work is to evaluate the quality and safety requirements of a commercial therapeutic erbium laser according to Brazilian regulations, and to discuss a risk control program intended to minimize the accidental exposition at dangerous laser radiation levels. It was verified that the analyzed laser can produce lesions in the skin and eyes, when exposed to laser radiation at distances smaller than 80 cm by 10 s or more. In these conditions, the use of protection glasses is recommended to the personnel that have access to the laser operation ambient. It was verified that the user's training and the presence of a target indicator are fundamental to avoid damages in the skin and buccal cavity. It was also verified that the knowledge and the correct use of the equipment safety devices, and the application of technical and administrative measures is efficient to minimize the risk of dangerous expositions to the laser radiation. (author)

Plutonium finishing plant safety systems and equipment list

International Nuclear Information System (INIS)

Bergquist, G.G.

1995-01-01

The Safety Equipment List (SEL) supports Analysis Report (FSAR), WHC-SD-CP-SAR-021 and the Plutonium Finishing Plant Operational Safety Requirements (OSRs), WHC-SD-CP-OSR-010. The SEL is a breakdown and classification of all Safety Class 1, 2, and 3 equipment, components, or system at the Plutonium Finishing Plant complex

FAST and SAFE Passive Safety Devices for Sodium-cooled Fast Reactor

Energy Technology Data Exchange (ETDEWEB)

Hartanto, Donny; Kim, Chihyung; Kim, In-Hyung; Kim, Yonghee [KAIST, Daejeon (Korea, Republic of)

2015-05-15

The major factor is the impact of the neutron spectral hardening. The second factor that affects the CVR is reduced capture by the coolant when the coolant voiding occurs. To improve the CVR, many ideas and concepts have been proposed, which include introduction of an internal blanket, spectrum softening, or increasing the neutron leakage. These ideas may reduce the CVR, but they deteriorate the neutron economy. Another potential solution is to adopt a passive safety injection device such as the ARC (autonomous reactivity control) system, which is still under development. In this paper, two new concepts of passive safety devices are proposed. The devices are called FAST (Floating Absorber for Safety at Transient) and SAFE (Static Absorber Feedback Equipment). Their purpose is to enhance the negative reactivity feedback originating from the coolant in fast reactors. SAFE is derived to balance the positive reactivity feedback due to sodium coolant temperature increases. It has been demonstrated that SAFE allows a low-leakage SFR to achieve a self-shutdown and self-controllability even though the generic coolant temperature coefficient is quite positive and the coolant void reactivity can be largely managed by the new FAST device. It is concluded that both FAST and SAFE devices will improve substantially the fast reactor safety and they deserve more detailed investigations.

76 FR 23255 - Federal Motor Vehicle Safety Standards; Lamps, Reflective Devices, and Associated Equipment

Science.gov (United States)

2011-04-26

... petitions for reconsideration from Harley-Davidson Motor Company (January 18, 2008) and Ford Motor Company... [Docket No. NHTSA-2007-28322] Federal Motor Vehicle Safety Standards; Lamps, Reflective Devices, and... part, the petitions for reconsideration of the December 4, 2007, final rule reorganizing Federal Motor...

A Study on Performance and Safety Tests of Defibrillator Equipment.

Science.gov (United States)

Tavakoli Golpaygani, A; Movahedi, M M; Reza, M

2017-12-01

Nowadays, more than 10,000 different types of medical devices can be found in hospitals. This way, medical electrical equipment is being employed in a wide variety of fields in medical sciences with different physiological effects and measurements. Hospitals and medical centers must ensure that their critical medical devices are safe, accurate, reliable and operational at the required level of performance. Defibrillators are critical resuscitation devices. The use of reliable defibirillators has led to more effective treatments and improved patient safety through better control and management of complications during Cardiopulmonary Resuscitation (CPR). The metrological reliability of twenty frequent use, manual defibrillators in use ten hospitals (4 private and 6 public) in one of the provinces of Iran according to international and national standards was evaluated. Quantitative analysis of control and instrument accuracy showed the amount of the obtained results in many units are critical which had less value over the standard limitations especially in devices with poor battery. For the accuracy of delivered energy analysis, only twelve units delivered acceptable output values and the precision in the output energy measurements especialy in weak battry condition, after activation of discharge alarm, were low. Obtained results indicate a need for new and severe regulations on periodic performance verifications and medical equipment quality control program especially for high risk instruments. It is also necessary to provide training courses on the fundumentals of operation and performane parameters for medical staff in the field of meterology in medicine and how one can get good accuracy results especially in high risk medical devices.

Safety management of software-based equipment

CERN Document Server

Boulanger, Jean-Louis

2013-01-01

A review of the principles of the safety of software-based equipment, this book begins by presenting the definition principles of safety objectives. It then moves on to show how it is possible to define a safety architecture (including redundancy, diversification, error-detection techniques) on the basis of safety objectives and how to identify objectives related to software programs. From software objectives, the authors present the different safety techniques (fault detection, redundancy and quality control). "Certifiable system" aspects are taken into account throughout the book. C

Safety rod driving device

International Nuclear Information System (INIS)

Murakami, Kiyonobu; Kurosaki, Akira.

1988-01-01

Purpose: To rapidly insert safety rods for a criticality experiment device into a reactor core container to stop the criticality reaction thereby prevent reactivity accidents. Constitution: A cylinder device having a safety rod as a cylinder rod attached with a piston at one end is constituted. The piston is elevated by pressurized air and attracted and fixed by an electromagnet which is a stationary device disposed at the upper portion of the cylinder. If the current supply to the electromagnet is disconnected, the safety rod constituting the cylinder rod is fallen together with the piston to the lower portion of the cylinder. Since the cylinder rod driving device has neither electrical motor nor driving screw as in the conventional device, necessary space can be reduced and the weight is decreased. In addition, since the inside of the nuclear reactor can easily be shielded completely from the external atmosphere, leakage of radioactive materials can be prevented. (Horiuchi, T.)

Safety of mechanical devices. Safety of automation systems

International Nuclear Information System (INIS)

Pahl, G.; Schweizer, G.; Kapp, K.

1985-01-01

The paper deals with the classic procedures of safety engineering in the sectors mechanical engineering, electrical and energy engineering, construction and transport, medicine technology and process technology. Particular stress is laid on the safety of automation systems, control technology, protection of mechanical devices, reactor safety, mechanical constructions, transport systems, railway signalling devices, road traffic and protection at work in chemical plans. (DG) [de

Guidelines for nuclear reactor equipments safety-analysis

International Nuclear Information System (INIS)

1978-01-01

The safety analysis in approving the applications for nuclear reactor constructions (or alterations) is performed by the Committee on Examination of Reactor Safety in accordance with various guidelines prescribed by the Atomic Energy Commission. In addition, the above Committee set forth its own regulations for the safety analysis on common problems among various types of nuclear reactors. This book has collected and edited those guidelines and regulations. It has two parts: Part I includes the guidelines issued to date by the Atomic Energy Commission: and Part II - regulations of the Committee. Part I has collected 8 categories of guidelines which relate to following matters: nuclear reactor sites analysis guidelines and standards for their applications; standard exposure dose of plutonium; nuclear ship operation guidelines; safety design analysis guidelines for light-water type, electricity generating nuclear reactor equipments; safety evaluation guidelines for emergency reactor core cooling system of light-water type power reactors; guidelines for exposure dose target values around light-water type electricity generating nuclear reactor equipments, and guidelines for evaluation of above target values; and meteorological guidelines for the safety analysis of electricity generating nuclear reactor equipments. Part II includes regulations of the Committee concerning - the fuel assembly used in boiling-water type and in pressurized-water type reactors; techniques of reactor core heat designs, etc. in boiling-water reactors; and others

Three equipment concepts for the Fusion Engineering Device

International Nuclear Information System (INIS)

Spampinato, P.T.; Masson, L.S.; Watts, K.D.; Grant, N.R.; Kuban, D.P.

1982-01-01

Maintenance equipment which is needed to remotely handle fusion device components is being conceptually developed for the Fusion Engineering Design Center. This will test the assumption that these equipment needs can be satisfied by present technology. In addition, the development of equipment conceptual designs will allow for cost estimates which have a much higher degree of certainty. Accurate equipment costs will be useful for assessments which trade off gains in availability as a function of increased investments in maintenance equipment

A Study on Performance and Safety Tests of Defibrillator Equipment

Directory of Open Access Journals (Sweden)

Tavakoli Golpaygani A.

2017-12-01

Full Text Available Introduction: Nowadays, more than 10,000 different types of medical devices can be found in hospitals. This way, medical electrical equipment is being employed in a wide variety of fields in medical sciences with different physiological effects and measurements. Hospitals and medical centers must ensure that their critical medical devices are safe, accurate, reliable and operational at the required level of performance. Defibrillators are critical resuscitation devices. The use of reliable defibirillators has led to more effective treatments and improved patient safety through better control and management of complications during Cardiopulmonary Resuscitation (CPR. Materials and Methods: The metrological reliability of twenty frequent use, manual defibrillators in use ten hospitals (4 private and 6 public in one of the provinces of Iran according to international and national standards was evaluated. Results: Quantitative analysis of control and instrument accuracy showed the amount of the obtained results in many units are critical which had less value over the standard limitations especially in devices with poor battery. For the accuracy of delivered energy analysis, only twelve units delivered acceptable output values and the precision in the output energy measurements especialy in weak battry condition, after activation of discharge alarm, were low. Conclusion: Obtained results indicate a need for new and severe regulations on periodic performance verifications and medical equipment quality control program especially for high risk instruments. It is also necessary to provide training courses on the fundumentals of operation and performane parameters for medical staff in the field of meterology in medicine and how one can get good accuracy results especially in high risk medical devices.

Safety lock for radiography exposure device

International Nuclear Information System (INIS)

Gaines, T.M.

1982-01-01

A safety lock for securing a radiation source in a radiography exposure device is disclosed. The safety lock prevents the inadvertent extension of the radiation source from the exposure device. The exposure devices are used extensively in industry for nondestructive testing of metal materials for defect. Unnecessary exposure of the radiographer or operator occurs not infrequently due to operator's error in believing that the radiation source is secured in the exposure device when, in fact, it is not. The present invention solves this problem of unnecessary exposure by releasingly trapping the radiation source in the shield of the radiography exposure device each time the source is retracted therein so that it is not inadvertently extended therefrom without the operator resetting the safety lock, thereby releasing the radiation source. Further, the safety lock includes an indicator which indicates when the source is trapped in the exposure device and also when it is untrapped. The safety lock is so designed that it does not prevent the return of the source to the trapped, shielded position in the exposure device. Further the safety lock includes a key means for locking the radiation source in the trapped position. The key means cannot be actuated until said radiation source is in said trapped position to further insure the safety lock cannot be inadvertently locked with the source untrapped and thus still extendable from the exposure device

30 CFR 250.806 - Safety and pollution prevention equipment quality assurance requirements.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 2 2010-07-01 2010-07-01 false Safety and pollution prevention equipment... Gas Production Safety Systems § 250.806 Safety and pollution prevention equipment quality assurance... install only certified safety and pollution prevention equipment (SPPE) in wells located on the OCS. SPPE...

46 CFR 189.60-10 - Cargo Ship Safety Equipment Certificate.

Science.gov (United States)

2010-10-01

... 46 Shipping 7 2010-10-01 2010-10-01 false Cargo Ship Safety Equipment Certificate. 189.60-10... VESSELS INSPECTION AND CERTIFICATION Certificates Under International Convention for Safety of Life at Sea, 1974 § 189.60-10 Cargo Ship Safety Equipment Certificate. (a) All vessels on an international voyage...

Design and construction of safety devices utilizing methods of measurement and control engineering

Energy Technology Data Exchange (ETDEWEB)

Greiner, B; Weidlich, S

1982-08-01

This article considers a proposed concept for the design and construction of measurement and control devices for the safety of chemical plants with the aim of preventing danger to persons and the environment and damage. Such measurement and control devices are generally employed when primary measures adopted for plant safety, such as safety valves, collection vessels, etc. are not applicable or insufficient by themselves. The concept regards the new sheet no. 3 of the VDI/VDE code draft 2180 ''Safety of chemical engineering plant'' and proposes a further subdivision of class A into safety classes A0, A1, and A2. Overall, it is possible, on the basis of the measures for raising the availability of measurement and control equipment which are presented in this article, to make selection appropriate to the potential danger involved. The proposed procedure should not, however, be regarded as a rigid scheme but rather as leading to a systematic view and supporting decisions resting on sound operating experience.

46 CFR 91.60-10 - Cargo Ship Safety Equipment Certificate.

Science.gov (United States)

2010-10-01

... 46 Shipping 4 2010-10-01 2010-10-01 false Cargo Ship Safety Equipment Certificate. 91.60-10... VESSELS INSPECTION AND CERTIFICATION Certificates Under International Convention for Safety of Life at Sea, 1974 § 91.60-10 Cargo Ship Safety Equipment Certificate. (a) All vessels on an international voyage are...

Hoisting appliances and fuel handling equipment at nuclear facilities

International Nuclear Information System (INIS)

1987-01-01

The guide is followed by the Finnish Centre for Radiation and Nuclear Safety (STUK) in regulating hoisting and handling equipment Class 3 at nuclear facilities. The guide is applied e.g. to the following equipment: reactor building overhead cranes, hoisting appliances at nuclear fuel storages, fuel handling machines, other hoisting appliances, which because of nuclear safety aspects are classified in Safety Class 3, and load-bearing devices connected with the above equipment, such as replaceable hoisting tools and auxiliary lifting devices. The regulating of hoisting and handling equipment comprises the following stages: handling of preliminary and final safety analysis reports, inspection of the construction plan, supervision of fabrication and construction inspection, and supervision of initial start-up and commissioning inspection

Development of superconducting equipment for fusion device

International Nuclear Information System (INIS)

Konno, Masayuki; Ueda, Toshio; Hiue, Hisaaki; Ohgushi, Kouzou

1993-01-01

At Fuji Electric Co., Ltd., the development of superconductivity was started from 1960, and superconducting equipment for fusion device has been developed for ten years. The superconducting equipment, which is developed for fusion by Fuji Electric Co., Ltd., are able to be grouped in three categories which are current lead, superconducting coil and superconducting bus-line. The current lead is an electrical feeder between a superconducting coil and an electrical power supply. The rated current of developed current lead is 30kA at continuous use and 100kA at short time use respectively. The advanced disk type coil is developed for the toroidal field coil and some coils are developed for critical current measurement. Superconductor is applied to the superconducting bus-line between the superconducting coils and the current leads, and the bus-line is being developed for the Large Helical Device. This report describes an abstract of these equipment. (author)

Experience of safety and performance improvement for fuel handling equipment

International Nuclear Information System (INIS)

Gyoon Chang, Sang; Hee Lee, Dae

2014-01-01

The purpose of this study is to provide experience of safety and performance improvement of fuel handling equipment for nuclear power plants in Korea. The fuel handling equipment, which is used as an important part of critical processes during the refueling outage, has been improved to enhance safety and to optimize fuel handling procedures. Results of data measured during the fuel reloading are incorporated into design changes. The safety and performance improvement for fuel handling equipment could be achieved by simply modifying the components and improving the interlock system. The experience provided in this study can be useful lessons for further improvement of the fuel handling equipment. (authors)

Control of Nuclear Materials and Special Equipment (Nuclear Safety Regulations)

International Nuclear Information System (INIS)

Cizmek, A.; Prah, M.; Medakovic, S.; Ilijas, B.

2008-01-01

Based on Nuclear Safety Act (OG 173/03) the State Office for Nuclear Safety (SONS) in 2008 adopted beside Ordinance on performing nuclear activities (OG 74/06) and Ordinance on special conditions for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety (OG 74/06) the new Ordinance on the control of nuclear material and special equipment (OG 15/08). Ordinance on the control of nuclear material and special equipment lays down the list of nuclear materials and special equipment as well as of nuclear activities covered by the system of control of production of special equipment and non-nuclear material, the procedure for notifying the intention to and filing the application for a license to carry out nuclear activities, and the format and contents of the forms for doing so. This Ordinance also lays down the manner in which nuclear material records have to be kept, the procedure for notifying the State administration organization (regulatory body) responsible for nuclear safety by the nuclear material user, and the keeping of registers of nuclear activities, nuclear material and special equipment by the State administration organization (regulatory body) responsible for nuclear safety, as well as the form and content of official nuclear safety inspector identification card and badge.(author)

A preliminary design of mechanical device on industrial digital radiography equipment design

International Nuclear Information System (INIS)

Nur Khasan; Samuel Praptoyo

2015-01-01

A preliminary design of mechanical device on industrial digital radiography equipment has been done. this design is intended as a basis for the manufacture of complete facilities for the realization a prototype on industrial digital radiography equipment. the design and construction were carried out by paying attention to the general configuration of the basic design in which its mechanical design has several components with specific dimensions and heavy mass. this design consist of a main frame holder, flat panel detector support and hydraulic hand stacker for mounting the x-ray machine. this mechanical device design will then be fabricated to facilitate and assist work of digital radiographic retrieval. computer application programs sketch-up is used to draw this design and the analysis stress of autodesk inventor to analysis the strength construction design. the results of this design are the configuration drawing, sketch drawings of construction and the safety factor of construction design with a minimum value of 2.39 as well as a maximum value of 15 when to be simulated by the load 500 Kg which is 4 times of total workload. (author)

Management information system of medical equipment using mobile devices

Science.gov (United States)

Núñez, C.; Castro, D.

2011-09-01

The large numbers of technologies currently incorporated into mobile devices transform them into excellent tools for capture and to manage the information, because of the increasing computing power and storage that allow to add many miscellaneous applications. In order to obtain benefits of these technologies, in the biomedical engineering field, it was developed a mobile information system for medical equipment management. The central platform for the system it's a mobile phone, which by a connection with a web server, it's capable to send and receive information relative to any medical equipment. Decoding a type of barcodes, known as QR-Codes, the management process is simplified and improved. These barcodes identified the medical equipments in a database, when these codes are photographed and decoded with the mobile device, you can access to relevant information about the medical equipment in question. This Project in it's actual state is a basic support tool for the maintenance of medical equipment. It is also a modern alternative, competitive and economic in the actual market.

Staff report on the environmental qualification of safety-related electrical equipment

International Nuclear Information System (INIS)

1977-12-01

The current NRC safety review process for nuclear power plants includes criteria related to the qualification of certain electrical equipment. These criteria require that electrical equipment important to safety must be qualified to function in the environment that might result from various accident conditions. Although such criteria have been applied since the early days of commercial nuclear power, the details of these criteria have been changed over the years. The evolution of environmental qualification of safety-related electrical equipment is described in Appendix A

Hoisting appliances and fuel handling equipment at nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

NONE

1988-12-31

The guide is followed by the Finnish Centre for Radiation and Nuclear Safety (STUK) in regulating hoisting and handling equipment Class 3 at nuclear facilities. The guide is applied e.g. to the following equipment: reactor building overhead cranes, hoisting appliances at nuclear fuel storages, fuel handling machines, other hoisting appliances, which because of nuclear safety aspects are classified in Safety Class 3, and load-bearing devices connected with the above equipment, such as replaceable hoisting tools and auxiliary lifting devices. The regulating of hoisting and handling equipment comprises the following stages: handling of preliminary and final safety analysis reports, inspection of the construction plan, supervision of fabrication and construction inspection, and supervision of initial start-up and commissioning inspection. 36 refs. Translation. The original text is published under the same guide number. The guide is valid from 5 January 1987 and will be in force until further notice.

1E Qualification of Electrical Equipment - Requirement for Safety Nuclear Power Plants

International Nuclear Information System (INIS)

Geambasu, C.; Segarceanu, D.; Albu, J.

2002-01-01

The paper presents the qualification methods of the safety related equipment according to the safety class 1E. There are presented the qualification principles, procedure and documents, emphasis being laid on the qualification approach by type tests. This approach assumes the equipment test under both normal and accident conditions (design basis events) simulating the operational conditions and covers the largest part of electrical equipment from a nuclear power plant.The safety related equipment is to be qualified is subjected to a sequential test that will be detailed in the paper. (author)

Nuclear safety regulation on nuclear safety equipment activities in relation to human and organizational factors

International Nuclear Information System (INIS)

Li Tianshu

2013-01-01

Based on years of knowledge in nuclear safety supervision and experience of investigating and dealing with violation events in repair welding of DFHM, this paper analyzes major faults in manufacturing and maintaining activities of nuclear safety equipment in relation to human and organizational factors. It could be deducted that human and organizational factors has definitely become key features in the development of nuclear energy and technology. Some feasible measures to reinforce supervision on nuclear safety equipment activities have also been proposed. (author)

[Implementation of safety devices: biological accident prevention].

Science.gov (United States)

Catalán Gómez, M Teresa; Sol Vidiella, Josep; Castellà Castellà, Manel; Castells Bo, Carolina; Losada Pla, Nuria; Espuny, Javier Lluís

2010-04-01

Accidental exposures to blood and biological material were the most frequent and potentially serious accidents in healthcare workers, reported in the Prevention of Occupational Risks Unit within 2002. Evaluate the biological percutaneous accidents decrease after a progressive introduction of safety devices. Biological accidents produced between 2.002 and 2.006 were analyzed and reported by the injured healthcare workers to the Level 2b Hospital Prevention of Occupational Risk Unit with 238 beds and 750 employees. The key of the study was the safety devices (peripheral i.v. catheter, needleless i.v. access device and capillary blood collection lancet). Within 2002, 54 percutaneous biological accidents were registered and 19 in 2006, that represents a 64.8% decreased. There has been no safety devices accident reported involving these material. Accidents registered during the implantation period occurred because safety devices were not used at that time. Safety devices have proven to be effective in reducing needle stick percutaneous accidents, so that they are a good choice in the primary prevention of biological accidents contact.

Stakeholder challenges in purchasing medical devices for patient safety.

Science.gov (United States)

Hinrichs, Saba; Dickerson, Terry; Clarkson, John

2013-03-01

This study identifies the stakeholders who have a role in medical device purchasing within the wider system of health-care delivery and reports on their particular challenges to promote patient safety during purchasing decisions. Data was collected through observational work, participatory workshops, and semi-structured qualitative interviews, which were analyzed and coded. The study takes a systems-based and engineering design approach to the study. Five hospitals took part in this study, and the participants included maintenance, training, clinical end-users, finance, and risk departments. The main stakeholders for purchasing were identified to be staff from clinical engineering (Maintenance), device users (Clinical), device trainers (Training), and clinical governance for analyzing incidents involving devices (Risk). These stakeholders display varied characteristics in terms of interpretation of their own roles, competencies for selecting devices, awareness and use of resources for purchasing devices, and attitudes toward the purchasing process. The role of "clinical engineering" is seen by these stakeholders to be critical in mediating between training, technical, and financial stakeholders but not always recognized in practice. The findings show that many device purchasing decisions are tackled in isolation, which is not optimal for decisions requiring knowledge that is currently distributed among different people within different departments. The challenges expressed relate to the wider system of care and equipment management, calling for a more systemic view of purchasing for medical devices.

A study on developpement of guideline on writing technical document for electrical medical devices: Dental x-ray equipment

Energy Technology Data Exchange (ETDEWEB)

Lee, Seung Youl; Kim, Jae Ryang; Lee, Jun Ho; Park, Chang Won [Division of Medical Device Research, National Institute of Food and Drug Safety Evaluation, Mnistry of Food and Drug Safety (Korea, Republic of)

2016-12-15

Due to recent population aging, the number of check-up for senior citizens has increased steadily. According to this trend, the market size of dental X-ray equipment and the number of approval and review for these devices have simultaneously increased. The technical document of medical device is required for approval and review for medical device, and medical device companies needs to have work comprehension and expertise, as the document needs to include the overall contents such as performances, test criteria, etc.. Yet, since most of domestic manufacturers or importers of medical devices are small businesses, it is difficult for them to recruit professional manpower for approval of medical devices, and submission of inaccurate technical documents has increased. These problems lead to delay of the approval process and to difficulties in quick entering into the market. Especially, the Ministry of Food and Drug safety (MFDS) standards of a dental extra-oral X-ray equipment, a dental intra-oral X-ray equipment, an arm-type computed tomography, and a portable X-ray system have been recently enacted or not. this guideline of dental X-ray equipment adjusting revised standards was developed to help relative companies and reviewers. For this study, first, the methods to write technical document have been reviewed with revised international and domestic regulations and system. Second, the domestic and foreign market status of each item has been surveyed and analyzed. Third, the contents of technical documents already approved by MFDS have been analyzed to select the correct example, test items, criteria, and methods. Finally, the guideline has been developed based on international and domestic regulation, through close review of a consultative body composed of academic, industrial, research institute and government experts.

A study on developpement of guideline on writing technical document for electrical medical devices: Dental x-ray equipment

International Nuclear Information System (INIS)

Lee, Seung Youl; Kim, Jae Ryang; Lee, Jun Ho; Park, Chang Won

2016-01-01

Due to recent population aging, the number of check-up for senior citizens has increased steadily. According to this trend, the market size of dental X-ray equipment and the number of approval and review for these devices have simultaneously increased. The technical document of medical device is required for approval and review for medical device, and medical device companies needs to have work comprehension and expertise, as the document needs to include the overall contents such as performances, test criteria, etc.. Yet, since most of domestic manufacturers or importers of medical devices are small businesses, it is difficult for them to recruit professional manpower for approval of medical devices, and submission of inaccurate technical documents has increased. These problems lead to delay of the approval process and to difficulties in quick entering into the market. Especially, the Ministry of Food and Drug safety (MFDS) standards of a dental extra-oral X-ray equipment, a dental intra-oral X-ray equipment, an arm-type computed tomography, and a portable X-ray system have been recently enacted or not. this guideline of dental X-ray equipment adjusting revised standards was developed to help relative companies and reviewers. For this study, first, the methods to write technical document have been reviewed with revised international and domestic regulations and system. Second, the domestic and foreign market status of each item has been surveyed and analyzed. Third, the contents of technical documents already approved by MFDS have been analyzed to select the correct example, test items, criteria, and methods. Finally, the guideline has been developed based on international and domestic regulation, through close review of a consultative body composed of academic, industrial, research institute and government experts

The french safety approach regarding equipment qualification

International Nuclear Information System (INIS)

Jalouneix, J.; Deletre, G.; Henry, J.Y.; Rousseau, L.

1989-10-01

The qualification of the equipment, used in France on nuclear reactors and reactor components, is discussed. The approach on safety involves the qualification of mechanical and electrical components, under operating and under seismic conditions. The principles of the qualification program and the list of the equipment concerned, are given. The conditions in which qualification tests are performed and the methods applied, are summarized. The actions for preserving the qualification procedures, are considered

Safety device for nuclear reactor

International Nuclear Information System (INIS)

Jacquelin, Roland.

1977-01-01

This invention relates to a safety device for a nuclear reactor, particularly a liquid metal (generally sodium) cooled fast reactor. This safety device includes an absorbing element with a support head connected by a disconnectable connector formed by the armature of an electromagnet at the end of an axially mobile vertical control rod. This connection is so designed that in the event of it becoming disconnected, the absorbing element gravity slides in a passage through the reactor core into an open container [fr

Information booklet on personal protective equipment: eye and face protection

International Nuclear Information System (INIS)

1992-01-01

In all work places where hazards of various kinds are present and the same cannot be totally controlled by engineering methods, suitable personal protective equipment (PPE) shall be used. There are several types of eye and face protection devices available in the market and it is important that employees use the proper type for the particular job. The main classes of eye and face protection devices required for the industrial operations are as follows: (a) eye protection devices which includes: (i) safety goggles (ii) safety spectacles (iii) safety clipons and eye and face protection devices which are (i) eye shield, (ii) face shield, (iii) wire mesh screen guard. Guide lines for selecting appropriate ear and face protection equipment for nuclear installations are given. (M.K.V.). 4 annexures, 1 appendix

Design review report for modifications to RMCS safety class equipment

International Nuclear Information System (INIS)

Corbett, J.E.

1997-01-01

This report documents the completion of the formal design review for modifications to the Rotary Mode Core Sampling (RMCS) safety class equipment. These modifications are intended to support core sampling operations in waste tanks requiring flammable gas controls. The objective of this review was to approve the Engineering Change Notices affecting safety class equipment used in the RMCS system. The conclusion reached by the review committee was that these changes are acceptable

Design review report for modifications to RMCS safety class equipment

Energy Technology Data Exchange (ETDEWEB)

Corbett, J.E.

1997-05-30

This report documents the completion of the formal design review for modifications to the Rotary Mode Core Sampling (RMCS) safety class equipment. These modifications are intended to support core sampling operations in waste tanks requiring flammable gas controls. The objective of this review was to approve the Engineering Change Notices affecting safety class equipment used in the RMCS system. The conclusion reached by the review committee was that these changes are acceptable.

Device for diagnoising abnormalities of equipments

International Nuclear Information System (INIS)

Nakano, Hiroshi.

1986-01-01

Purpose: To measure the collision energy easily and at high accuracy by applying impact shocks at known collision energy from a simulated acoustic wave generator and using the generated acoustic signal as reference data. Constitution: A plurality of acoustic detectors are attached to the surface of a nuclear reactor pressure vessel. These acoustic detectors are connected respectively to an abnormality diagnosis device for equipments. Then, when metal obstacles collide against the inner surface of the reactor pressure vessel, acoustic signals generated upon collision are detected by the acoustic detectors and acoustic information thus obtained from the acoustic detectors determines the colliding position of the metal obstacles by means of the abnormality diagnosis device and then the collision energy is measured. In this case, by applying impact shocks at known collision energy near the colliding position of metal obstacles determined by the abnormality diagnosis device, collision energy can be determined at a higher accuracy. (Kawakami, Y.)

An evaluation of sharp safety blood evacuation devices.

Science.gov (United States)

Ford, Joanna; Phillips, Peter

This article describes an evaluation of three sharp safety blood evacuation devices in seven Welsh NHS boards and the Welsh Blood Service. Products consisted of two phlebotomy needles possessing safety shields and one phlebotomy device with wings, tubing and a retractable needle. The device companies provided the devices and appropriate training. Participating healthcare workers used the safety device instead of the conventional device to sample blood during the evaluation period and each type of device was evaluated in random order. Participants filled in a questionnaire for each type of device and then a further questionnaire comparing the two shielded evacuation needles with each other Results showed that responses to all three products were fairly positive, although each device was not liked by everyone who used it. When the two shielded evacuation devices were compared with each other, most users preferred the device with the shield positioned directly above the needle to the device with the shield at the side. However, in laboratory tests, the preferred device produced more fluid splatter than the other shielded device on activation.

Safety equipment list for 241-C-106 waste retrieval, Project W-320: Revision 1

International Nuclear Information System (INIS)

Conner, J.C.

1994-01-01

The goals of the C-106 sluicing operation are: (1) to stabilize the tank by reducing the heat load in the tank to less than 42 MJ/hr (40,000 Btu/hour), and (2) to initiate demonstration of single-shell tank (SST) retrieval technology. The purpose of this supporting document (SD) is as follows: (1) to provide safety classifications for items (systems, structures, equipment, components, or parts) for the waste retrieval sluicing system (WRSS), and (2) to document and methodology used to develop safety classifications. Appropriate references are made with regard to use of existing systems, structures, equipments, components, and parts for C-106 single-shell transfer tank located in the C Tank Farm, and 241-AY-102 (AY-102) double shell receiver tanks (DST) located in the Aging Waste Facility (AWF). The Waste Retrieval Sluicing System consists of two transfer lines that would connect the two tanks, one to carry the sluiced waste slurry to AY-102, and the other to return the supernatant liquid to C-106. The supernatant, or alternate fluid, will be used to mobilize waste in C-106 for the sluicing process. The equipment necessary for the WRSS include pumps in each tank, sluicers to direct the supernatant stream in C-106, a slurry distributor in AY-102, HVAC for C-106, instrumentation and control devices, and other existing components as required

Regulatory Activities on Civil Nuclear Safety Equipment in China

International Nuclear Information System (INIS)

Gaoshang, Lu; Choi, Kwang Sik

2011-01-01

It is stipulated in IAEA Fundamental Safety Principles (SF1) that the fundamental safety objective is to protect people and the environment from harmful effects of ionizing radiation. The fundamental safety objective applies for all facilities and activities and for all stages over the lifetime of a facility or radiation source, including planning, sitting, design, manufacturing, construction, commissioning and operation, as well as decommissioning and closure. So, according to the requirement, the related activities such as design, manufacturing, installation and non-destructive test that conducted on civil nuclear equipment should be well controlled by the vendors, the owner of the nuclear power plants and the regulatory body. To insure the quality of those equipment, Chinese government had taken a series of measures to regulate the related activities on them

Benefits of Digital Equipment Generic Qualification Activities

International Nuclear Information System (INIS)

Thomas, James E.; Steiman, Samuel C.

2002-01-01

As a result of nuclear power plant instrumentation and control obsolescence issues, there have been numerous activities during recent years relating to the qualification of digital equipment. Some of these activities have been 'generic' in nature in that the qualification was not limited to plant specific applications, but was intended to cover a broad base of potential applications of the digital equipment. These generic qualifications have been funded by equipment manufacturers and by utility groups and organizations. The generic activities sponsored by the Electric Power Research Institute (EPRI) have been pilot projects for an overall generic qualification approach. The primary benefit resulting from the generic qualification work to date is that a number of digital platforms and digital devices are now available for use in various nuclear safety-related applications. Many of the tests and evaluations necessary to support plant specific applications have been completed. The amount of data and documentation that each utility must develop on a case by case basis has been significantly reduced. There are also a number of additional benefits resulting from these industry efforts. The challenges and difficulties in qualifying digital equipment for safety-related applications are now more clearly understood. EPRI has published a lessons learned document (EPRI Report 1001452, Generic Qualification of Commercial Grade Digital Devices: Lessons Learned from Initial Pilots, which covers several different qualification areas, including device selection, project planning, vendor surveys and design reviews, and electromagnetic compatibility (EMC) qualification. Application of the experience and lessons learned from the EPRI pilot activities should help reduce the effort and cost required for future qualification work. Most generic qualification activities for commercial equipment have been conducted using the approach of EPRI TR-106439, Guideline on Evaluation and Acceptance

Safety syringes and anti-needlestick devices in orthopaedic surgery.

Science.gov (United States)

Sibbitt, Wilmer L; Band, Philip A; Kettwich, Lawrence G; Sibbitt, Cristina R; Sibbitt, Lori J; Bankhurst, Arthur D

2011-09-07

The American Academy of Orthopaedic Surgery (AAOS), The Joint Commission, the Occupational Safety and Health Administration (OSHA), and the Needlestick Safety and Prevention Act encourage the integration of safety-engineered devices to prevent needlestick injuries to health-care workers and patients. We hypothesized that safety syringes and needles could be used in outpatient orthopaedic injection and aspiration procedures. The study investigated the orthopaedic uses and procedural idiosyncrasies of safety-engineered devices, including (1) four safety needles (Eclipse, SafetyGlide, SurGuard, and Magellan), (2) a mechanical safety syringe (RPD), (3) two automatic retractable syringes (Integra, VanishPoint), (4) three manual retractable syringes (Procedur-SF, Baksnap, Invirosnap), and (5) three shielded syringes (Safety-Lok, Monoject, and Digitally Activated Shielded [DAS] Syringe). The devices were first tested ex vivo, and then 1300 devices were used for 425 subjects undergoing outpatient arthrocentesis, intra-articular injections, local anesthesia, aspiration biopsy, and ultrasound-guided procedures. During the clinical observation, there were no accidental needlesticks (0 needlesticks per 1300 devices). Safety needles could be successfully used on a Luer syringe but were limited to ≤1.5 in (≤3.81 cm) in length and the shield could interfere with sonography. The mechanical safety syringes functioned well in all orthopaedic procedures. Automatic retractable syringes were too small for arthrocentesis of the knee, and the plunger blew out and prematurely collapsed with high-pressure injections. The manual retractable syringes and shielded syringes could be used with conventional needles for most orthopaedic procedures. The most effective and reliable safety devices for orthopaedic syringe procedures are shielded safety needles, mechanical syringes, manual retractable syringes, and shielded syringes, but not automatic retractable syringes. Even when adopting

Safety for Compressed Gas and Air Equipment. Module SH-26. Safety and Health.

Science.gov (United States)

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

This student module on safety for compressed gas and air equipment is one of 50 modules concerned with job safety and health. This module presents technical data about commonly used gases and stresses the procedures necessary for safe handling of compressed gases. Following the introduction, 14 objectives (each keyed to a page in the text) the…

30 CFR 57.9330 - Clearance for surface equipment.

Science.gov (United States)

2010-07-01

... NONMETAL MINE SAFETY AND HEALTH SAFETY AND HEALTH STANDARDS-UNDERGROUND METAL AND NONMETAL MINES Loading, Hauling, and Dumping Safety Devices, Provisions, and Procedures for Roadways, Railroads, and Loading and... the farthest projection of moving railroad equipment shall be provided on at least one side of the...

The effect of using road safety equipment and systems and ...

African Journals Online (AJOL)

The effect of using road safety equipment and systems and determine their role on ... traffic control equipment situation and by multi-criteria weighting systems AHP ... The results have shown that indices median, lighting and panel type and the ...

Safety in Cryogenics – Safety device sizing

CERN Multimedia

CERN. Geneva

2016-01-01

The calculation is separated in three operations: o The estimation of the loads arriving on the component to protect, o The calculation of the mass flow to evacuate, o And the sizing of the safety device.

A safety equipment list for rotary mode core sampling systems operation in single shell flammable gas tanks

International Nuclear Information System (INIS)

SMALLEY, J.L.

1999-01-01

This document identifies all interim safety equipment to be used for rotary mode core sampling of single-shell flammable gas tanks utilizing Rotary Mode Core Sampling systems (RMCS). This document provides the safety equipment for RMCS trucks HO-68K-4600, HO-68K-4647, trucks three and four respectively, and associated equipment. It is not intended to replace or supersede WHC-SD-WM-SEL-023, (Kelly 1991), or WHC-SD-WM-SEL-032, (Corbett 1994), which classifies 80-68K-4344 and HO-68K-4345 respectively. The term ''safety equipment'' refers to safety class (SC) and safety significant (SS) equipment, where equipment refers to structures, systems and components (SSC's). The identification of safety equipment in this document is based on the credited design safety features and analysis contained in the Authorization Basis (AB) for rotary mode core sampling operations in single-shell flammable gas tanks. This is an interim safety classification since the AB is interim. This document will be updated to reflect the final RMCS equipment safety classification designations upon completion of a final AB which will be implemented with the release of the Final Safety Analysis Report (FSAR)

Safety systems I/C equipment reliability analyses of the Kozloduy NPP units 3 and 4

Energy Technology Data Exchange (ETDEWEB)

Halev, G; Christov, N [Risk Engineering Ltd., Sofia (Bulgaria)

1996-12-31

The purpose of the analysis is to assess the safety systems I/C equipment reliability. The assessment includes: quantification of the safety systems unavailability due to component failures; definition of the minimal cut sets leading to the analysed safety systems failure; quantification of the I/C equipment importance measures of the dominant contribution components. The safety systems I/C equipment reliability has been analysed using PSAPACK (a code for probabilistic safety assessment). Fault trees for the following safety systems of the Kozloduy-3 and Kozloduy-4 reactors have been constructed: neutron flow control equipment, reactor protection system, main coolant pumps, pressurizer safety valves `Sempell`, steam dump systems, spray system, low pressure injection system, emergency feeding water system, essential service water system. THree separate reports have been issued containing the performed analyses and results. 1 ref.

IEEE standard for design qualification of safety systems equipment used in nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1980-01-01

This standard is written to serve as a general standard for qualification of all types of safety systems equipment, mechanical and instrumentation as well as electrical. It also establishes principles and procedures to be followed in preparing specific safety systems equipment standards. Guidance for qualifying specific safety systems equipment may be found in various specific equipment qualification standards that are now available or are being prepared. It is required that safety systems equipment in nuclear power generating stations meet or exceed its performance requirements throughout its installed life. This is accomplished by a disciplined program of design qualification and quality assurance of design, production, installation, maintenance and surveillance. This standard is for the design qualification section of the program only. Design qualification is intended to demonstrate the capability of the equipment design to perform its safety function(s) over the expected range of normal, abnormal, design basis event, post design basis event, and in-service test conditions. Inherent to design qualification is the requirement for demonstration, within limitations afforded by established technical state-of-the-art, that in-service aging throughout the qualified life established for the equipment will not degrade safety systems equipment from its original design condition to the point where it cannot perform its required safety function(s), upon demand. The above requirement reflects the primary role of design qualification to provide reasonable assurance that design- and age-related common failure modes will not occur during performance of safety function(s) under postulated service conditions

38 CFR 17.155 - Minimum standards of safety and quality for automotive adaptive equipment.

Science.gov (United States)

2010-07-01

... safety and quality for automotive adaptive equipment. 17.155 Section 17.155 Pensions, Bonuses, and... Minimum standards of safety and quality for automotive adaptive equipment. (a) The Under Secretary for... officials that it meets implicit standards of safety and quality adopted by the industry or as later...

System constitution of plasma high frequency heating device and element equipment

International Nuclear Information System (INIS)

Nagashima, Takashi

1988-01-01

On the high frequency heating device used for nuclear fusion experiment, the system constitution and the main items of development for the element equipment are described. As for the high frequency heating device, large technical progress was observed in the past 10 years as the second stage heating for tokamaks and one of the main means of current drive. At present, three frequency zones are regarded as promising for plasma high frequency heating in large nuclear fusion devices, and the experiment of 10 MW class is in progress at JT-60, JET and so on. There are electron cyclotron heating, lower hybrid resonance frequency heating and ion cyclotron range of frquency heating. The basic constitution of these heating devices includes a high frequency source, a transmission system, a connection system, and a common system for control, cooling, record and others. The ECH device using gyrotrons of several tens GHz, the LHRF heating device using large power klystrons up to several GHz and the ICRF heating device up to 200 MHz are briefly explained. The main element equipments composing the high frequency heating systems of several tens MW are discussed. (Kako, I.)

Safety of nursing staff and determinants of adherence to personal protective equipment.

Science.gov (United States)

Neves, Heliny Carneiro Cunha; Souza, Adenícia Custódia Silva e; Medeiros, Marcelo; Munari, Denize Bouttelet; Ribeiro, Luana Cássia Miranda; Tipple, Anaclara Ferreira Veiga

2011-01-01

A qualitative study conducted in a teaching hospital with 15 nursing professionals. Attempted to analyze the reasons, attitudes and beliefs of nursing staff regarding adherence to personal protective equipment. Data were collected through focus groups, analyzed by the method of interpretation of meanings, considering Rosenstock's model of health beliefs as a reference framework. Data revealed two themes: Occupational safety and Interpersonal Relationship. We identified several barriers that interfere in matters of safety and personal protective equipment, such as communication, work overload, physical structure, accessibility of protective equipment and organizational and management aspects. Adherence to personal protective equipment is determined by the context experienced in the workplace, as well as by individual values and beliefs, but the decision to use the personal protective equipment is individual.

Auxetic foam for snowsport safety devices

OpenAIRE

Allen, Tom; Duncan, Olly; Foster, Leon; Senior, Terry; Zampieri, Davide; Edeh, Victor; Alderson, Andrew

2017-01-01

Skiing and snowboarding are popular snow-sports with inherent risk of injury. There is potential to reduce the prevalence of injuries by improving and implementing snow-sport safety devices with the application of advanced materials. This paper investigates the application of auxetic foam to snow-sport safety devices. Composite pads - consisting of foam covered with a semi-rigid shell - were investigated as a simple model of body armour and a large 70 x 355 x 355 mm auxetic foam sample was fa...

Electronic equipment and software for device 'FAZA'

International Nuclear Information System (INIS)

Avdeev, S.P.; Karnaukhov, V.A.; Kuznetsov, V.D.; Petrov, L.A.; Oeschler, H.; Lips, F.; Bart, R.

1992-01-01

Electronic equipment and software for the device FAZA are described. The device, designed for studying the nuclear multifragmentation process, consists of 5 time-of-flight telescopes, a position-sensitive avalanche chamber and 58 PM tubes. The time resolution of the time-of-flight telescopes is 0.5 ns, which allows a velocity resolution of 1.5%. The spatial resolution of the large avalanche counter is 4 mm, which allows angular resolution of 1 deg. Analogue signals from each PM tube come to two ADCs, to which strobes are supplied with a 400 ns shift. It allows codes corresponding to Cherenkov radiation and deexcitation of CsJ(Tl) to be distinguished in a two-dimensional plot. 8 refs.; 2 figs

Pump safety device

International Nuclear Information System (INIS)

Timmermans, Francis; Vandervorst, Jean.

1981-01-01

Safety device for longitudinally leak proofing the shaft of a pump in the event of the fracture of the dynamic seal separating the pump fluid high pressure chamber from the low pressure chamber. It is designed for fitting to the primary pumps of nuclear reactors. It includes a hollow cyclindrical piston located coaxially around the pump shaft and normally housed in a chamber provided for this purpose in the fixed housing of the dynamic seal, and means for moving this piston coaxially so as to compress a safety O ring between the shaft and the piston in the event of the dynamic seal failing [fr

Inquiry about the uses of special equipment (CT equipment, angiography systems, mammography devices, screens)

International Nuclear Information System (INIS)

Schwager, P.; Stieve, F.E.

1986-01-01

There are at least 1100 special devices in medical establishment in Bavaria which require special inspection and surveillance with regard to quality of equipment and radiation protection. In addition, there are at least 53 tomographs available for operation, and at least 120 installed X-ray screens. These devices need special approval testing and quality control services as they contribute a very significant amount of the medically indicated radiation exposure of the population. Appropriate measures are explained that can be applied in order to reduce the medical radiation exposure to an optimum. (orig.) [de

Navigation Tools and Equipment and How They Have Improved Aviation Safety

OpenAIRE

Sulaiman D. S Alsahli FadalahassanALfadala

2017-01-01

This paper highlights the impact of navigation tools and equipment, such as the GPS, navigation radar, and other communications tools, which aid in ensuring aviation safety. It emphasizes the need for aviation safety and how these navigation methods are of great help to reduce the hazards and clearly indicate the problems related to the aircraft, aircraft traffic management, weather disturbances, among others. It also recommends how these tools and equipment must be further developed to promo...

Nuclear power plants. Electrical equipment of the safety system. Qualification

International Nuclear Information System (INIS)

2001-01-01

This International Standard applies to electrical parts of safety systems employed at nuclear power plants, including components and equipment of any interface whose failure could affect unfavourably properties of the safety system. The standard also applies to non-electrical safety-related interfaces. Furthermore, the standard describes the generic process of qualification certification procedures and methods of qualification testing and related documentation. (P.A.)

A safety equipment list for rotary mode core sampling systems operation in single shell flammable gas tanks; TOPICAL

International Nuclear Information System (INIS)

SMALLEY, J.L.

1999-01-01

This document identifies all interim safety equipment to be used for rotary mode core sampling of single-shell flammable gas tanks utilizing Rotary Mode Core Sampling systems (RMCS). This document provides the safety equipment for RMCS trucks HO-68K-4600, HO-68K-4647, trucks three and four respectively, and associated equipment. It is not intended to replace or supersede WHC-SD-WM-SEL-023, (Kelly 1991), or WHC-SD-WM-SEL-032, (Corbett 1994), which classifies 80-68K-4344 and HO-68K-4345 respectively. The term ''safety equipment'' refers to safety class (SC) and safety significant (SS) equipment, where equipment refers to structures, systems and components (SSC's). The identification of safety equipment in this document is based on the credited design safety features and analysis contained in the Authorization Basis (AB) for rotary mode core sampling operations in single-shell flammable gas tanks. This is an interim safety classification since the AB is interim. This document will be updated to reflect the final RMCS equipment safety classification designations upon completion of a final AB which will be implemented with the release of the Final Safety Analysis Report (FSAR)

Application of quality assurance program to safety related aging equipment or components

International Nuclear Information System (INIS)

Papaiya, N.C.

1990-01-01

This paper addresses how quality assurance programs and their criteria are applied to safety related and aging equipment or components used in commercial nuclear plant applications. The QA Programs referred to are 10CFR50 Appendix B and EPRI NP-5652. The QA programs as applicable are applied to equipment/component aging qualification, preventive maintenance, surveillance testing and procurement engineering. The intent of this paper is not the technical issues, methods and research of aging. The paper addresses QA program's application to age-related equipment or components in safety related applications. Quality Assurance Program 10CFR50 Appendix B applies to all safety related aging components or equipment related to the qualification program and associated preventive maintenance and surveillance testing programs. Quality Assurance involvement with procurement engineering for age-related commercial grade items supports EPRI NP-5652 and assures that the dedicated OGI is equal to the item purchased as a basic component to 10CFR50 Appendix B requirements

Impact of pre-conditioning on the qualification of safety-related equipment

International Nuclear Information System (INIS)

Isgro, J.R.

1982-01-01

This paper shares some recent experiences on the effects of preconditioning on the qualification of safety-related equipment not located in a harsh environment. Environmental and seismic qualification testing programs were conducted following the guidelines of IEEE 323-1974, IEEE 344-1975 and appropriate IEEE daughter standards, where available. The examples that follow will illustrate the degree of pre-conditioning of safety-related equipment qualified to the requirements of IEEE-323-1974, and its effect on the outcome of the qualification program

33 CFR 159.131 - Safety: Incinerating device.

Science.gov (United States)

2010-07-01

... (CONTINUED) POLLUTION MARINE SANITATION DEVICES Design, Construction, and Testing § 159.131 Safety.... Unitized incineration devices must completely burn to a dry, inert ash, a simultaneous defecation and...

A new approach to determine the environmental qualification requirements for the safety related equipment

International Nuclear Information System (INIS)

Hasnaoui, C.; Parent, G.

2000-01-01

The objective of the environmental qualification of safety related equipment is to ensure that the plant defense-in-depth is not compromised by common mode failures following design basis accidents with a harsh environment. A new approach based on safety functions has been developed to determine what safety-related equipment is required to function during and after a design basis accident, as well as their environmental qualification requirements. The main feature of this approach is to use auxiliary safety functions established from safety requirements as credited in the safety analyses. This approach is undertaken in three steps: identification of the auxiliary safety functions of each main safety function; determination of the main equipment groups required for each auxiliary safety function; and review of the safety analyses for design basis accidents in order to determine the credited auxiliary safety functions and their mission times for each accident scenario. Some of the benefits of the proposed approach for the determination of the safety environmental qualification requirements are: a systematic approach for the review of safety analyses based on a safety function check list, and the insurance, with the availability of the safety functions, that Gentilly-2 defense-in-depth would not be compromised by design basis accidents with a harsh environment. (author)

Standardization and improvement of safety for radioisotope equipped instruments

International Nuclear Information System (INIS)

Sumi, Tetsuo

1980-01-01

The safety for radioisotope-equipped instruments is considered. The one is the safety for the source assembly. The radioisotopes employed for radioisotope-equipped instruments are sealed sources which are used in the state of being contained in the enclosures. Many of the enclosures are provided with shutter mechanism for the purpose of emitting radiation only during the period required. If the possible troubles that might lead to the accidents are sampled out of the results of field operation of radiation instruments, and the safety measures for source enclosures are considered in connection with these troubles, it is no exaggeration to say that the safety for source enclosures has been maintained by preventing the critical accidents by the management of users and the cooperation of manufactures though there were the chance for investigating the safety in the common field and the establishment of JIS Z 4614 standard. Another consideration is concerned with the measures to improve the safety. No accident in the past never guarantees no accident in the future. Accumulation of experience is most effective for those measures, and the more experiences the better. It may be most effective that the manufacturers disclose their experiences each other from the wide outlook overcoming the barrier of trade secret. Fortunately, such consciousness has risen since a few years ago, and the investigation group is doing the works in the Japan Radioisotope Association. On the other hand, the reasonable revision of the radiation injury prevention law is desired. (Wakatsuki, Y.)

L-038: EPR-First Responders: Forces / safety equipment. Action Guides

International Nuclear Information System (INIS)

2011-01-01

This conference is about the actions carry out by the forces and the safety equipment in a radiological emergency. The security area, the victims, the hospitals, the police vehicles area, the safety cordon, the evacuation, the contamination level and the risk of life are important aspects to be considered by the first responders.

Clothing, equipment and devices for personnel protection: Its selection according to occupational risks

International Nuclear Information System (INIS)

1989-01-01

This Venezuelan standard establishes the selection of the type of clothing, equipment and devices for personnel protection, to be used by workers according to the occupational risk they deal with, in order to avoid or to reduce the factors that can, directly or indirectly, affect their physical integrity. For the risks not contemplated in this norm, the selection of the type of clothing, equipment and devices for personnel protection, must be done following the corresponding international standard [es

Pediatric interventional radiography equipment: safety considerations

International Nuclear Information System (INIS)

Strauss, Keith J.

2006-01-01

This paper discusses pediatric image quality and radiation dose considerations in state-of-the-art fluoroscopic imaging equipment. Although most fluoroscopes are capable of automatically providing good image quality on infants, toddlers, and small children, excessive radiation dose levels can result from design deficiencies of the imaging device or inappropriate configuration of the equipment's capabilities when imaging small body parts. Important design features and setup choices at installation and during the clinical use of the imaging device can improve image quality and reduce radiation exposure levels in pediatric patients. Pediatric radiologists and cardiologists, with the help of medical physicists, need to understand the issues involved in creating good image quality at reasonable pediatric patient doses. The control of radiographic technique factors by the generator of the imaging device must provide a large dynamic range of mAs values per exposure pulse during both fluoroscopy and image recording as a function of patient girth, which is the thickness of the patient in the posterior-anterior projection at the umbilicus (less than 10 cm to greater than 30 cm). The range of pulse widths must be limited to less than 10 ms in children to properly freeze patient motion. Variable rate pulsed fluoroscopy can be leveraged to reduce radiation dose to the patient and improve image quality. Three focal spots with nominal sizes of 0.3 mm to 1 mm are necessary on the pediatric unit. A second, lateral imaging plane might be necessary because of the child's limited tolerance of contrast medium. Spectral and spatial beam shaping can improve image quality while reducing the radiation dose. Finally, the level of entrance exposure to the image receptor of the fluoroscope as a function of operator choices, of added filter thickness, of selected pulse rate, of the selected field-of-view and of the patient girth all must be addressed at installation. (orig.)

Safety device of thermonuclear device

International Nuclear Information System (INIS)

Aoki, Isao; Ueda, Shuzo; Seki, Yasushi; Sakurai, Akiko; Kasahara, Fumio; Obara, Atsushi; Yamauchi, Michinori.

1997-01-01

The present invention provides a safety device against an event of intrusion of coolants in a vacuum vessel. Namely, a coolant supply system comprises cooling tubes for supplying coolants to main reactor structure components including a vacuum vessel. A detection means detects leakage of coolants in the vacuum vessel. A coolant supply control means controls the supply of coolants to the main reactor structural components based on the leakage detection signals of the detection means. A stagnated material discharging means discharges stagnated materials in the main reactor structural components caused by the leakage of coolants. The leakage of coolants (for example, water) in the vacuum vessel can thus be detected by the water detection device in the vacuum vessel. A control value of a coolant supply means is closed by the leakage detection signals. The supply of coolants to the main reactor structural components is restricted to suppress the leakage. The stagnated materials are discharged to a tank by way of a water draining valve. (I.S.)

Safety analysis report for packaging (onsite) decontaminated equipment self-container

International Nuclear Information System (INIS)

Boehnke, W.M.

1998-01-01

The purpose of this Safety Analysis Report for Packaging (SARP) is to demonstrate that specific decontaminated equipment can be safely used as its own self-container. As a Decontaminated Equipment Self-Container (also referred to as a self-container), no other packaging, such as a burial box, would be required to transport the equipment onsite. The self-container will consist of a piece of equipment or apparatus which has all readily removable interior contamination removed, all of its external openings sealed, and all external surfaces decontaminated to less than 2000 dpm/100 cm for gamma-emitting radionuclides and less than 220 dpm/100 CM2 for alpha-emitting radionuclides

Monitoring Device Safety in Interventional Cardiology

OpenAIRE

Matheny, Michael E.; Ohno-Machado, Lucila; Resnic, Frederic S.

2006-01-01

Objective: A variety of postmarketing surveillance strategies to monitor the safety of medical devices have been supported by the U.S. Food and Drug Administration, but there are few systems to automate surveillance. Our objective was to develop a system to perform real-time monitoring of safety data using a variety of process control techniques.

Safety considerations in the design of the fusion engineering device

International Nuclear Information System (INIS)

Barrett, R.J.

1983-01-01

Safety considerations play a significant role in the design of a near-term Fusion Engineering Device (FED). For the safety of the general public and the plant workers, the radiation environment caused by the reacting plasma and the potential release of tritium fuel are the dominant considerations. The U.S. Department of Energy (DOE) regulations and guidelines for radiation protection have been reviewed and are being applied to the device design. Direct radiation protection is provided by the device shield and the reactor building walls. Radiation from the activated device components and the tritium fuel is to be controlled with shielding, contamination control, and ventilation. The potential release of tritium from the plant has influenced the selection of reactor building and plant designs and specifications. The safety of the plant workers is affected primarily by the radiation from the activated device components and from plasma chamber debris. The highly activated device components make it necessary to design many of the maintenance activities in the reactor building for totally remote operation. The hot cell facility has evolved as a totally remote maintenance facility due to the high radiation levels of the device components. Safety considerations have had substantial impacts on the design of FED. Several examples of safety-related design impacts are discussed in the paper. Feasible solutions have been identified for all outstanding safety-related items, and additional optimization of these solutions is anticipated in future design studies

Failure diagnosis aiding device for plant equipment

International Nuclear Information System (INIS)

Uhara, Yoshihiko.

1990-01-01

The present invention intends to improve the efficiency of trouble shooting for equipments of industrial plants such as nuclear power plants. The device of the present invention comprises an intelligence base and an inference mechanism base. The intelligence base comprises a rule base, an information storing section having a part frame and a working frame and a user's frame. The parts frame contains the failure rate on every parts and data on related operations. The working frame contains the importance and frequency of working. The user's frame contains parameters showing the extent of user's skills. The rule base, the parts frame and the working frame can be selected in accordance with the extent of the user's skill in the inference mechanism. With such a constitution, failures can be checked with the intelligence base in accordance with the knowledges for the failures of the equipments and the extent of user's skill by way of the inference mechanism. (I.S.)

NIF special equipment construction health and safety plan

Energy Technology Data Exchange (ETDEWEB)

Sawicki, R.H.

1997-07-28

The purpose of this plan is to identify how the construction and deployment activities of the National Ignition Facility (NIF) Special Equipment (SE) will be safely executed. This plan includes an identification of (1) the safety-related responsibilities of the SE people and their interaction with other organizations involved; (2) safety related requirements, policies, and documentation; (3) a list of the potential hazards unique to SE systems and the mechanisms that will be implemented to control them to acceptable levels; (4) a summary of Environmental Safety and Health (ES&H) training requirements; and (5) requirements of contractor safety plans that will be developed and used by all SE contractors participating in site activities. This plan is a subsidiary document to the NIF Construction Safety Program (CSP) and is intended to compliment the requirements stated therein with additional details specific to the safety needs of the SE construction-related activities. If a conflict arises between these two documents, the CSP will supersede. It is important to note that this plan does not list all of the potential hazards and their controls because the design and safety analysis process is still ongoing. Additional safety issues win be addressed in the Final Safety Analysis Report, Operational Safety Procedures (OSPs), and other plans and procedures as described in Section 3.0 of this plan.

NIF special equipment construction health and safety plan

International Nuclear Information System (INIS)

Sawicki, R.H.

1997-01-01

The purpose of this plan is to identify how the construction and deployment activities of the National Ignition Facility (NIF) Special Equipment (SE) will be safely executed. This plan includes an identification of (1) the safety-related responsibilities of the SE people and their interaction with other organizations involved; (2) safety related requirements, policies, and documentation; (3) a list of the potential hazards unique to SE systems and the mechanisms that will be implemented to control them to acceptable levels; (4) a summary of Environmental Safety and Health (ES ampersand H) training requirements; and (5) requirements of contractor safety plans that will be developed and used by all SE contractors participating in site activities. This plan is a subsidiary document to the NIF Construction Safety Program (CSP) and is intended to compliment the requirements stated therein with additional details specific to the safety needs of the SE construction-related activities. If a conflict arises between these two documents, the CSP will supersede. It is important to note that this plan does not list all of the potential hazards and their controls because the design and safety analysis process is still ongoing. Additional safety issues win be addressed in the Final Safety Analysis Report, Operational Safety Procedures (OSPs), and other plans and procedures as described in Section 3.0 of this plan

Configuration control during maintenance of safety related equipment

International Nuclear Information System (INIS)

Irish, C.S.

2001-01-01

Possibly the most important aspect of performing maintenance of safety related equipment is maintaining the component's original design basis. Assuring that the repaired item will perform the same safety function within the original performance and equipment qualification parameters is commonly referred to as configuration control. Maintaining configuration control of a technologically current well documented item is easy. Unfortunately, this does not describe most safety related items requiring maintenance within the global nuclear industry. Items such as motors, transformers, metal clad switchgear (low and medium voltage circuit breakers), refrigeration compressors, and electronic components (i.e. circuit boards, power supplies, regulators, etc.) which routinely require repair have been in service for twenty plus years. As a result, finding replacement parts and or material to repair the items to the original condition is becoming more and more difficult. An added difficulty is the lack of original technical documentation available on the item which is being repaired. The lack of technical documentation makes it difficult to identify replacement material and parts when the original part or material is not available. The lack of documentation also makes it difficult to test the repaired item to make sure that the original configuration has been maintained after the repair. The presentation will discuss the details of repairing various items including motors, metal clad switchgear, refrigeration compressors and power supplies and the controls which are necessary to maintain the configuration of the original item. The discussion will include the Quality Assurance and engineering necessary to identify and evaluate replacement material and parts necessary to perform repairs on safety related equipment when the original material or part is not available. Examples of repairs which required different parts or materials than the original to be used in the repair will be

Configuration control during maintenance of safety related equipment

International Nuclear Information System (INIS)

Irish, C.S.

2003-01-01

Possibly the most important aspect of performing maintenance of safety related equipment is maintaining the component's original design basis. Assuring that the repaired item will perform the same safety function within the original performance and equipment qualification parameters is commonly referred to as configuration control. Maintaining configuration control of a technologically current well documented item is easy. Unfortunately, this does not describe most safety related items requiring maintenance within the global nuclear industry. Items such as motors, transformers, metal clad switchgear (low and medium voltage circuit breakers), refrigeration compressors, and electronic components (i.e. circuit boards, power supplies, regulators, etc.) which routinely require repair have been in service for twenty plus years. As a result, finding replacement parts and or material to repair the items to the original condition is becoming more and more difficult. An added difficulty is the lack of original technical documentation available on the item which is being repaired. The lack of technical documentation makes it difficult to identify replacement material and parts when the original part or material is not available. The lack of documentation also makes it difficult to test the repaired item to make sure that the original configuration has been maintained after the repair. The presentation will discuss the details of repairing various items including motors, metal clad switchgear, refrigeration compressors and power supplies and the controls which are necessary to maintain the configuration of the original item. The discussion will include the Quality Assurance and engineering necessary to identify and evaluate replacement material and parts necessary to perform repairs on safety related equipment when the original material or part is not available. Examples of repairs which required different parts or materials than the original to be used in the repair will be

A study on enforcement effects of radiation safety control regulations for diagnostic X-ray equipment

International Nuclear Information System (INIS)

Sung, Mo IL; Park, Myeong Hwan; Kwon, Duk Moon; Lee, Joon IL

1999-01-01

The purposes of this study are to analyze the realities after enforcements of safety control regulations for diagnostic X-ray equipment and to suggest means for an improvement of low radiation safety control. A questionnaire survey for medical radiologic technologists was carried out to determine enforcement effects of the safety control regulations. The results of analysis from the survey are as follows. That is, most of he respondents realized the importance of the radiation safety control system, but about a half of them revealed that regulations were not well observed in accordance with their purposes. Only 43.9 percent of the respondents took an active part in quality control of radiation. And responsibility, sex, age, and knowledge for safety control were important indicators for observations of the regulations. Training for the safety control regulations are needed to ensure safety control and proper usage of diagnostic X-ray equipment. And management of organizations using diagnostic X-ray equipment have to understand and stress the importance of radiation safety control system. (author)

Push Off 2000 : new oilfield safety device catching on

Energy Technology Data Exchange (ETDEWEB)

Mowers, J.

2006-12-15

Fuel gas scrubbers use production gas to operate oil batteries, well separators, dehydrators, compressors, and pneumatic and pressure controls. Once an internal float gets stuck, production is stopped. The Push Off 2000 is a new safety device for fuel gas scrubbers which allows operators to easily dislodge a stuck internal float by activating the tool, which is mounted on top of the vessel. The device was developed after an operator suffered burns from a flash explosion that occurred after using a hammer to strike the fuel gas scrubber. The hammer method is the usual method of dealing with stuck internal floats, and can also jeopardize the integrity of the vessel, releasing gas or liquid hydrocarbons into the environment. The Push Off 2000 is expected to reduce costly facility downtime and increase revenue generating production time. Over 50 oil and gas companies have the Push Off 2000 device installed on fuel gas scrubber units at their facilities, and have recognized the safety and economic merits of the tool. The patented device has been approved by the Alberta Boilers Safety Association, the British Columbia Boiler and Elevator Safety Branch, and the Saskatchewan Boiler and Pressure Vessel Safety Unit. 1 fig.

Functionality of road safety devices – identification and analysis of factors

Directory of Open Access Journals (Sweden)

Jeliński Łukasz

2017-01-01

Full Text Available Road safety devices are designed to protect road users from the risk of injury or death. The principal type of restraint is the safety barrier. Deployed on sites with the highest risk of run-off-road accidents, safety barriers are mostly found on bridges, flyovers, central reservations, and on road edges which have fixed obstacles next to them. If properly designed and installed, safety barriers just as other road safety devices, should meet a number of functional features. This report analyses factors which may deteriorate functionality, ways to prevent this from happening and the thresholds for loss of road safety device functionality.

Radiation safety in X-ray facilities

International Nuclear Information System (INIS)

2001-09-01

The guide specifies the radiation safety requirements for structural shielding and other safety arrangements used in X-ray facilities in medical and veterinary X-ray activities and in industry, research and education. The guide is also applicable to premises in which X-ray equipment intended for radiation therapy and operating at a voltage of less than 25 kV is used. The guide applies to new X-ray facilities in which X-ray equipment that has been used elsewhere is transferred. The radiation safety requirements for radiation therapy X-ray devices operating at a voltage exceeding 25 kV, and for the premices in which such devices are used, are set out in Guide ST 2.2

Radiation safety in X-ray facilities

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-09-01

The guide specifies the radiation safety requirements for structural shielding and other safety arrangements used in X-ray facilities in medical and veterinary X-ray activities and in industry, research and education. The guide is also applicable to premises in which X-ray equipment intended for radiation therapy and operating at a voltage of less than 25 kV is used. The guide applies to new X-ray facilities in which X-ray equipment that has been used elsewhere is transferred. The radiation safety requirements for radiation therapy X-ray devices operating at a voltage exceeding 25 kV, and for the premices in which such devices are used, are set out in Guide ST 2.2.

Safety evaluation in the development of medical devices and combination products

CERN Document Server

Gad, Shayne C

2008-01-01

Capturing the growth of the global medical device market in recent years, this practical new guide is essential for all who are responsible for ensuring safety in the use and manufacture of medical devices. It has been extensively updated to reflect significant advances, incorporating combination products and helpful case examples of current real-life problems in the field.The Third Edition explores these key current trends:global device marketscontinually advancing technologythe increasing harmonization of device safety regulation worldwideEach aspect of safety evaluation is considered in ter

Aspects of safety assessments for package with additional equipment components

International Nuclear Information System (INIS)

Reiche, I.; Boerst, F.M.; Krietsch, T.

2004-01-01

Many paragraphs in TS-R-1 contain the terms ''package'' or ''packaging''. These terms are defined in TS-R-1 paras 230 and 231 and explained in TS-G-1.1 paras 230.1 - 230.6. The importance of a consistent understanding of these definitions has been shown by recent discussions during the assessment of applications for package design approval. There was disagreement, if equipment components attached to the container body during transport, e.g. a transport frame, should be considered part of the package and taken into account in the safety assessment for the package. Discussions were also caused by the way inner design components are treated in the safety assessment of the package. This paper summarises the regulatory requirements to such additional equipment components and presents the way of their inclusion into the package design approval process in Germany

26 CFR 1.187-1 - Amortization of certain coal mine safety equipment.

Science.gov (United States)

2010-04-01

... 26 Internal Revenue 3 2010-04-01 2010-04-01 false Amortization of certain coal mine safety... (CONTINUED) INCOME TAX (CONTINUED) INCOME TAXES Itemized Deductions for Individuals and Corporations (continued) § 1.187-1 Amortization of certain coal mine safety equipment. (a) Allowance of deduction—(1) In...

Synergistic behaviour of nuclear radiation, temperature-humidity extremes and LOCA situation on safety and safety-related equipment in Indian nuclear power plants

International Nuclear Information System (INIS)

Kulkarni, R.D.; Bora, J.S.; Prakash, Ravi; Agarwal, Vivek; Sundersingh, V.P.

2002-01-01

Full text: The general philosophy for the instrumentation in nuclear power plants is based on the use of equipment/instruments which are capable of continuous satisfactory operation over a long period of time with minimum attention. Long term reliability under varying service conditions is of prime importance. The reliability of nuclear power plant depends on the reliability of safety and safety-related electronic instruments/ equipment used for performing the crucial tasks. The electrical and electronic systems/ circuits/ components of the equipment used in reactor safety systems (e.g. reactor protection system, emergency core cooling system, etc.) and reactor safety-related systems (e.g. reactor containment isolation and cooling system, reactor shutdown system, etc.) are responsible for safe and reliable operation of a nuclear power plant. The performance of reactor safety and safety-related equipment/instruments viz. pressure and differential pressure transmitter, amplifier for ion chamber, etc. has been evaluated under synergistic atmosphere including LOCA to find out the critical link in the circuits and subsequent modifications are suggested. The mathematical representation of the generated database has been done to estimate the life span of the instruments and accordingly the guidelines has been prepared for the operational staff to avoid the forced outage of the plant. All the details are included and mathematical models are presented to predict the future performances

Design and fabrication of equipment and devices for a Radiotherapy department

International Nuclear Information System (INIS)

Picon, C.L.; Zaharia B, M.

1998-01-01

The objective of this work is to present the possibility to design and construct utilizing local technology, a series of equipment and devices necessaries for a routine in a Radiotherapy Department with typical budget in the Latin-American hospitals. (Author)

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.…

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

Science.gov (United States)

2005-01-01

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

CFD Analysis of the Safety Injection Tank and Fluidic Device

Energy Technology Data Exchange (ETDEWEB)

Cho, Jai Oan; Nietiadi, Yohanes Setiawan; Lee, Jeong Ik [KAIST, Daejeon (Korea, Republic of); Addad, Yacine [KUSTAR, Abu Dhabi (United Arab Emirates)

2016-05-15

One of the most important components in the ECCS is the safety injection tank (SIT). Inside the SIT, a fluidic device is installed, which passively controls the mass flow of the safety injection and eliminates the need for low pressure safety injection pumps. As more passive safety mechanisms are being pursued, it has become more important to understand flow structure and the loss mechanism within the fluidic device. Current computational fluid dynamics (CFD) calculations have had limited success in predicting the fluid flow accurately. This study proposes to find a more exact result using CFD and more realistic modeling to predict the performance during accident scenarios more accurately. The safety injection tank with fluidic device was analyzed thoroughly using CFD. The preliminary calculation used 60,000 meshes for the initial test calculation. The results fit the experimental results surprisingly despite its coarse grid. Nonetheless, the mesh resolution was increased to capture the vortex in the fluidic device precisely. Once a detailed CFD computation is finished, a small-scale experiment will be conducted for the given conditions. Using the experimental results and the CFD model, physical models can be improved to fit the results more accurately.

46 CFR 31.40-10 - Cargo Ship Safety Equipment Certificate-T/ALL.

Science.gov (United States)

2010-10-01

... 46 Shipping 1 2010-10-01 2010-10-01 false Cargo Ship Safety Equipment Certificate-T/ALL. 31.40-10 Section 31.40-10 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY TANK VESSELS INSPECTION AND CERTIFICATION Certificates Under International Convention for Safety of Life at Sea, 1974 § 31.40-10 Cargo Ship...

Safety and feasibility research of CIPT-Ⅱ irradiation device

International Nuclear Information System (INIS)

Zhang Zhihua; Mi Xiangmiao; Li Rundong

2014-01-01

CITP-Ⅱ irradiation device, which is specially designed for fusion tritium breeder research, works in a thermal neutron reactor. With lithium orthosilicate as the breeder, the safety analysis was done to work out the device's influence on physical parameters of the reactor and get the breeder's temperature distribution and thermo-technical features in the n-γ field. The stiffness and strength were checked, and also the safety characters of the device were assessed. The feasibility of gap gas regulating the temperature and gas refueling the breeder was demonstrated. The calculation and analysis results provide data for comprehensive performance assessment. (authors)

Health and safety manual

International Nuclear Information System (INIS)

1980-02-01

The manual consists of the following chapters: general policies and administration; the Environmental Health and Safety Department; the Medical Services Department: biological hazards; chemical safety; confined space entry; cryogenic safety; electrical safety; emergency plans; engineering and construction; evacuations, trenching, and shoring; fire safety; gases, flammable and compressed; guarding, mechanical; ladders and scaffolds, work surfaces; laser safety; materials handling and storage; noise; personal protective equipment; pressure safety; radiation safety, ionizing and non-ionizing; sanitation; seismic safety; training, environmental health and safety; tools, power and hand-operated; traffic and transportation; and warning signs and devices

Safety-related control air systems

International Nuclear Information System (INIS)

Anon.

1977-01-01

This Standard applies to those portions of the control air system that furnish air required to support, control, or operate systems or portions of systems that are safety related in nuclear power plants. This Standard relates only to the air supply system(s) for safety-related air operated devices and does not apply to the safety-related air operated device or to air operated actuators for such devices. The objectives of this Standard are to provide (1) minimum system design requirements for equipment, piping, instruments, controls, and wiring that constitute the air supply system; and (2) the system and component testing and maintenance requirements

Verification of BGA type FPGA logic applied to a control equipment with Safety Class using the special socket

International Nuclear Information System (INIS)

Chung, YounHu; Yoo, Kwanwoo; Lee, Myeongkyun; Yun, Donghwa

2015-01-01

This article aims to provide the verification method for BGA-type FPGA of Programmable Logic Controller (PLC) developed as Safety Class. The logic of FPGA in the control device with Safety Class is the circuit to control overall logic of PLC. This device converts to the different module from the input signals for both digital and analogue of the equipment in the field and outputs their data. In addition, it should perform the logical controls such as backplane communication control and data communication. We suggest acquiring method of the data signal with efficient logic using the socket in this article. Proposed test socket is made by simpler process than former one, and the process is done in batches by which cost can be reduces, and the test socket can be quickly produced in response to any request. Also, it is possible to reduce the wear by reducing the contact force of the ball phenomenon. The structure on the basis of silicon can be reduced the modification, and it has excellent linearity. At the logic verification, the operation that state data block is designed in the FPGA could be easily confirmed by using a socket

Selection of equipment for equipment qualification

International Nuclear Information System (INIS)

Torr, K.G.

1989-01-01

This report describes the methodology applied in selecting equipment in the special safety systems for equipment qualification in the CANDU 600 MW nuclear generating stations at Gentilly 2 and Point Lepreau. Included is an explanation of the selection procedure adopted and the rationale behind the criteria used in identifying the equipment. The equipment items on the list have been grouped into three priority categories as a planning aid to AECB staff for a review of the qualification status of the special safety systems

The basic discussion on nuclear power safety improvement based on nuclear equipment design

International Nuclear Information System (INIS)

Zhao Feiyun; Yao Yangui; Yu Hao; He Yinbiao; Gao Lei; Yao Weida

2013-01-01

The safety of strengthening nuclear power design was described based on nuclear equipment design after Fukushima nuclear accident. From these aspects, such as advanced standard system, advanced design method, suitable test means, consideration of beyond design basis event, and nuclear safety culture construction, the importance of nuclear safety improvement was emphatically presented. The enlightenment was given to nuclear power designer. (authors)

Design of Hack-Resistant Diabetes Devices and Disclosure of Their Cyber Safety.

Science.gov (United States)

Sackner-Bernstein, Jonathan

2017-03-01

The focus of the medical device industry and regulatory bodies on cyber security parallels that in other industries, primarily on risk assessment and user education as well as the recognition and response to infiltration. However, transparency of the safety of marketed devices is lacking and developers are not embracing optimal design practices with new devices. Achieving cyber safe diabetes devices: To improve understanding of cyber safety by clinicians and patients, and inform decision making on use practices of medical devices requires disclosure by device manufacturers of the results of their cyber security testing. Furthermore, developers should immediately shift their design processes to deliver better cyber safety, exemplified by use of state of the art encryption, secure operating systems, and memory protections from malware.

Comparing non-safety with safety device sharps injury incidence data from two different occupational surveillance systems.

Science.gov (United States)

Mitchell, A H; Parker, G B; Kanamori, H; Rutala, W A; Weber, D J

2017-06-01

The United States Occupational Safety and Health Administration (OSHA) Bloodborne Pathogens Standard as amended by the Needlestick Safety and Prevention Act requiring the use of safety-engineered medical devices to prevent needlesticks and sharps injuries has been in place since 2001. Injury changes over time include differences between those from non-safety compared with safety-engineered medical devices. This research compares two US occupational incident surveillance systems to determine whether these data can be generalized to other facilities and other countries either with legislation in place or considering developing national policies for the prevention of sharps injuries among healthcare personnel. Copyright © 2017 The Healthcare Infection Society. Published by Elsevier Ltd. All rights reserved.

48 CFR 252.239-7016 - Telecommunications security equipment, devices, techniques, and services.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Telecommunications... SOLICITATION PROVISIONS AND CONTRACT CLAUSES Text of Provisions And Clauses 252.239-7016 Telecommunications... clause: Telecommunications Security Equipment, Devices, Techniques, and Services (DEC 1991) (a...

Discussion on unpacking inspection of imported civil nuclear safety equipment

International Nuclear Information System (INIS)

Li Chan; Zhang Wenguang; Li Maolin; Li Shixin; Jin Gang; Yao Yuan

2014-01-01

This paper introduces the purpose, contents, process and requirements of unpacking inspection which is the second stage of safety inspection of imported civil nuclear safety equipment, expresses review key points on application documents of unpacking inspection, processes of witness on-the-spot before unpacking inspection outside the civil nuclear facilities by the test agency, discusses understanding of unpacking inspection, supervision of manufacture, inspection prior to shipment, supervision of loading and acceptance by the unit operating civil nuclear facilities, reports on unpacking inspection. Some suggestions on reinforcing the unpacking inspection in China are concerned. (authors)

Home Healthcare Medical Devices: A Checklist

Science.gov (United States)

... not using it. Contact your doctor and home healthcare team often to review your health condition. * Check ... assurance of their safety and effectiveness. A home healthcare medical device is any product or equipment used ...

A safety control device for detecting undesirable conditions

Energy Technology Data Exchange (ETDEWEB)

1974-09-26

The invention relates to safety control devices. It deals with a device adapted to transmit a warning signal and to the detection of an undesirable condition in an associated apparatus, said device comprising switching means comprising transistors mounted in a reaction path, feeding means for opening the switching means whenever an undesirable condition has been detected by sensors, whereby an oscillator is caused to stop oscillating, and an outlet device controlled by the oscillator stoppage. This can be applied to the supervision of nuclear reactor.

Electromedical devices test laboratories accreditation

International Nuclear Information System (INIS)

Murad, C; Rubio, D; Ponce, S; Alvarez Abri, A; Terron, A; Vicencio, D; Fascioli, E

2007-01-01

In the last years, the technology and equipment at hospitals have been increase in a great way as the risks of their implementation. Safety in medical equipment must be considered an important issue to protect patients and their users. For this reason, test and calibrations laboratories must verify the correct performance of this kind of devices under national and international standards. Is an essential mission for laboratories to develop their measurement activities taking into account a quality management system. In this article, we intend to transmit our experience working to achieve an accredited Test Laboratories for medical devices in National technological University

APR1400 Fluidic Device Sensitivity Test

International Nuclear Information System (INIS)

Choi, Nam Hyun; Chu, In Cheol; Min, Kyong Ho; Song, Chul Hwa

2005-12-01

In the safety injection tank at the emergency core cooling system of APR1400, a new safety design feature, passive fluidic device is equipped which includes no active driving system. It is essential to evaluate the new design feature with various experiments. For this reason, three categories of sensitivity tests have been performed in the present study. As the first sensitivity experiment, the effect of the height of the stand pipe was investigated. The second sensitivity test was conducted with removing the insert plate gasket to examine its effect. The effect of the expansion of the control nozzle width was ascertained from the third sensitivity test. The results of each test showed that the passive fluidic device which will be equipped in the SIT tank of APR1400 has great integrity and repeatability

Technical evaluation of seismic qualification of safety-related equipment

Energy Technology Data Exchange (ETDEWEB)

Cho, Yang Hui; Park, Heong Gee; Park, Yeong Seok [Univ. of Incheon, Incheon (Korea, Republic of)

1994-04-15

This study is purposed to evaluate the technical acceptability of the procedures and techniques of seismic qualifications which were performed for the YGN 3 and 4 safety-related equipment.This study is also targeted to suggest a systematized technical procedure guide for the effective performance and review of the seismic qualification, which reflects the most up-to-date licensing requirements and state-of the-art.

Radiation safety of sealed sources and equipment containing them

International Nuclear Information System (INIS)

1993-01-01

The guide gives information and requirements concerning the technical construction, installation, use and licensing of devices containing sealed radioactive sources in order to ensure the operational safety. The requirements are in accordance with the international standards ISO 1677, ISO 2919, ISO 7205 and Nordic Recommendations on radiation protection for radionuclide gauges in permanent installation. The guide explains also the practical measures that must be taken into account when a radiation device is repaired, maintained or removed from the use. (8 refs.)

Safety and efficacy for new techniques and imaging using new equipment to support European legislation: An EU coordination action

International Nuclear Information System (INIS)

Zoetelief, J.; Faulkner, K.

2008-01-01

The past two decades have witnessed a technologically driven revolution in radiology. At the centre of these developments has been the use of computing. These developments have also been driven by the introduction of new detector and imaging devices in radiology and nuclear medicine, as well as the widespread application of computing techniques to enhance and extract information within the images acquired. Further advances have been introduced into digital practice. These technological developments, however, have not been matched by justification and optimisation studies to ensure that these new imaging devices and techniques are as effective as they might be, or performed at the lowest possible dose. The work programme of the SENTINEL Coordination Action was subdivided into eight work packages: functional performance and standards; efficacy and safety in digital radiology, dentistry and nuclear medicine, cardiology, interventional radiology, population screening/sensitive groups; justification, ethics and efficacy; good practice guidance and training; and project management. The intention of the work programme was to underwrite the safety, efficacy and ethical aspects of digital practice as well as to protect and add value to the equipment used in radiology. (authors)

Decree No85-968 of 27 August 1986 amending Article R.233-83 of the Labour Code and defining the health and safety conditions to be met by gamma industrial radiography equipment

International Nuclear Information System (INIS)

1986-01-01

This Decree, amending Article R 233-83 of the Labour Code, applies to gamma-ray industrial radiography equipment whether mobile or fixed. It contains specific technical conditions concerning the equipment, in particular, safety devices located at the entry and exit points of the source's shield. The equipment must carry a notice mentioning''Radioactive''prepared by the constructor or the importer of the source, which explains the conditions for handling, setting-up, use and maintenance of the source, including the frequency of revisions. The Decree entered into force on 1 June 1986. (NEA) [fr

The history of anaesthetic equipment evaluation in the United Kingdom: lessons for developing future strategy.

Science.gov (United States)

Wilkes, A R; Pandit, J J; O'Sullivan, E

2011-12-01

Recent guidance published by the Association of Anaesthetists of Great Britain and Ireland encourages the purchase of equipment based on evidence of safety and performance. For many years, evidence of the safety and performance of anaesthetic equipment was published by various government departments and agencies. However, these schemes were gradually eroded over time such that many devices entered the market with little or no clinical evidence of their efficacy. This recently led to the Difficult Airway Society's issuing guidance to its members on how best to select new airway devices; guidance that was based on the available evidence. This article provides a short history of the evaluation of anaesthetic equipment in the United Kingdom. © 2011 The Authors. Anaesthesia © 2011 The Association of Anaesthetists of Great Britain and Ireland.

Development of a Test Equipment for Performance Evaluation of Safety Systems

International Nuclear Information System (INIS)

Kim, S. J.; Kwon, S. M.; Lee, J. M.; Kim, C. K.; Cho, C. H.; Chun, J. H.; Park, M. K.

2004-07-01

The purpose of this study is to develop a test equipment for performance evaluation of safety systems in nuclear power plants. First, we develop an input-output simulator for reactor protection systems, ESF component control systems, and a data acquisition system for these I/O simulators as a hardware for this equipment. Then, we develop a software for human-machine interface system, which is easy-to-use and easy-to-modify. In addition, a simulation tool for a reactor trip switch gear is developed

Spent nuclear fuel project cold vacuum drying facility safety equipment list

International Nuclear Information System (INIS)

IRWIN, J.J.

1999-01-01

This document provides the safety equipment list (SEL) for the Cold Vacuum Drying Facility (CVDF). The SEL was prepared in accordance with the procedure for safety structures, systems, and components (SSCs) in HNF-PRO-516, ''Safety Structures, Systems, and Components,'' Revision 0 and HNF-PRO-097, Engineering Design and Evaluation, Revision 0. The SEL was developed in conjunction with HNF-SO-SNF-SAR-O02, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998). The SEL identifies the SSCs and their safety functions, the design basis accidents for which they are required to perform, the design criteria, codes and standards, and quality assurance requirements that are required for establishing the safety design basis of the SSCs. This SEL has been developed for the CVDF Phase 2 Safety Analysis Report (SAR) and shall be updated, expanded, and revised in accordance with future phases of the CVDF SAR until the CVDF final SAR is approved

49 CFR 214.507 - Required safety equipment for new on-track roadway maintenance machines.

Science.gov (United States)

2010-10-01

... maintenance machines. 214.507 Section 214.507 Transportation Other Regulations Relating to Transportation... Roadway Maintenance Machines and Hi-Rail Vehicles § 214.507 Required safety equipment for new on-track roadway maintenance machines. (a) Each new on-track roadway maintenance machine shall be equipped with: (1...

Novel AC Servo Rotating and Linear Composite Driving Device for Plastic Forming Equipment

Science.gov (United States)

Liang, Jin-Tao; Zhao, Sheng-Dun; Li, Yong-Yi; Zhu, Mu-Zhi

2017-07-01

The existing plastic forming equipment are mostly driven by traditional AC motors with long transmission chains, low efficiency, large size, low precision and poor dynamic response are the common disadvantages. In order to realize high performance forming processes, the driving device should be improved, especially for complicated processing motions. Based on electric servo direct drive technology, a novel AC servo rotating and linear composite driving device is proposed, which features implementing both spindle rotation and feed motion without transmission, so that compact structure and precise control can be achieved. Flux switching topology is employed in the rotating drive component for strong robustness, and fractional slot is employed in the linear direct drive component for large force capability. Then the mechanical structure for compositing rotation and linear motion is designed. A device prototype is manufactured, machining of each component and the whole assembly are presented respectively. Commercial servo amplifiers are utilized to construct the control system of the proposed device. To validate the effectiveness of the proposed composite driving device, experimental study on the dynamic test benches are conducted. The results indicate that the output torque can attain to 420 N·m and the dynamic tracking errors are less than about 0.3 rad in the rotating drive. the dynamic tracking errors are less than about 1.6 mm in the linear feed. The proposed research provides a method to construct high efficiency and accuracy direct driving device in plastic forming equipment.

Material & equipment, procurement & maintenance: Impact on blood safety.

Science.gov (United States)

Emmanuel, Jean C

2010-01-01

Blood Transfusion Safety is dependent on effectively organised and managed blood services, which have adequate financial resources, skilled manpower, appropriate infrastructure and quality management systems in place. 80% of the world's population has access to 20% of the supply blood products, of which little is consistently safe. HIV highlighted the importance of blood safety. The lack of effective blood services in low human development index (LHDI), developing countries, has lead to international funding and capacity building for more than three decades. The initial strategies focused on providing HIV testing reagents to prevention transmission, however this only addresses one part of blood safety. Blood safety is not only dependent on preventing HIV transmission. In many populations there are other infectious agents, which have a higher prevalence. Ensuring the correct blood is provided to the patient depends on: well managed services with effective leadership and adequate budgets; capacity building and retention of skilled experienced staff; availability of laboratory equipment, correctly maintained; blood cold chain systems; procedures for tendering, purchasing and ensuring an unbroken supply of reagents and consumables; and quality management systems. Barriers for simplified effective tendering, procurement and contracting require urgent attention and coordination of all funding organisations to ensure an unbroken supply of reagents. Copyright 2009. Published by Elsevier Ltd.

Plant operation monitoring method and device therefor

International Nuclear Information System (INIS)

Ando, Tsugio; Matsuki, Tsutomu.

1997-01-01

The present invention provides a method of and a device for monitoring the operation of a nuclear power plant during operation, which improves the safety and reliability of operation without increasing an operator's burden. Namely, a chief in charge orally instruct an operation to an operator upon the operation of a plant constituent equipment. The operator points the equipment and calls the name. Actual operation instruction for the equipment is inputted after confirmation by oral response. The voices of theses series of operation instruction/point-calling/response confirmation are taken into a voice recognition processing device. The processing device discriminates each of the person who calls, and discriminates the content of the calls and objective equipments to be operated. Then, the series of procedures and contents of the operation for the equipments previously disposed in the data base are compared with the order of inputted calls, discriminated contents and the objective equipments to be operated. If they are not agreed with each other, the operation instruction is blocked even if actual operation instructions are inputted. (I.S.)

Unresolved Safety Issue A-46 - seismic qualification of equipment in operating plants

International Nuclear Information System (INIS)

Anderson, N.

1985-01-01

Seismic Qualification of Equipment in Operating Plants was designated as an Unresolved Safety Issue (USI) in December, 1980. The USI A-46 program was developed in early 1981 to investigate the adequacy of mechanical and electrical equipment in operating plants to withstand a safe shutdown earthquake. The approach taken was to develop viable, cost effective alternatives to current seismic qualification licensing requirements which could be applied to operating nuclear power plants. The tasks investigated include: (1) identification of seismic sensitive systems and equipment; (2) assessment of adequacy of existing seismic qualification methods; (3) development and assessment of in-situ test procedures to assist in qualification of equipment; (4) seismic qualification of equipment using seismic experience data; and (5) development of methods to generate generic floor response spectra. Progress to date and plans for completion of resolution are reported

Use of digital computing devices in systems important to safety

International Nuclear Information System (INIS)

1986-01-01

The incorporation of digital computing devices in systems important to safety now is progressing fast in several countries, including Canada, France, Federal Republic of Germany, Japan, USA. There are now reactors with microprocessors in some trip systems. The major functions of those systems are: reactor trip initiation, display, monitoring, testing, re-calibration of detectors. The benefits of moving to a fully computerized shut-down system should be improved reliability, greater flexibility, better man-machine interface, improved testing, higher reactor output and lower overall cost. With the introduction of computer devices in systems important to safety, plant availability and safety are improved because disturbances are treated before they lead to safety action, in this way helping the operator to avoid errors. The Meeting presentations were divided into sessions devoted to the following topics: Needs for the use of digital devices (DCD) in safety important systems (SIS) (5 papers); Problems raised by the integration SIS in the NPP control (7 papers); Description and presentation of DCD of SIS (6 papers); Results of experiences in engineering, manufacture, qualification operation of DCD hardware and software (5 papers). A separate abstract was prepared for each of these papers

Comparison of safety equipment between London underground and Beijing subway

Science.gov (United States)

Chen, T.; Zhang, S. Y.; Zhao, L. Z.; Xia, J. J.; Fu, X. C.; Bao, Z. M.; Chen, Y.; Zhang, X. Z.; Wang, R. J.; Hu, C.; Jing, L. S.; Wang, Y.

2017-06-01

The purpose of this paper was to improve the safety equipment’s effectiveness through the comparison. Firstly, the history and safety accident of London Underground and Beijing Subway were shown. Secondly, fire equipment between these two cities was compared including station’s hardware installations and carriage’s hardware installations. Thirdly, the relative software installations were also compared such as emergency drills. The results showed that Beijing Subway’s hardware installations were better than London. However, London Underground’s some installations were more effective than Beijing. Both cities would pay more attention on anti-terrorist in tunnel.

Evaluation of Electrical Characteristics of Protective Equipment - a Prerequisite for Ensuring Safety and Health of Workers at Work

Science.gov (United States)

Buică, G.; Beiu, C.; Antonov, A.; Dobra, R.; Păsculescu, D.

2017-06-01

The protecting electrical equipment in use are subject to various factors generated by the use, maintenance, storage and working environment, which may change the characteristics of protection against electric shock. The study presents the results of research on the behaviour over time of protective characteristics of insulating covers of material of work equipment in use, in order to determine the type and periodicity of safety tests. There were tested and evaluated safety equipment with plastic and insulating rubber covers used in operations of verifying functionality, safety and maintenance of machinery used in manufacturing industries and specific services from electric, energy and food sector.

Evaluation of safety requirements of erbium laser equipment used in dentistry; Avaliacao de requisitos de seguranca de um equipamento a laser de erbio para fins odontologicos

Energy Technology Data Exchange (ETDEWEB)

Braga, Flavio Hamilton

2002-07-01

The erbium laser (Er:YAG) has been used in several therapeutic processes. Erbium lasers, however, operate with energies capable to produce lesions in biological tissues. Aiming the safe use, the commercialization of therapeutic laser equipment is controlled in Brazil, where the equipment should comply with quality and safety requirement prescribed in technical regulations. The objective of this work is to evaluate the quality and safety requirements of a commercial therapeutic erbium laser according to Brazilian regulations, and to discuss a risk control program intended to minimize the accidental exposition at dangerous laser radiation levels. It was verified that the analyzed laser can produce lesions in the skin and eyes, when exposed to laser radiation at distances smaller than 80 cm by 10 s or more. In these conditions, the use of protection glasses is recommended to the personnel that have access to the laser operation ambient. It was verified that the user's training and the presence of a target indicator are fundamental to avoid damages in the skin and buccal cavity. It was also verified that the knowledge and the correct use of the equipment safety devices, and the application of technical and administrative measures is efficient to minimize the risk of dangerous expositions to the laser radiation. (author)

Inspection device for buried equipment

International Nuclear Information System (INIS)

Hanawa, Jun.

1994-01-01

In an inspection device for a buried equipment, a rail is suspended at the upper portion of a vessel of a pit-vessel type pump buried in a plant building floor, and a truck movable vertical in the vessel along the rail, and an ultrasonic wave probe contained in the truck and urged to the vessel by an electromagnet are disposed. In addition, an elevator moving vertically along a shaft is disposed, and an arm having the ultrasonic probe disposed at the end portion and driven by a piston are disposed to the elevator. The ultrasonic wave probe moves vertically together with the truck along the rail in the vessel while being urged to the vessel by the electromagnet to inspect and measure the state at the inner and outer surfaces of the vessel. Further, the length of the arm is controlled so as to set a predetermined distance between the ultrasonic wave probe and the vessel. Subsequently, the elevator is moved vertically along a shaft passing through a shaft hole of a mount, and the shaft is rotated thereby enabling to inspect and measure the state of the inner and outer surfaces of the vessel. (N.H.)

Recommended safety procedures for the selection, installation and use of baggage inspection x-ray equipment

International Nuclear Information System (INIS)

1978-05-01

Good X-ray equipment alone will not preclude unnecessary exposure to x-radiation. The equipment must be installed, maintained and used by adequately trained personnel, with due regard for the inherent hazards of such equipment and an appreciation of the need to observe proper operational procedures. It is the intent of this Code to define equipment specifications and conditions of installation and use for baggage inspection X-ray equipment, such that the hazard to operating personnel and the general public from such devices remains negligibly small. (auth)

Radiation protection in dentistry. Recommended safety procedures for the use of dental x-ray equipment. Safety code 30

International Nuclear Information System (INIS)

1994-01-01

The Radiation Protection Bureau has prepared a series of documents on safety codes to set out requirements for the safe use of radiation-emitting equipment. This Safety Code has been prepared to provide specific guidance to the dentist, dental hygienist, dental assistant and other support personnel concerned with safety procedures and equipment performance. Dental radiography is one of the most valuable tools used in modern dental health care. It makes possible the diagnosis of physical conditions that would otherwise be difficult to identify. The use of dental radiological procedures must be carefully managed, because x-radiation has the potential for damaging healthy cells and tissues. Although no known occurrence of cancer or genetic damage has been observed from radiation doses delivered in modern dentistry, and until more evidence is available, one should practice radiation hygiene with the same care as would be dictated if a hazard were known to exist. The aim of radiation protection in dentistry is to obtain the desired clinical information with minimal radiation exposure to patients, dental personnel and the public. 15 tabs

Radiation protection in dentistry. Recommended safety procedures for the use of dental x-ray equipment. Safety code 30

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-31

The Radiation Protection Bureau has prepared a series of documents on safety codes to set out requirements for the safe use of radiation-emitting equipment. This Safety Code has been prepared to provide specific guidance to the dentist, dental hygienist, dental assistant and other support personnel concerned with safety procedures and equipment performance. Dental radiography is one of the most valuable tools used in modern dental health care. It makes possible the diagnosis of physical conditions that would otherwise be difficult to identify. The use of dental radiological procedures must be carefully managed, because x-radiation has the potential for damaging healthy cells and tissues. Although no known occurrence of cancer or genetic damage has been observed from radiation doses delivered in modern dentistry, and until more evidence is available, one should practice radiation hygiene with the same care as would be dictated if a hazard were known to exist. The aim of radiation protection in dentistry is to obtain the desired clinical information with minimal radiation exposure to patients, dental personnel and the public. 15 tabs.

Fundamentals of a graded approach to safety-related equipment setpoints

International Nuclear Information System (INIS)

Woodruff, B.A.; Cash, J.S. Jr.; Bockhorst, R.M.

1993-01-01

The concept of using a graded approach to reconstitute instrument setpoints associated with safety-related equipment was first presented to the industry by the U.S. Nuclear Regulatory Commission during the 1992 ISA/POWID Symposium in Kansas City, Missouri. The graded approach establishes that the manner in which a utility analyzes and documents setpoints is related to each setpoint's relative importance to safety. This allows a utility to develop separate requirements for setpoints of varying levels of safety significance. A graded approach to setpoints is a viable strategy that minimizes extraneous effort expended in resolving difficult issues that arise when formal setpoint methodology is applied blindly to all setpoints. Close examination of setpoint methodology reveals that the application of a graded approach is fundamentally dependent on the analytical basis of each individual setpoint

Safety Features of Material and Personnel Movement Devices. Module SH-25. Safety and Health.

Science.gov (United States)

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

This student module on safety features of material and personnel movement devices is one of 50 modules concerned with job safety and health. This module covers safe conditions and operating practices for conveyors, elevators, escalators, moving walks, manlifts, forklifts, and motorized hand trucks. Following the introduction, 10 objectives (each…

Method of operator safety assessment for underground mobile mining equipment

Science.gov (United States)

Działak, Paulina; Karliński, Jacek; Rusiński, Eugeniusz

2018-01-01

The paper presents a method of assessing the safety of operators of mobile mining equipment (MME), which is adapted to current and future geological and mining conditions. The authors focused on underground mines, with special consideration of copper mines (KGHM). As extraction reaches into deeper layers of the deposit it can activate natural hazards, which, thus far, have been considered unusual and whose range and intensity are different depending on the field of operation. One of the main hazards that affect work safety and can become the main barrier in the exploitation of deposits at greater depths is climate threat. The authors have analysed the phenomena which may impact the safety of MME operators, with consideration of accidents that have not yet been studied and are not covered by the current safety standards for this group of miners. An attempt was made to develop a method for assessing the safety of MME operators, which takes into account the mentioned natural hazards and which is adapted to current and future environmental conditions in underground mines.

Method of operator safety assessment for underground mobile mining equipment

Directory of Open Access Journals (Sweden)

Działak Paulina

2018-01-01

Full Text Available The paper presents a method of assessing the safety of operators of mobile mining equipment (MME, which is adapted to current and future geological and mining conditions. The authors focused on underground mines, with special consideration of copper mines (KGHM. As extraction reaches into deeper layers of the deposit it can activate natural hazards, which, thus far, have been considered unusual and whose range and intensity are different depending on the field of operation. One of the main hazards that affect work safety and can become the main barrier in the exploitation of deposits at greater depths is climate threat. The authors have analysed the phenomena which may impact the safety of MME operators, with consideration of accidents that have not yet been studied and are not covered by the current safety standards for this group of miners. An attempt was made to develop a method for assessing the safety of MME operators, which takes into account the mentioned natural hazards and which is adapted to current and future environmental conditions in underground mines.

Safety-related control air systems - approved 1977

International Nuclear Information System (INIS)

Anon.

1978-01-01

This standard applies to those portions of the control air system that furnish air required to support, control, or operate systems or portions of systems that are safety related in nuclear power plants. This standard relates only to the air supply system(s) for safety-related air operated devices and does not apply to the safety-related air operated device or to air operated actuators for such devices. The objectives of this standard are to provide (1) minimum system design requirements for equipment, piping, instruments, controls, and wiring that constitute the air supply system; and (2) the system and component testing and maintenance requirements

RESULTS OF THE SURVEY CONDUCTED AMONG OPHTHALMOLOGISTS ON THE ISSUE OF EQUIPMENT OF MEDICAL INSTITUTIONS WITH OPHTHALMOLOGY DEVICES

Directory of Open Access Journals (Sweden)

S. V. Seraphimov

2017-01-01

Full Text Available Introduction. The problem of limited accessibility and quality of ophthalmic medical care remains one of the leading ones in the national healthcare. This article presents results of the survey conducted among ophthalmologists about the effect of large-scale equipment of all medical institutions in the Leningrad Region with modern ophthalmologic devices over the recent years.Objective is to determine the contribution of the health care modernization program to equipping the medical institutions of the Leningrad Region with modern ophthalmologic medical devices, and to identify the main areas for improving the ophthalmologic care for residents of the Leningrad region with cataracts.Materials and methods. According to a specially developed questionnaire, 105 ophthalmologists from the Leningrad Region were interviewed. The survey was conducted among physicians working both in out-patient medical facilities and in medical facilities with in-patient modalities.Results. The results of the study confirmed positive changes that occurred in recent years as a result of equipping medical institutions with modern medical devices. Almost two-thirds (59.9% of respondents noted that equipping with modern medical devices had a significant impact on the quality of the medical and diagnostic measures carried out in healthcare facilities of the region.Conclusions. The equipment had a significant impact on the diagnosis and treatment of all kinds of diseases of the eye and its appendages, especially such eye disease which is so common among the population of the Leningrad Region as cataracts (75.0 per 100 ophthalmologists surveyed. At the same time, in spite of these efforts, the standard for equipping ophthalmologic departments in individual medical institutions has not been fully provided. Only every fifth (20.9% ophthalmologist noted during the survey that the list of available ophthalmic devices was sufficient, and that they all worked properly.

The Difficult Airway Society 'ADEPT' guidance on selecting airway devices: the basis of a strategy for equipment evaluation.

Science.gov (United States)

Pandit, J J; Popat, M T; Cook, T M; Wilkes, A R; Groom, P; Cooke, H; Kapila, A; O'Sullivan, E

2011-08-01

Faced with the concern that an increasing number of airway management devices were being introduced into clinical practice with little or no prior evidence of their clinical efficacy or safety, the Difficult Airway Society formed a working party (Airway Device Evaluation Project Team) to establish a process by which the airway management community within the profession could itself lead a process of formal device/equipment evaluation. Although there are several national and international regulations governing which products can come on to the market and be legitimately sold, there has hitherto been no formal professional guidance relating to how products should be selected (i.e. purchased). The Airway Device Evaluation Project Team's first task was to formulate such advice, emphasising evidence-based principles. Team discussions led to a definition of the minimum level of evidence needed to make a pragmatic decision about the purchase or selection of an airway device. The Team concluded that this definition should form the basis of a professional standard, guiding those with responsibility for selecting airway devices. We describe how widespread adoption of this professional standard can act as a driver to create an infrastructure in which the required evidence can be obtained. Essential elements are that: (i) the Difficult Airway Society facilitates a coherent national network of research-active units; and (ii) individual anaesthetists in hospital trusts play a more active role in local purchasing decisions, applying the relevant evidence and communicating their purchasing decisions to the Difficult Airway Society. © 2011 The Authors. Anaesthesia © 2011 The Association of Anaesthetists of Great Britain and Ireland.

Extraglottic airway devices: technology update

Directory of Open Access Journals (Sweden)

Sharma B

2017-08-01

Full Text Available Bimla Sharma, Chand Sahai, Jayashree Sood Department of Anaesthesiology, Pain and Perioperative Medicine, Sir Ganga Ram Hospital, New Delhi, India Abstract: Extraglottic airway devices (EADs have revolutionized the field of airway management. The invention of the laryngeal mask airway was a game changer, and since then, there have been several innovations to improve the EADs in design, functionality, safety and construction material. These have ranged from changes in the shape of the mask, number of cuffs and material used, like rubber, polyvinylchloride and latex. Phthalates, which were added to the construction material in order to increase device flexibility, were later omitted when this chemical was found to have serious adverse reproductive outcomes. The various designs brought out by numerous companies manufacturing EADs resulted in the addition of several devices to the airway market. These airway devices were put to use, many of them with inadequate or no evidence base regarding their efficacy and safety. To reduce the possibility of compromising the safety of the patient, the Difficult Airway Society (DAS formed the Airway Device Evaluation Project Team (ADEPT to strengthen the evidence base for airway equipment and vet the new extraglottic devices. A preuse careful analysis of the design and structure may help in better understanding of the functionality of a particular device. In the meantime, the search for the ideal EAD continues. Keywords: extraglottic airway devices, laryngeal mask airway, other extraglottic airway devices, safety, technology update

Effect of electronic device use on pedestrian safety : a literature review.

Science.gov (United States)

2016-04-01

This literature review on the effect of electronic device use on pedestrian safety is part of a research project sponsored by the Office of Behavioral Safety Research in the National Highway Traffic Safety Administration (NHTSA). An extensive literat...

Safety plan for the cooperative telerobotic retrieval system equipment development area

Energy Technology Data Exchange (ETDEWEB)

Haney, T.J.; Jessmore, J.J.

1995-07-01

This plan establishes guidelines to minimize safety risks for the cooperative telerobotic retrieval project at the North Boulevard Annex (NBA). This plan has the dual purpose of minimizing safety risks to workers and visitors and of securing sensitive equipment from inadvertent damage by nonqualified personnel. This goal will be accomplished through physical control of work zones and through assigned responsibilities for project personnel. The scope of this plan is limited to establishing the working zone boundaries and entry requirements, and assigning responsibilities for project personnel. This plan does not supersede current safety organization responsibilities for the Landfill Stabilization Focus Area Transuranic (LSFA TRU) Arid outlined in the Environment, Safety, Health, and Quality Plan for the Buried Waste Integrated Demonstration Program; Tenant Manual; Idaho Falls Building Emergency Control Plan;; applicable Company Procedures; the attached Interface Agreement (Appendix A).

Safety plan for the cooperative telerobotic retrieval system equipment development area

International Nuclear Information System (INIS)

Haney, T.J.; Jessmore, J.J.

1995-07-01

This plan establishes guidelines to minimize safety risks for the cooperative telerobotic retrieval project at the North Boulevard Annex (NBA). This plan has the dual purpose of minimizing safety risks to workers and visitors and of securing sensitive equipment from inadvertent damage by nonqualified personnel. This goal will be accomplished through physical control of work zones and through assigned responsibilities for project personnel. The scope of this plan is limited to establishing the working zone boundaries and entry requirements, and assigning responsibilities for project personnel. This plan does not supersede current safety organization responsibilities for the Landfill Stabilization Focus Area Transuranic (LSFA TRU) Arid outlined in the Environment, Safety, Health, and Quality Plan for the Buried Waste Integrated Demonstration Program; Tenant Manual; Idaho Falls Building Emergency Control Plan;; applicable Company Procedures; the attached Interface Agreement (Appendix A)

Technical basis for environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

International Nuclear Information System (INIS)

Korsah, K.; Wood, R.T.; Hassan, M.; Tanaka, T.J.

1998-01-01

This document presents the results of studies sponsored by the Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. The studies were conducted by Oak Ridge National Laboratory (ORNL), Sandia National Laboratories (SNL), and Brookhaven National Laboratory (BNL). The studies address the following: (1) adequacy of the present test methods for qualification of digital I and C systems; (2) preferred (i.e., Regulatory Guide-endorsed) standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging for equipment to be located in a benign environment; and (5) determination of an appropriate approach for addressing the impact of smoke in digital equipment qualification programs. Significant findings from the studies form the technical basis for a recommended approach to the environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

Technical basis for environmental qualification of microprocessor-based safety-related equipment in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Korsah, K.; Wood, R.T. [Oak Ridge National Lab., TN (United States); Hassan, M. [Brookhaven National Lab., Upton, NY (United States); Tanaka, T.J. [Sandia National Labs., Albuquerque, NM (United States)

1998-01-01

This document presents the results of studies sponsored by the Nuclear Regulatory Commission (NRC) to provide the technical basis for environmental qualification of computer-based safety equipment in nuclear power plants. The studies were conducted by Oak Ridge National Laboratory (ORNL), Sandia National Laboratories (SNL), and Brookhaven National Laboratory (BNL). The studies address the following: (1) adequacy of the present test methods for qualification of digital I and C systems; (2) preferred (i.e., Regulatory Guide-endorsed) standards; (3) recommended stressors to be included in the qualification process during type testing; (4) resolution of need for accelerated aging for equipment to be located in a benign environment; and (5) determination of an appropriate approach for addressing the impact of smoke in digital equipment qualification programs. Significant findings from the studies form the technical basis for a recommended approach to the environmental qualification of microprocessor-based safety-related equipment in nuclear power plants.

Equipment line-up developed for structuring programmed digital systems important to safety

International Nuclear Information System (INIS)

Remus, L.; Colling, J.M.; Buisson, J.

1986-01-01

The use of the programmed digital techniques in systems important to safety led to developing equipment line-ups which allow to procedure, through using a restricted number of sub-assemblies, a variety of facilities capable of performing diversified functions. Upon remembering the requirements that such equipment are required to meet (quality assurance both at the design and production stages, qualification, testing opportunities, etc.) the equipments produced by MERLIN GERIN are described in this paper. Such equipments include a whole set of printed circuit boards, plug-in units with self-engaging connectors and the related cabinets to accomodate them. The following systems are made up of such equipments: Digital integrated protection system; Rod control and monitoring system; Reactor power distribution monitoring equipment. This equipment line-up has been gradually complemented and is still further expanding both as a result of the component further development or for the purpose of meeting new requirements or applications (new digital neutron instrumentation, local area networks). Experience gained thus far provides us with the capability of working out in a short time programmed systems for further applications in the nuclear power field

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

Science.gov (United States)

2013-05-20

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

Safety equipment and methods for evaluating its effectiveness

Energy Technology Data Exchange (ETDEWEB)

Evdokimov, F I; Nadtoka, T B [DPI (Ukraine)

1993-05-01

Analyzes relations between technologies (especially for roof support) used in black coal mining and work safety in mines. The share of manual work and accident rate are compared for mining by narrow and wide web shearer loaders and by coal plows with powered and individual support. Protection from occupational injury is discussed at three levels: safety engineering, work organization and the human factor. A method of evaluating the social and economic effectiveness of protection from occupational injury developed at the DPI institute is presented. The method uses the knowledge of probability distribution of failure situations, failures and protective means to determine the probabilistic characteristics of the functioning of protection systems and to calculate, for a given period, the occurrence probability and mean number of accidents. Each state of the system is characterized by determined social and/or economic results. The method was used in designing equipment intended for protective power cut-off in electric mine networks.

Visual communication and terminal equipment

International Nuclear Information System (INIS)

Kang, Cheol Hui

1988-06-01

This book is divided two parts about visual communication and terminal equipment. The first part introduces visual communication, which deals with foundation of visual communication, technique of visual communication, equipment of visual communication, a facsimile and pictorial image system. The second part contains terminal equipment such as telephone, terminal equipment for data transmission on constitution and constituent of terminal equipment for data transmission, input device and output device, terminal device and up-to-date terminal device.

Visual communication and terminal equipment

Energy Technology Data Exchange (ETDEWEB)

Kang, Cheol Hui

1988-06-15

This book is divided two parts about visual communication and terminal equipment. The first part introduces visual communication, which deals with foundation of visual communication, technique of visual communication, equipment of visual communication, a facsimile and pictorial image system. The second part contains terminal equipment such as telephone, terminal equipment for data transmission on constitution and constituent of terminal equipment for data transmission, input device and output device, terminal device and up-to-date terminal device.

Guide On Safety Tests

Energy Technology Data Exchange (ETDEWEB)

NONE

1987-05-15

This book tells US important things to do safety tests, which includes basic caution for experiment treatment of used materials such as ignition substance inflammables, explosive substance and toxic substance, handling of used equipment like inflammable device, machine, high pressure device, high pressure gas, and high energy device, first aid such as addiction by drug, flame, radiation exposure, and heart massage treatment of waste in laboratory like cautions on general treatment, handling of inorganic waste, organic waste and waste treatment with disposal facilities.

Guide On Safety Tests

International Nuclear Information System (INIS)

1987-05-01

This book tells US important things to do safety tests, which includes basic caution for experiment treatment of used materials such as ignition substance inflammables, explosive substance and toxic substance, handling of used equipment like inflammable device, machine, high pressure device, high pressure gas, and high energy device, first aid such as addiction by drug, flame, radiation exposure, and heart massage treatment of waste in laboratory like cautions on general treatment, handling of inorganic waste, organic waste and waste treatment with disposal facilities.

Development of a handmade device for collimation and central ray alignment tests in medical X-ray equipment

International Nuclear Information System (INIS)

Cruz, B.L. da; Brito, E.B.; Gomes, A.S.

2017-01-01

Ordinance 453/98 of the Ministry of Health establishes that medical X-ray equipment should be monitored by tests that prove its efficiency. This practice is called quality control (QC), and two important tests jointly evaluate the operation of the collimation and alignment systems of the central axis of the X-ray beam. The low supply and the high cost generate allegations of difficulties in the periodic realization of the tests. The aim of this work is to design, make and evaluate the performance of a handmade device for the mentioned tests, using low cost materials. Once built, the device had its performance evaluated and compared with the traditionally marketed device. The handmade device proved to be fit in its functions. It is possible to make a device that tests X-ray medical equipment, using the radiology technologist himself as the test runner. Radiation protection is promoted and legislation with no real financial burden

Safety of Magnetic Resonance Imaging in Patients with Cardiac Devices.

Science.gov (United States)

Nazarian, Saman; Hansford, Rozann; Rahsepar, Amir A; Weltin, Valeria; McVeigh, Diana; Gucuk Ipek, Esra; Kwan, Alan; Berger, Ronald D; Calkins, Hugh; Lardo, Albert C; Kraut, Michael A; Kamel, Ihab R; Zimmerman, Stefan L; Halperin, Henry R

2017-12-28

Patients who have pacemakers or defibrillators are often denied the opportunity to undergo magnetic resonance imaging (MRI) because of safety concerns, unless the devices meet certain criteria specified by the Food and Drug Administration (termed "MRI-conditional" devices). We performed a prospective, nonrandomized study to assess the safety of MRI at a magnetic field strength of 1.5 Tesla in 1509 patients who had a pacemaker (58%) or an implantable cardioverter-defibrillator (42%) that was not considered to be MRI-conditional (termed a "legacy" device). Overall, the patients underwent 2103 thoracic and nonthoracic MRI examinations that were deemed to be clinically necessary. The pacing mode was changed to asynchronous mode for pacing-dependent patients and to demand mode for other patients. Tachyarrhythmia functions were disabled. Outcome assessments included adverse events and changes in the variables that indicate lead and generator function and interaction with surrounding tissue (device parameters). No long-term clinically significant adverse events were reported. In nine MRI examinations (0.4%; 95% confidence interval, 0.2 to 0.7), the patient's device reset to a backup mode. The reset was transient in eight of the nine examinations. In one case, a pacemaker with less than 1 month left of battery life reset to ventricular inhibited pacing and could not be reprogrammed; the device was subsequently replaced. The most common notable change in device parameters (>50% change from baseline) immediately after MRI was a decrease in P-wave amplitude, which occurred in 1% of the patients. At long-term follow-up (results of which were available for 63% of the patients), the most common notable changes from baseline were decreases in P-wave amplitude (in 4% of the patients), increases in atrial capture threshold (4%), increases in right ventricular capture threshold (4%), and increases in left ventricular capture threshold (3%). The observed changes in lead parameters

Safety and effectiveness considerations for clinical studies of visual prosthetic devices

Science.gov (United States)

Cohen, Ethan D.

2007-03-01

With the advent of new designs of visual prostheses for the blind, FDA is faced with developing guidance for evaluating their engineering, safety and patient performance. Visual prostheses are considered significant risk medical devices, and their use in human clinical trials must be approved by FDA under an investigation device exemption (IDE). This paper contains a series of test topics and design issues that sponsors should consider in order to assess the safety and efficacy of their device. The IDE application includes a series of pre-clinical and clinical data sections. The pre-clinical section documents laboratory, animal and bench top performance tests of visual prostheses safety and reliability to support a human clinical trial. The materials used in constructing the implant should be biocompatible, sterile, corrosion resistant, and able to withstand any forces exerted on it during normal patient use. The clinical data section is composed of items related to patient-related evaluation of device performance. This section documents the implantation procedure, trial design, statistical analysis and how visual performance is assessed. Similar to cochlear implants, a visual prosthesis is expected to last in the body for many years, and good pre-clinical and clinical testing will help ensure its safety, durability and effectiveness.

Considerations concerning the reliability of reactor safety equipment

International Nuclear Information System (INIS)

Furet, J.; Guyot, Ch.

1967-01-01

A review is made of the circumstances which favor a good collection of maintenance data at the C.E.A. The large amount of data to be treated has made necessary the use of a computer for analyzing automatically the results collected. Here, only particular aspects of the reliability from the point of view of the electronics used for nuclear reactor control will be dealt with: sale and unsafe failures; probability of survival (in the case of reactor safety); availability. The general diagrams of the safety assemblies which have been drawn up for two types of reactor (power reactor and low power experimental reactor) are given. Results are presented of reliability analysis which could be applied to the use of functional modular elements, developed industrially in France. Improvement of this reliability appears to be fairly limited by an increase in the redundancy; on the other hand it is shown how it may be very markedly improved by the use of automatic tests with different frequencies for detecting unsafe failures rates of measurements for the sub-assemblies and for the logic sub-assemblies. Finally examples are given to show the incidence of the complexity and of the use of different technologies in reactor safety equipment on the reliability. (authors) [fr

Regulatory analysis for resolution of Unresolved Safety Issue A-46, seismic qualification of equipment in operating plants

International Nuclear Information System (INIS)

Chang, T.Y.; Anderson, N.R.

1987-02-01

The margin of safety provided in existing nuclear power plant equipment to resist seismically induced loads and perform required safety functions may vary considerably, because of significant changes in design criteria and methods for the seismic qualification of equipment over the years. Therefore, the seismic qualification of equipment in operating plants must be reassessed to determine whether requalification is necessary. The objective of technical studies performed under Task Action Plan A-46 was to establish an explicit set of guidelines and acceptance criteria to judge the adequacy of equipment under seismic loading at all operating plants, in lieu of requiring these plants to meet the criteria that are applied to new plants. This report presents the regulatory analysis for Unresolved Safety Issue (USI) A-46. It includes: Statement of the Problem; the Objective of USI A-46; a Summary of A-46 Tasks; a Proposed Implementation Procedure; a Value-Impact Analysis; Application of the Backfit Rule; 10 CFR 50.109; Implementation; and Operating Plants To Be Reviewed to USI A-46 Requirements

Autonomous booster device of a safety valve

International Nuclear Information System (INIS)

Namand, H.

1983-01-01

The invention concerns an autonomous booster device of a protection safety valve of a pressure vessel. The valve comprises a hollow structure, a seat connected with a mobile flap forming one piece with a stem and a calibration spring bearing on the stem and on the valve structure to maintain the flap bearing on the seat. The stem of the flap is prolongated in a box forming one piece with the valve structure and receives an added push of a spring. The box acts as a pressure device of which the piston can exercise on the stem a push opposite to and larger than the spring one. The feeding device of the pressure box is finally described in detail [fr

Auditing of Monitoring and Respiratory Support Equipment in a Level III-C Neonatal Intensive Care Unit

Directory of Open Access Journals (Sweden)

Elena Bergon-Sendin

2015-01-01

Full Text Available Background. Random safety audits (RSAs are a safety tool but have not been widely used in hospitals. Objectives. To determine the frequency of proper use of equipment safety mechanisms in relation to monitoring and mechanical ventilation by performing RSAs. The study also determined whether factors related to the patient, time period, or characteristics of the area of admission influenced how the device safety systems were used. Methods. A prospective observational study was conducted in a level III-C Neonatal Intensive Care Unit (NICU during 2012. 87 days were randomly selected. Appropriate overall use was defined when all evaluated variables were correctly programmed in the audited device. Results. A total of 383 monitor and ventilator audits were performed. The Kappa coefficient of interobserver agreement was 0.93. The rate of appropriate overall use of the monitors and respiratory support equipment was 33.68%. Significant differences were found with improved usage during weekends, OR 1.85 (1.12–3.06, p=0.01, and during the late shift (3 pm to 10 pm, OR 1.59 (1.03–2.4, p=0.03. Conclusions. Equipment safety systems of monitors and ventilators are not properly used. To improve patient safety, we should identify which alarms are really needed and where the difficulties lie for the correct alarm programming.

Study on a quantitative evaluation method of equipment maintenance level and plant safety level for giant complex plant system

International Nuclear Information System (INIS)

Aoki, Takayuki

2010-01-01

In this study, a quantitative method on maintenance level which is determined by the two factors, maintenance plan and field work implementation ability by maintenance crew is discussed. And also a quantitative evaluation method on safety level for giant complex plant system is discussed. As a result of consideration, the following results were obtained. (1) It was considered that equipment condition after maintenance work was determined by the two factors, maintenance plan and field work implementation ability possessed by maintenance crew. The equipment condition determined by the two factors was named as 'equipment maintenance level' and its quantitative evaluation method was clarified. (2) It was considered that CDF in a nuclear power plant, evaluated by using a failure rate counting the above maintenance level was quite different from CDF evaluated by using existing failure rates including a safety margin. Then, the former CDF was named as 'plant safety level' of plant system and its quantitative evaluation method was clarified. (3) Enhancing equipment maintenance level means an improvement of maintenance quality. That results in the enhancement of plant safety level. Therefore, plant safety level should be always watched as a plant performance indicator. (author)

Establishment of experimental equipments in irradiation technology development building (2)

International Nuclear Information System (INIS)

Shibata, Hiroshi; Nakano, Hiroko; Suzuki, Yoshitaka; Ohtsuka, Noriaki; Nishikata, Kaori; Takeuchi, Tomoaki; Hirota, Noriaki; Tsuchiya, Kunihiko

2018-01-01

From the viewpoints of utilization improvement of the Japan Materials Testing Reactor (JMTR), the experimental devices have been established for the out-pile tests in the irradiation technology development building. The devices for the irradiation capsule assembly, material tests and inspections were established at first and experimental data were accumulated before the neutron irradiation tests. On the other hand, after the Great East Japan Earthquake, the repairs and earthquake-resistant measures of the existing devices were carried out. New devices and equipments were also established for the R and D program for power plant safety enhancement of the Agency for Natural Resources and Energy, Ministry of Economy, Trade and Industry (METI) and 99 Mo/ 99m Tc production development under the Tsukuba International Strategic Zone. This report describes the outline and basic operation manuals of the devices established from 2011 to 2016 and the management points for the safety works in the irradiation technology development building. (author)

The design of an energy harvesting device for prolonging the working time of DC equipment

Science.gov (United States)

Wen, Yayuan; Deng, Huaxia; Zhang, Jin; Yu, Liandong

2016-01-01

Energy harvesting (EH) derives from the idea of converting the ambient energy into electric energy, which can solve the problem of DC supply for some electronic equipment. PZT is a typical piezoelectric material of inorganic, which has been developed as EH devices to transfer ambient vibration energy into electric energy. However, these PZT devices require relatively violent excitation, and easy to be fatigue fracture under the resonance condition. In this paper, PVDF, which is a kind of soft piezoelectric polymer, is adopted for developing transducer. The PVDF devices are flexible and have longer life time than PZT devices under the harmonic environment. The EH researches are mainly focused on the development of energy transfer efficiency either by the mechanical structure of transducer or the improvement of circuit. However, the practicality and stability of the EH devices are important in the practical engineering applications. In this paper, a charge amplifier is introduced in the circuit in order to guarantee the stability of the battery charging under small ambient vibration conditions. The model of the mechanical structure of PVDF and the electric performance of circuit are developed. The experimental results and simulation show that the stability of battery charging is improved and the working time of DC equipment is prolonged.

Technical diagnostics - equipment monitoring for increasing safety and availability of nuclear power plants

International Nuclear Information System (INIS)

Sturm, A.; Foerster, R.

1977-01-01

Utilization of technical diagnostics in equipment monitoring of nuclear power plants for ensuring nuclear safety, economic availability, and for decision making on necessary maintenance is reviewed. Technical diagnostics is subdivided into inspection and early detection of malfunctions. Moreover, combination of technical diagnostics and equipment monitoring, integration of technical diagnostics into maintenance strategy, and problems of introducing early detection of malfunctions into maintenance management of nuclear power plants are also discussed. In addition, a compilation of measuring techniques used in technical diagnostics has been made. The international state of the art of equipment monitoring in PWR nuclear power plants is illustrated by description of the sound and vibration measuring techniques. (author)

IE Information Notice No. 85-08: Industry experience on certain materials used in safety-related equipment

International Nuclear Information System (INIS)

Jordan, E.L.

1992-01-01

This information notice is being issued to provide licensees and construction permit holders with information pertaining to the behavior of certain materials used in safety-related equipment. The materials, as described below, were observed to have the potential of degrading the operability of safety-related equipment. These observations were made during environmental qualification testing and/or during routine inspection of in-service equipment. The notice describes the following: elastomeric seals used in personnel air locks for the reactor containment systems; epoxy phenolic coating applied to the lower portion of the interior surface of diesel oil storage tanks; the use of Viton elastomer as the seal material in hydrogen recombiner applications; and environmental qualification of ASCO NP valves with Viton and ethylene propylene parts

Supraglottic devices as alternative equipment to airway management in state of sudden cardiac arrest

Directory of Open Access Journals (Sweden)

Rafał Czyż

2017-08-01

All of supraglottic devices are characterized by easiness in applying without experience in use them. Additionally time need to airway management in use of them is many times shorter than with traditional endotracheal intubation. Fundamental defect in these devices is a fact that they don’t provide total safety before aspiration for chime. Current literature shows us that supraglottic airway devices are perfect alternative to endotracheal intubation.

Safety Evakuation Of Triga-2000 Reactor Operation Viewed From Safety Culture

International Nuclear Information System (INIS)

Karliana, Itjeu

2001-01-01

The safety evaluation activities of TRIGA-2000 operation viewed from safety culture performed by questioners data collected from the operators and supervisor site of TRIGA-2000 P3TN, Bandung. There are 9 activity aspects surveyed, for instant to avail the policy of safety from their chairman, safety management, education and training, emergency aids planning, safety consultancy, accident information, safety analysis, safety devices, safety and occupational health. The surveying undertaken by filling the questioner that containing of 9 activity aspects and 20 samples of employees. The safety evaluation results' of the operation personnel in TRIGA-2000 P3TN are good implemented by both the operators and supervisors should be improve and attention need to provide the equipment's. The education and training especially for safety refreshment must be performing

A Study on Performance and Safety Tests of Electrosurgical Equipment.

Science.gov (United States)

Tavakoli Golpaygani, A; Movahedi, M M; Reza, M

2016-09-01

Modern medicine employs a wide variety of instruments with different physiological effects and measurements. Periodic verifications are routinely used in legal metrology for industrial measuring instruments. The correct operation of electrosurgical generators is essential to ensure patient's safety and management of the risks associated with the use of high and low frequency electrical currents on human body. The metrological reliability of 20 electrosurgical equipment in six hospitals (3 private and 3 public) was evaluated in one of the provinces of Iran according to international and national standards. The achieved results show that HF leakage current of ground-referenced generators are more than isolated generators and the power analysis of only eight units delivered acceptable output values and the precision in the output power measurements was low. Results indicate a need for new and severe regulations on periodic performance verifications and medical equipment quality control program especially in high risk instruments. It is also necessary to provide training courses for operating staff in the field of meterology in medicine to be acquianted with critical parameters to get accuracy results with operation room equipment.

Interim staff position on environmental qualification of safety-related electrical equipment: including staff responses to public comments. Regulatory report

International Nuclear Information System (INIS)

Szukiewicz, A.J.

1981-07-01

This document provides the NRC staff positions regarding selected areas of environmental qualification of safety-related electrical equipment, in the resolution of Unresolved Safety Issue A-24, 'Qualification of Class IE Safety-Related Equipment.' The positions herein are applicable to plants that are or will be in the construction permit (CP) or operating license (OL) review process and that are required to satisfy the requirements set forth in either the 1971 or the 1974 version of IEEE-323 standard

Augmented reality for improved safety

CERN Multimedia

Stefania Pandolfi

2016-01-01

Sometimes, CERN experts have to operate in low visibility conditions or in the presence of possible hazards. Minimising the duration of the operation and reducing the risk of errors is therefore crucial to ensuring the safety of personnel. The EDUSAFE project integrates different technologies to create a wearable personnel safety system based on augmented reality.    The EDUSAFE integrated safety system uses a camera mounted on the helmet to monitor the working area.  In its everyday operation of machines and facilities, CERN adopts a whole set of measures and safety equipment to ensure the safety of its personnel, including personal wearable safety devices and access control systems. However, sometimes, scheduled and emergency maintenance work needs to be done in zones with potential cryogenic hazards, in the presence of radioactive equipment or simply in demanding conditions where visibility is low and moving around is difficult. The EDUSAFE Marie Curie Innovative&...

Product-based Safety Certification for Medical Devices Embedded Software.

Science.gov (United States)

Neto, José Augusto; Figueiredo Damásio, Jemerson; Monthaler, Paul; Morais, Misael

2015-01-01

Worldwide medical device embedded software certification practices are currently focused on manufacturing best practices. In Brazil, the national regulatory agency does not hold a local certification process for software-intensive medical devices and admits international certification (e.g. FDA and CE) from local and international industry to operate in the Brazilian health care market. We present here a product-based certification process as a candidate process to support the Brazilian regulatory agency ANVISA in medical device software regulation. Center of Strategic Technology for Healthcare (NUTES) medical device embedded software certification is based on a solid safety quality model and has been tested with reasonable success against the Class I risk device Generic Infusion Pump (GIP).

Radiation Safety in Industrial Radiography. Specific Safety Guide

International Nuclear Information System (INIS)

2011-01-01

This Safety Guide provides recommendations for ensuring radiation safety in industrial radiography used in non-destructive testing. This includes industrial radiography work that utilizes X ray and gamma sources, both in shielded facilities that have effective engineering controls and in outside shielded facilities using mobile sources. Contents: 1. Introduction; 2. Duties and responsibilities; 3. Safety assessment; 4. Radiation protection programme; 5. Training and qualification; 6. Individual monitoring of workers; 7. Workplace monitoring; 8. Control of radioactive sources; 9. Safety of industrial radiography sources and exposure devices; 10. Radiography in shielded enclosures; 11. Site radiography; 12. Transport of radioactive sources; 13. Emergency preparedness and response; Appendix: IAEA categorization of radioactive sources; Annex I: Example safety assessment; Annex II: Overview of industrial radiography sources and equipment; Annex III: Examples of accidents in industrial radiography.

The method for assurance to operational safety of cryogenics equipment through definite maintenance

International Nuclear Information System (INIS)

Anghel, Vasile

2004-01-01

The present paper reports about a method of ensuring operational safety of cryogenics equipment through specific maintenance measures which imply a definite concept of maintainability and operational reliability, methods of maintenance, necessary logistic and necessary personnel. The stages of the concept should succeed in a logical order and must be based on detailed analyses of the process of maintenance. The method starts from the operation conditions of cryogenic equipment in nuclear regime. Thus maintenance policy must be well defined within the boundaries of the nuclear plant through definition of coherent objectives and responsibility delegation for the personnel implied in maintenance activity. This method ensures performance in maintenance and an efficient feedback from equipment analysis. (author)

Investigation of potential fire-related damage to safety-related equipment in nuclear power plants

International Nuclear Information System (INIS)

Wanless, J.

1985-11-01

Based on a review of vendor information, fire damage reports, equipment qualification and hydrogen burn test results, and material properties, thirty-three types of equipment found in nuclear power plants were ranked in terms of their potential sensitivity to fire environments. The ranking considered both the functional requirements and damage proneness of each component. A further review of the seven top-ranked components was performed, considering the relative prevalence and potential safety significance of each. From this, relays and hand switches dominate as first choices for fire damage testing with logic equipment, power supplies, transmitters, and motor control centers as future candidates

Co-operation Equipment Qualification for Safety grade I and C Equipment between Russia and Korea

International Nuclear Information System (INIS)

Ham, J. K.; Lee, D. H.; Park, J. W.; Jeong, M. H.; Choi, Y. H.; Suh, J. J.; Jang, T. H.

2007-06-01

Equipment Qualification technology for I and C system on nuclear grade have been approved with accurate and safe for verifying and validation. It contributes to acknowledge of reliability and to review of user approval. Also it did not completely satisfied the requirement of Russia, it can be satisfied by bit of modification on design. It is expected to support the export of safety PLC to nuclear power plant. Proven EQ technology is required on the further markets of nuclear. Therefore, comparison test with foreign country is necessary to support the mutual accreditation of EQ for export of domestic products

Co-operation Equipment Qualification for Safety grade I and C Equipment between Russia and Korea

Energy Technology Data Exchange (ETDEWEB)

Ham, J. K.; Lee, D. H.; Park, J. W.; Jeong, M. H.; Choi, Y. H.; Suh, J. J.; Jang, T. H. [Korea Testing Laboratory, Seoul (Korea, Republic of)

2007-06-15

Equipment Qualification technology for I and C system on nuclear grade have been approved with accurate and safe for verifying and validation. It contributes to acknowledge of reliability and to review of user approval. Also it did not completely satisfied the requirement of Russia, it can be satisfied by bit of modification on design. It is expected to support the export of safety PLC to nuclear power plant. Proven EQ technology is required on the further markets of nuclear. Therefore, comparison test with foreign country is necessary to support the mutual accreditation of EQ for export of domestic products.

Design and construction of engineering test device of a multi-purpose radwaste incineration system

International Nuclear Information System (INIS)

Wang Peiyi; Zhou Lianquan; Ma Mingxie; Qiu Mingcai; Yang Liguo; Li Xiaohai; Zhang Xiaobin; Lu Xiaowu; Dong Jingling; Wang Xujin; Li Chuanlian; Yang Baomin

2002-01-01

The author describes designs of main un-standard devices, monitoring system and safety system, as well as construction of the engineering system devices for a multi-purpose radwaste incineration system. Un-standard devices include waste crusher, pyrolysis furnace, incinerator furnace, cool stream dilution device and bag filter, etc. The monitoring system mainly includes industrial controlled computer, supported by conventional electrical equipment and instruments. Designs of system safety takes account of containment of radioactive materials fire-prevention, explosion prevention, anti-corrosion, redundance and reservation, emergency system, controlling and electric safety system, etc. Results show that main technological system remains good airtight with leakage ratio at 0.67%

Increasing the Usage of Personal Protective Equipments in Constructing Subway Stations: An Application of Social Marketing Model

Directory of Open Access Journals (Sweden)

M Shams

2013-10-01

Full Text Available Abstract Background & aim: Although the relationship between the use of personal protective equipment and the reduction of workplace injuries is well-known the use of these devices during operation by the staff is not so desirable. This study was based on a model of social marketing interventions to increase the use of safety devices and personal protection on the subway-station staff. Methods: The present quasi-experimental study was based on the results of a formative research consisted of a qualitative (exploring employees’ views through focus group discussions and a quantitative study (measuring attitudes and behaviors by questionnaire and checklist. Based on the formative research findings, a free package includes a helmet with a label containing the message, an anti-cut safety gloves, a dust mask, and an educational pamphlet were delivered to intervention group. After four weeks, the check list of observational behaviors in two constructing stations was completed and the results were compared with before intervention. The data were analyzed by paired t-test, t-test and logistic regression. Results: Three common behaviors were observed among staff not using caps, masks and gloves. The odds ratio for helmet and mask usage in the intervention group was more than other groups. After the intervention, the use of safety helmets and masks significantly increased (p < 0.05. The odds ratio for the use of helmets and masks after intervention in the intervention group was significantly higher than other groups (p < 0.05. Conclusion: The experimental basis of the safety devices and personal protection needs and demands of the audience, material and immaterial costs of the equipment, supplies, and promoting their use in the right place, can encourage the staff to continuously use the safety devices at workplace. Key Words: Workplace, Injuries, Personal Protective Equipment, Social Marketing

Methods for medical device and equipment procurement and prioritization within low- and middle-income countries: findings of a systematic literature review.

Science.gov (United States)

Diaconu, Karin; Chen, Yen-Fu; Cummins, Carole; Jimenez Moyao, Gabriela; Manaseki-Holland, Semira; Lilford, Richard

2017-08-18

Forty to 70 % of medical devices and equipment in low- and middle-income countries are broken, unused or unfit for purpose; this impairs service delivery to patients and results in lost resources. Undiscerning procurement processes are at the heart of this issue. We conducted a systematic review of the literature to August 2013 with no time or language restrictions to identify what product selection or prioritization methods are recommended or used for medical device and equipment procurement planning within low- and middle-income countries. We explore the factors/evidence-base proposed for consideration within such methods and identify prioritization criteria. We included 217 documents (corresponding to 250 texts) in the narrative synthesis. Of these 111 featured in the meta-summary. We identify experience and needs-based methods used to reach procurement decisions. Equipment costs (including maintenance) and health needs are the dominant issues considered. Extracted data suggest that procurement officials should prioritize devices with low- and middle-income country appropriate technical specifications - i.e. devices and equipment that can be used given available human resources, infrastructure and maintenance capacity. Suboptimal device use is directly linked to incomplete costing and inadequate consideration of maintenance services and user training during procurement planning. Accurate estimation of life-cycle costing and careful consideration of device servicing are of crucial importance.

Safety device for nuclear reactors

International Nuclear Information System (INIS)

Gruhl, H.

1974-01-01

The safety device is used to capture fragments of the lid of a pressure vessel when this vessel ruptures. It consists of a catcher structure attached to the concrete vessel, which is open at the top, and surrounding the pressure vessel. The catcher structure in this case may be designed as a ring installed very close to the concrete vessel, as a closure plate or may be made of transverse beams arranged parallel to each other. It is anchored either rigidly or elastically to the concrete vessel by means of springs or to the foundation by means of steel stretching members. (DG) [de

A Study on Performance and Safety Tests of Electrosurgical Equipment

Directory of Open Access Journals (Sweden)

Tavakoli Golpaygani A.

2016-09-01

Full Text Available Introduction: Modern medicine employs a wide variety of instruments with different physiological effects and measurements. Periodic verifications are routinely used in legal metrology for industrial measuring instruments. The correct operation of electrosurgical generators is essential to ensure patient’s safety and management of the risks associated with the use of high and low frequency electrical currents on human body. Material and Methods: The metrological reliability of 20 electrosurgical equipment in six hospitals (3 private and 3 public was evaluated in one of the provinces of Iran according to international and national standards. Results: The achieved results show that HF leakage current of ground-referenced generators are more than isolated generators and the power analysis of only eight units delivered acceptable output values and the precision in the output power measurements was low. Conclusion: Results indicate a need for new and severe regulations on periodic performance verifications and medical equipment quality control program especially in high risk instruments. It is also necessary to provide training courses for operating staff in the field of meterology in medicine to be acquianted with critical parameters to get accuracy results with operation room equipment.

21 CFR 866.4540 - Immunonephelometer equipment.

Science.gov (United States)

2010-04-01

...) MEDICAL DEVICES IMMUNOLOGY AND MICROBIOLOGY DEVICES Immunology Laboratory Equipment and Reagents § 866.4540 Immunonephelometer equipment. (a) Identification. Immunonephelometer equipment for clinical use...

MRI with cardiac pacing devices – Safety in clinical practice

Energy Technology Data Exchange (ETDEWEB)

Kaasalainen, Touko, E-mail: touko.kaasalainen@hus.fi [HUS Medical Imaging Center, Helsinki University Central Hospital, POB 340 (Haartmaninkatu 4), 00290 Helsinki (Finland); Department of Physics, University of Helsinki (Finland); Pakarinen, Sami, E-mail: sami.pakarinen@hus.fi [HUS Department of Cardiology, Helsinki University Central Hospital, POB 340 (Haartmaninkatu 4), 00290 Helsinki (Finland); Kivistö, Sari, E-mail: sari.kivisto@hus.fi [HUS Medical Imaging Center, Helsinki University Central Hospital, POB 340 (Haartmaninkatu 4), 00290 Helsinki (Finland); Holmström, Miia, E-mail: miia.holmstrom@hus.fi [HUS Medical Imaging Center, Helsinki University Central Hospital, POB 340 (Haartmaninkatu 4), 00290 Helsinki (Finland); Hänninen, Helena, E-mail: helena.hanninen@hus.fi [HUS Department of Cardiology, Helsinki University Central Hospital, POB 340 (Haartmaninkatu 4), 00290 Helsinki (Finland); Peltonen, Juha, E-mail: juha.peltonen@hus.fi [HUS Medical Imaging Center, Helsinki University Central Hospital, POB 340 (Haartmaninkatu 4), 00290 Helsinki (Finland); Department of Biomedical Engineering and Computational Science, School of Science, Aalto University, Helsinki (Finland); Lauerma, Kirsi, E-mail: kirsi.lauerma@hus.fi [HUS Medical Imaging Center, Helsinki University Central Hospital, POB 340 (Haartmaninkatu 4), 00290 Helsinki (Finland); Sipilä, Outi, E-mail: outi.sipila@hus.fi [HUS Medical Imaging Center, Helsinki University Central Hospital, POB 340 (Haartmaninkatu 4), 00290 Helsinki (Finland)

2014-08-15

Objectives: The aim of this study was to introduce a single centre “real life” experience of performing MRI examinations in clinical practice on patients with cardiac pacemaker systems. Additionally, we aimed to evaluate the safety of using a dedicated safety protocol for these patients. Materials and methods: We used a 1.5 T MRI scanner to conduct 68 MRI scans of different body regions in patients with pacing systems. Of the cardiac devices, 32% were MR-conditional, whereas the remaining 68% were MR-unsafe. We recorded the functional parameters of the devices prior, immediately after, and approximately one month after the MRI scanning, and compared the device parameters to the baseline values. Results: All MRI examinations were completed safely, and each device could be interrogated normally following the MRI. We observed no changes in the programmed parameters of the devices. For most of the participants, the distributions of the immediate and one-month changes in the device parameters were within 20% of the baseline values, although some changes approached clinically important thresholds. Furthermore, we observed no differences in the variable changes between MR-conditional and MR-unsafe pacing systems, or between scans of the thorax area and other scanned areas. Conclusion: MRI in patients with MR-conditional pacing systems and selected MR-unsafe systems could be performed safely under strict conditions in this study.

21 CFR 866.4520 - Immunofluorometer equipment.

Science.gov (United States)

2010-04-01

...) MEDICAL DEVICES IMMUNOLOGY AND MICROBIOLOGY DEVICES Immunology Laboratory Equipment and Reagents § 866.4520 Immunofluorometer equipment. (a) Identification. Immunofluorometer equipment for clinical use with...

An examination of safety reports involving electronic flight bags and portable electronic devices

Science.gov (United States)

2014-06-01

The purpose of this research was to develop a better understanding of safety considerations with the use of Electronic Flight Bags (EFBs) and Portable Electronic Devices (PEDs) by examining safety reports from Aviation Safety Reporting System (ASRS),...

The Role of Patient Safety in the Device Purchasing Process

National Research Council Canada - National Science Library

Johnson, Todd R; Zhang, Jiajie; Patel, Vimla L; Keselman, Alla; Tang, Xiaozhou; Brixey, Juliana J; Paige, Danielle; Turley, James P

2005-01-01

To examine how patient safety considerations are incorporated into medical device purchase decisions, individuals involved in recent infusion pump purchasing decisions at three different health care...

Safety considerations in the design of the Fusion Engineering Device

International Nuclear Information System (INIS)

Barrett, R.J.

1983-01-01

The US Department of Energy (DOE) regulations and guidelines for radiation protection have been reviewed and are being applied to the device design. Direct radiation protection is provided by the device shield and the reactor building walls. Radiation from the activated device components and the tritium fuel is to be controlled with shielding, contamination control, and ventilation. The potential release of tritium from the plant has influenced the selection of reactor building and plant designs and specifications. The safety of the plant workers is affected primarily by the radiation from the activated device components and from plasma chamber debris

30 CFR 77.506 - Electric equipment and circuits; overload and short-circuit protection.

Science.gov (United States)

2010-07-01

... short-circuit protection. 77.506 Section 77.506 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION... circuits; overload and short-circuit protection. Automatic circuit-breaking devices or fuses of the correct type and capacity shall be installed so as to protect all electric equipment and circuits against short...

Radiation Safety in Industrial Radiography. Specific Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2013-01-01

This Safety Guide provides recommendations for ensuring radiation safety in industrial radiography used in non-destructive testing. This includes industrial radiography work that utilizes X ray and gamma sources, both in shielded facilities that have effective engineering controls and in outside shielded facilities using mobile sources. Contents: 1. Introduction; 2. Duties and responsibilities; 3. Safety assessment; 4. Radiation protection programme; 5. Training and qualification; 6. Individual monitoring of workers; 7. Workplace monitoring; 8. Control of radioactive sources; 9. Safety of industrial radiography sources and exposure devices; 10. Radiography in shielded enclosures; 11. Site radiography; 12. Transport of radioactive sources; 13. Emergency preparedness and response; Appendix: IAEA categorization of radioactive sources; Annex I: Example safety assessment; Annex II: Overview of industrial radiography sources and equipment; Annex III: Examples of accidents in industrial radiography

Radiation Safety in Industrial Radiography. Specific Safety Guide (French Edition)

International Nuclear Information System (INIS)

2013-01-01

This Safety Guide provides recommendations for ensuring radiation safety in industrial radiography used in non-destructive testing. This includes industrial radiography work that utilizes X ray and gamma sources, both in … shielded facilities that have effective engineering controls and in outside shielded facilities using mobile sources. Contents: 1. Introduction; 2. Duties and responsibilities; 3. Safety assessment; 4. Radiation protection programme; 5. Training and qualification; 6. Individual monitoring of workers; 7. Workplace monitoring; 8. Control of radioactive sources; 9. Safety of industrial radiography sources and exposure devices; 10. Radiography in shielded enclosures; 11. Site radiography; 12. Transport of radioactive sources; 13. Emergency preparedness and response; Appendix: IAEA categorization of radioactive sources; Annex I: Example safety assessment; Annex II: Overview of industrial radiography sources and equipment; Annex III: Examples of accidents in industrial radiography

Radiation Safety in Industrial Radiography. Specific Safety Guide (Arabic Edition)

International Nuclear Information System (INIS)

2012-01-01

This Safety Guide provides recommendations for ensuring radiation safety in industrial radiography used in non-destructive testing. This includes industrial radiography work that utilizes X ray and gamma sources, both in shielded facilities that have effective engineering controls and outside shielded facilities using mobile sources. Contents: 1. Introduction; 2. Duties and responsibilities; 3. Safety assessment; 4. Radiation protection programme; 5. Training and qualification; 6. Individual monitoring of workers; 7. Workplace monitoring; 8. Control of radioactive sources; 9. Safety of industrial radiography sources and exposure devices; 10. Radiography in shielded enclosures; 11. Site radiography; 12. Transport of radioactive sources; 13. Emergency preparedness and response; Appendix: IAEA categorization of radioactive sources; Annex I: Example safety assessment; Annex II: Overview of industrial radiography sources and equipment; Annex III: Examples of accidents in industrial radiography.

Motorcycle safety device investigation: A case study on airbags

Indian Academy of Sciences (India)

analysis methods for research evaluation of rider crash protective devices fitted to ... The safety evaluation is then based on simulation of the 200 impact types. ... with recording of ISO 13232 car-front impact tests to evaluate the qualitative.

On safety 1E qualification of electrical equipment for nuclear power stations

International Nuclear Information System (INIS)

Segarceanu, D.; Geambasu, C.; Avramescu, M.

1995-01-01

Electrical equipment and systems for the emergency shutdown of a nuclear reactor are qualified according to safety class 1E. Methods of qualification meeting the requirements should be used, either individually or in combination include, type-test qualification, qualification by operating experience, qualification by analysis, combined qualification. These methods qualification principles, procedures and documents are discussed. (N.T.). 1 fig

Electromagnetic interference from radio frequency identification inducing potentially hazardous incidents in critical care medical equipment

NARCIS (Netherlands)

Togt, R. van der; Lieshout, E.J. van; Hensbroek, R.; Beinat, E.; Binnekade, J.M.; Bakker, P.J.M.

2008-01-01

Context: Health care applications of autoidentification technologies, such as radio frequency identification (RFID), have been proposed to improve patient safety and also the tracking and tracing of medical equipment. However, electromagnetic interference (EMI) by RFID on medical devices has never

Seismic response analysis of Wolsung NPP structure and equipment subjected to scenario earthquakes

Energy Technology Data Exchange (ETDEWEB)

Choi, In Kil; Ahn, Seong Moon; Choun, Young Sun; Seo, Jeong Moon

2005-03-15

The standard response spectrum proposed by US NRC has been used as a design earthquake for the design of Korean nuclear power plant structures. However, it does not reflect the characteristic of seismological and geological of Korea. In this study, the seismic response analysis of Wolsung NPP structure and equipment were performed. Three types of input motions, artificial time histories that envelop the US NRC Regulatory Guide 1.60 spectrum and the probability based scenario earthquake spectra developed for the Korean NPP site and a typical near-fault earthquake recorded at thirty sites, were used as input motions. The acceleration, displacement and shear force responses of Wolsung containment structure due to the design earthquake were larger than those due to the other input earthquakes. But, considering displacement response increases abruptly as Wolsung NPP structure does nonlinear behavior, the reassessment of the seismic safety margin based on the displacement is necessary if the structure does nonlinear behavior; although it has adequate the seismic safety margin within elastic limit. Among the main safety-related devices, electrical cabinet and pump showed the large responses on the scenario earthquake which has the high frequency characteristic. This has great effects of the seismic capacity of the main devices installed inside of the building. This means that the design earthquake is not so conservative for the safety of the safety related nuclear power plant equipments.

Seismic response analysis of Wolsung NPP structure and equipment subjected to scenario earthquakes

International Nuclear Information System (INIS)

Choi, In Kil; Ahn, Seong Moon; Choun, Young Sun; Seo, Jeong Moon

2005-03-01

The standard response spectrum proposed by US NRC has been used as a design earthquake for the design of Korean nuclear power plant structures. However, it does not reflect the characteristic of seismological and geological of Korea. In this study, the seismic response analysis of Wolsung NPP structure and equipment were performed. Three types of input motions, artificial time histories that envelop the US NRC Regulatory Guide 1.60 spectrum and the probability based scenario earthquake spectra developed for the Korean NPP site and a typical near-fault earthquake recorded at thirty sites, were used as input motions. The acceleration, displacement and shear force responses of Wolsung containment structure due to the design earthquake were larger than those due to the other input earthquakes. But, considering displacement response increases abruptly as Wolsung NPP structure does nonlinear behavior, the reassessment of the seismic safety margin based on the displacement is necessary if the structure does nonlinear behavior; although it has adequate the seismic safety margin within elastic limit. Among the main safety-related devices, electrical cabinet and pump showed the large responses on the scenario earthquake which has the high frequency characteristic. This has great effects of the seismic capacity of the main devices installed inside of the building. This means that the design earthquake is not so conservative for the safety of the safety related nuclear power plant equipments

Use of individual protection equipment and collective in case of accident during the transport of radioactive product - class 7

International Nuclear Information System (INIS)

Pastura, Valeria da F. e S.; Carvalho, Natanael Bruno de

2013-01-01

The personal protective equipment (PPE) are devices used by professionals against potential radiological hazards that may threaten the health or safety in the event of an accident or incident during the transport of radioactive material. The collective protection equipment (CPE) devices are used in place of the accident in order to protect people and the environment from risks such as safety signs, among others. This work will be part of the new edition of the NBR 9735 - Set of equipment for emergencies in land transport of dangerous goods - edited by the Brazilian Association of Technical Standards ABNT - National Standardization Forum which CNEN participates in the Study Committee - CB16 namely, dangerous, accounting for Class 7 radioactive materials. The Standard 9735 establishes the minimum set of equipment for emergencies in Inland transport of dangerous goods, consisting of protective equipment to be used by the driver and staff involved (if any) in the transport operations of transport units, equipment for signaling, isolation of the area of occurrence (fault, accident and/or emergency). Thus, we will present a set of individual and collective equipment that must accompany the carriage of Class 7 products to meet the radiological accident situations and also establish a training base for the driver as the use of them. (author)

Device for positioning and generation of an element of track model and slice of the MELAS automatic equipment

International Nuclear Information System (INIS)

Kryutchenko, E.V.; Fedotov, V.S.

1979-01-01

The structure and organization of the device for positioning and generation of element of track model and slice of the MELAS automatic equipment which is developed for measuring films from big bubble chambers, is described. Main features of the device are studied and characteristics are given as well

Analysis of Medical Equipment Management in Relation to the Mandatory Medical Equipment Safety Manager (MESM in Japan

Directory of Open Access Journals (Sweden)

Kai Ishida

2014-01-01

Full Text Available Half a decade has passed since the fifth revision of the medical law and mandatory appointment of a medical equipment safety manager (MESM in hospitals in Japan. During this period, circumstances have changed regarding maintenance of medical equipment (ME. We conducted a survey to examine these changes and the current situation in ME management. Maintenance of ME and related work were found to have increased in many hospitals, but the number of clinical engineering technologists (CETs has only slightly increased. The appointed MESM was a CET or physician in most hospitals. In hospitals where physicians were appointed as the MESM, 81% had operation managers. Many respondents commented that it was difficult for one person to cover all the tasks required by the MESM, due to a lack of knowledge, too much work, or other reasons. This suggests the importance of an operation manager for ME to work under the MESM.

Recommended safety guides for industrial laboratories and shops

Science.gov (United States)

Allison, W. W.

1971-01-01

Booklet provides references to 29 publications providing information on hazard control and approved safety practices. Areas include pressurized gas and vacuum systems. Guidelines are presented for safeguarding facilities where machinery, equipment, electrical devices, or hazardous chemicals are used.

Universal Safety Distance Alert Device for Road Vehicles

Directory of Open Access Journals (Sweden)

Matic Virant

2016-04-01

Full Text Available Driving with too short of a safety distance is a common problem in road traffic, often with traffic accidents as a consequence. Research has identified a lack of vehicle-mountable devices for alerting the drivers of trailing vehicles about keeping a sufficient safe distance. The principal requirements for such a device were defined. A conceptual study was performed in order to select the components for the integration of the device. Based on the results of this study, a working prototype of a flexible, self-contained device was designed, built and tested. The device is intended to be mounted on the rear of a vehicle. It uses radar as the primary distance sensor, assisted with a GPS receiver for velocity measurement. A Raspberry Pi single-board computer is used for data acquisition and processing. The alerts are shown on an LED-matrix display mounted on the rear of the host vehicle. The device software is written in Python and provides automatic operation without requiring any user intervention. The tests have shown that the device is usable on almost any motor vehicle and performs reliably in simulated and real traffic. The open issues and possibilities for future improvements are presented in the Discussion.

Condition Monitoring and Fault Diagnosis for an Antifalling Safety Device

Directory of Open Access Journals (Sweden)

Guangxiang Yang

2015-01-01

Full Text Available There is a constant need for the safe operation and reliability of antifalling safety device (AFSD of an elevator. This paper reports an experimental study on rotation speed and catching torque monitoring and fault diagnosis of an antifalling safety device in a construction elevator. Denoising the signal using wavelet transform is presented in this paper. Based on the denoising effects for several types of wavelets, the sym8 wavelet basis, which introduces the high order approximation and an adaptive threshold, is employed for denoising the signal. The experimental result shows a maximum data error reduction of 7.5% is obtained and SNRs (signal-to-noise ratio of rotation speed and catching torque are improved for 3.9% and 6.4%, respectively.

Seismic qualification of equipment in operating nuclear power plants: Unresolved Safety Issue A-46

International Nuclear Information System (INIS)

Chang, T.Y.

1987-02-01

The margin of safety provided in existing nuclear power plant equipment to resist seismically induced loads and perform their intended safety functions may vary considerably, because of significant changes in design criteria and methods for the seismic qualification of equipment over the years. Therefore, the seismic qualification of equipment in operating plants must be reassessed to determine whether requalification is necessary. The objective of technical studies performed under the Task Action Plan A-46 was to establish an explicit set of guidelines and acceptance criteria to judge the adequacy of equipment under seismic loading at all operating plants, in lieu of requiring qualification to the current criteria that are applied to new plants. This report summarizes the work accomplished on USI A-46. In addition, the collection and review of seismic experience data and existing seismic test data are presented. Staff assessment of work accomplished under USI A-46 leads to the conclusion that the use of seismic experience data provides the most reasonable alternative to current qualification criteria. Consideration of seismic qualification by use of experience data was a specific task in USI A-46. Several other A-46 tasks serve to support the use of an experienced data base. The principal technical finding of USI A-46 is that seismic experience data, supplemented by existing seismic test data, applied in accordance with the guidelines developed, can be used to verify the seismic adequacy of mechanical and electrical equipment in operating nuclear plants. Explicit seismic qualification should be required only if seismic experience data or existing test data on similar components cannot be shown to apply

Industrial high pressure applications. Processes, equipment and safety

Energy Technology Data Exchange (ETDEWEB)

Eggers, Rudolf (ed.) [Technische Univ. Hamburg-Harburg, Hamburg (Germany). Inst. fuer Thermische Verfahrenstechnik

2012-07-01

Industrial high pressure processes open the door to many reactions that are not possible under 'normal' conditions. These are to be found in such different areas as polymerization, catalytic reactions, separations, oil and gas recovery, food processing, biocatalysis and more. The most famous high pressure process is the so-called Haber-Bosch process used for fertilizers and which was awarded a Nobel prize. Following an introduction on historical development, the current state, and future trends, this timely and comprehensive publication goes on to describe different industrial processes, including methanol and other catalytic syntheses, polymerization and renewable energy processes, before covering safety and equipment issues. With its excellent choice of industrial contributions, this handbook offers high quality information not found elsewhere, making it invaluable reading for a broad and interdisciplinary audience.

78 FR 16358 - Safety Advisory 2013-02; Low-Speed, Wheel-Climb Derailments of Passenger Equipment With “Stiff...

Science.gov (United States)

2013-03-14

..., Staff Director, Motive Power and Equipment Division, Office of Railroad Safety, FRA, 1200 New Jersey Avenue SE., Washington, DC 20590, telephone (202) 493-6322; or Anna Nassif Winkle, Trial Attorney, Office... studies conducted by the equipment manufacturer and FRA using computer modeling indicate that an uneven...

Regulations No. 59 of 20 February 1978 on X-ray skin therapy equipment up to 50 kV

International Nuclear Information System (INIS)

1978-01-01

These regulations lay down the provisions to be complied with for the protection of medical staff and patients when using X-ray equipment for skin therapy. The operators of such equipment must comply with the technical guidelines contained in the regulations and provision is made for annual inspections to ensure that the devices meet the necessary safety standards. (NEA) [fr

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

Science.gov (United States)

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

2018-03-01

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

Position measuring device

International Nuclear Information System (INIS)

Maeda, Kazuyuki; Takahashi, Shuichi; Maruyama, Mayumi

1998-01-01

The present invention provides a device capable of measuring accurate position and distance easily even at places where operator can not easily access, such as cell facilities for vitrifying radioactive wastes. Referring to a case of the vitrifying cell, an objective equipment settled in the cell is photographed by a photographing device. The image is stored in a position measuring device by way of an image input device. After several years, when the objective equipment is exchanged, a new objective equipment is photographed by a photographing device. The image is also stored in the position measuring device. The position measuring device compares the data of both of the images on the basis of pixel unit. Based on the image of the equipment before the exchange as a reference, extent of the displacement of the installation position of the equipment on the image after the exchange caused by installation error and manufacturing error is determined to decide the position of the equipment after exchange relative to the equipment before exchange. (I.S.)

Safety of nursing staff and determinants of adherence to personal protective equipment

OpenAIRE

Neves,Heliny Carneiro Cunha; Souza,Adenícia Custódia Silva e; Medeiros,Marcelo; Munari,Denize Bouttelet; Ribeiro,Luana Cássia Miranda; Tipple,Anaclara Ferreira Veiga

2011-01-01

A qualitative study conducted in a teaching hospital with 15 nursing professionals. Attempted to analyze the reasons, attitudes and beliefs of nursing staff regarding adherence to personal protective equipment. Data were collected through focus groups, analyzed by the method of interpretation of meanings, considering Rosenstock’s model of health beliefs as a reference framework. Data revealed two themes: Occupational safety and Interpersonal Relationship. We identified several barriers that i...

Safety analysis report for packaging onsite long-length contaminated equipment transport system

International Nuclear Information System (INIS)

McCormick, W.A.

1997-01-01

This safety analysis report for packaging describes the components of the long-length contaminated equipment (LLCE) transport system (TS) and provides the analyses, evaluations, and associated operational controls necessary for the safe use of the LLCE TS on the Hanford Site. The LLCE TS will provide a standardized, comprehensive approach for the disposal of approximately 98% of LLCE scheduled to be removed from the 200 Area waste tanks

Safety analysis report for packaging, onsite, long-length contaminated equipment transport system

Energy Technology Data Exchange (ETDEWEB)

McCormick, W.A.

1997-05-09

This safety analysis report for packaging describes the components of the long-length contaminated equipment (LLCE) transport system (TS) and provides the analyses, evaluations, and associated operational controls necessary for the safe use of the LLCE TS on the Hanford Site. The LLCE TS will provide a standardized, comprehensive approach for the disposal of approximately 98% of LLCE scheduled to be removed from the 200 Area waste tanks.

Quality and safety based management of radiological and clinical equipment

International Nuclear Information System (INIS)

Arora, S.; Saini, P.S.

2001-01-01

TQM (Total quality management) is the 'buzz' acronym expected in almost every aspect of industrial manufacturing, product development and services solicited by the outside agencies. The correct management of the many technological resources in health institutions in terms of efficiency, effectiveness and safety is a necessity in view of the criteria on which modern medicine is based. Almost all activities -be they diagnostic, therapeutic and rehabilitative - carried out within a modern hospital are based on widespread application of equipment and technology, the efficiency of which can directly influence the quality of service offered to the patient

Radiation emitting devices regulations

International Nuclear Information System (INIS)

1970-01-01

The Radiation Emitting Devices Regulations are the regulations referred to in the Radiation Emitting Devices Act and relate to the operation of devices. They include standards of design and construction, standards of functioning, warning symbol specifications in addition to information relating to the seizure and detention of machines failing to comply with the regulations. The radiation emitting devices consist of the following: television receivers, extra-oral dental x-ray equipment, microwave ovens, baggage inspection x-ray devices, demonstration--type gas discharge devices, photofluorographic x-ray equipment, laser scanners, demonstration lasers, low energy electron microscopes, high intensity mercury vapour discharge lamps, sunlamps, diagnostic x-ray equipment, ultrasound therapy devices, x-ray diffraction equipment, cabinet x-ray equipment and therapeutic x-ray equipment

Simulating The Technological Movements Of The Equipment Used For Manufacturing Prosthetic Devices Using 3D Models

Science.gov (United States)

Chicea, Anca-Lucia

2015-09-01

The paper presents the process of building geometric and kinematic models of a technological equipment used in the process of manufacturing devices. First, the process of building the model for a six axes industrial robot is presented. In the second part of the paper, the process of building the model for a five-axis CNC milling machining center is also shown. Both models can be used for accurate cutting processes simulation of complex parts, such as prosthetic devices.

30 CFR 77.506-1 - Electric equipment and circuits; overload and short circuit protection; minimum requirements.

Science.gov (United States)

2010-07-01

... short circuit protection; minimum requirements. 77.506-1 Section 77.506-1 Mineral Resources MINE SAFETY...-1 Electric equipment and circuits; overload and short circuit protection; minimum requirements. Devices providing either short circuit protection or protection against overload shall conform to the...

Software used to size the safety devices

CERN Multimedia

CERN. Geneva

2016-01-01

To avoid mistakes during the calculation, CEA/SBT has decided to write a software that take into account all the situations it is possible to encountered (subcritical state, supercritical state, …). The goal is to permit to the engineer in charge of a cryostat manufacturing to perform this calculation; he is the only person able to do the accidental analysis which is fundamental for the sizing of the safety device. The software performed will be presented.

Plant control device

International Nuclear Information System (INIS)

Sato, Masuo; Ono, Makoto.

1995-01-01

A plant control device comprises an intellectual instrumentation group for measuring a predetermined process amount, an intellectual equipment group operating in accordance with a self-countermeasure, a system information space for outputting system information, a system level monitoring and diagnosing information generalization section for outputting system information, a system level maintenance information generalization section for outputting information concerning maintenance, a plant level information space and a plant level information generalization section. Each of them determines a state of the plant autonomously, and when abnormality is detected, each of the intellectual instrumentation, equipments and systems exchange information with each other, to conduct required operations including operations of intellectual robots, as required. Appropriate countermeasures for gauges, equipments and systems can be conducted autonomously at a place where operators can not access to improve reliability of complicate operations in the working site, as well as improve plant safety and reliability. (N.H.)

X-ray safety at the Los Alamos National Laboratory

International Nuclear Information System (INIS)

Gutierrez, J.A.

1986-11-01

An organized and structured safety program for x-ray generating devices was initiated in October, 1979. An X-ray Device Control Office was established to manage the program that currently oversees the activities of 201 x-ray generating devices and to provide SOP reviews, perform shielding calculations, and provide training for both the operators and health physics x-ray device surveyors. The new program also establishes controls for procurement of new equipment, requires the writing of Standard Operating Procedures, requires training for operators and provides routine and non-routine safety inspections of x-ray generating devices. Prior to this program going into effect, the Laboratory had recorded nine documented x-ray related exposure accidents. Since then, there have been none. Program elements and experiences of interest to other x-ray device users are discussed. 3 refs

Guidelines for evaluation of anchorage adequacy for safety-related equipment typically used on WWER-type NPPs

International Nuclear Information System (INIS)

Masopust, R.

1999-01-01

This report describes the criteria which should be met when the capacity evaluation of anchorage of safety related equipment is performed for the WWER type NPPs. It should be noted that these criteria were developed specifically for anchorage of WWER type equipment and components to the concrete or steel building structures and they cover different types of anchor bolts and other anchorage details which are typical just for the existing, constructed or reconstructed WWER type NPPs. The screening approach for verifying of equipment anchorage presented in this report is based on a combination of inspections, calculations, and engineering judgement

Factors affecting the utilization of safety devices by commercial ...

African Journals Online (AJOL)

Background: Motorcycle crashes are common causes of morbidity and mortality for both riders and passengers. To prevent and reduce the severity of injuries sustained through road traffic accidents (RTA) many countries enforce the use of safety devices while riding. Certain factors including non-enforcement of the existing ...

30-th anniversary of nuclear power engineering in the USSR. Safety problems of nuclear engineering

International Nuclear Information System (INIS)

Kulov, E.V.; Sidorenko, V.A.; Kovalevich, O.M.

1984-01-01

The problems of safety and protection of personnel, population and environments from the NPP radiation effect in the Soviet Union in cases of possible accidents and in the course of normal operation are discussed. The problem of safety assurance includes scientific technological and organizational aspects. The necessity of accounting the ''national factor'' in the form of a possible NPP location, existing legislation experience gained, etc. is noted. The main trends in ensuring safety are a high quality of equipment manufacturing and assembly, quality control of equipment at all stages of operation, development and realization of efficient protective measures and devices, assurance of safety precautions at all stages of designing equipment production, NPP operation and maintenance, functioning of the system of state control of NPP safety assurance. The skill and training of personnel are necessary prerequisite for ensuring safety of nuclear power plants

Improvement suggestions on license extension management for civil nuclear safety equipment activities

International Nuclear Information System (INIS)

Sun Xingjian; Liu Hongji; Han Guoli; Jia Fengcai

2013-01-01

Based on the concepts of Clear Requirements, Comprehensive Review, Objective Assessment, Dynamic Management, this paper gives improvement suggestions on license extension management for civil nuclear safety equipment design, manufacture, installation and non-destructive examination activities, which include establishing a relatively unified license extension review standard, combining multi-views and close linking license review and supervision, full utilizing the daily supervision and inspection results, as well as further improving motivation and elimination mechanism. (authors)

Requirements for industrial x-ray equipment

International Nuclear Information System (INIS)

1987-01-01

This safety code is concerned with the protection of all individuals who may be exposed to radiation emitted by X-ray equipment operating at energies up to 1 MeV as used in industrial radiography. This code presents basic radiation safety information for the protection of personnel operating and servicing X-ray equipment and other workers and the general public in the vicinity of areas where X-ray equipment is in operation. It specifies general safety features of design, construction and functioning of X-ray equipment and facilities; describes the responsibilities of the user, operator and maintenance personnel; contains recommendations to ensure that the X-ray equipment is used and maintained in accordance with the ALARA principle; and describes a program of personnel monitoring and radiation safety surveys. ( 6 refs., 5 tabs., 4 figs.)

Application of risk-based inspection methods for cryogenic equipment

CERN Multimedia

CERN. Geneva

2016-01-01

Risk-based Inspection (RBI) is widely applied across the world as part of Pressure Equipment Integrity Management, especially in the oil and gas industry, to generally reduce costs compared with time-based approaches and assist in assigning resources to the most critical equipment. One of the challenges in RBI is to apply it for low temperature and cryogenic applications, as there are usually no degradation mechanisms by which to determine a suitable probability of failure in the overall risk assessment. However, the assumptions used for other degradation mechanisms can be adopted to determine, qualitatively and semi-quantitatively, a consequence of failure within the risk assessment. This can assist in providing a consistent basis for the assumptions used in ensuring adequate process safety barriers and determining suitable sizing of relief devices. This presentation will discuss risk-based inspection in the context of cryogenic safety, as well as present some of the considerations for the risk assessme...

The Design of Transportation Equipment in Terms of Human Capabilities. The Role of Engineering Psychology in Transport Safety.

Science.gov (United States)

McFarland, Ross A.

Human factors engineering is considered with regard to the design of safety factors for aviation and highway transportation equipment. Current trends and problem areas are identified for jet air transportation and for highway transportation. Suggested solutions to transportation safety problems are developed by applying the techniques of human…

Situation analysis of physical independence of the equipment and safety circuits of Almaraz NPP regarding R.G. 1.75 rev.3 (2005)

International Nuclear Information System (INIS)

Seijas Portela, S.

2010-01-01

Situation analysis of physical independence of the electrical equipment and circuits CN safety Almaraz about R.G. 1.75 rev. 3. (2005) The aim of this paper is to present the work done in the analysis of the physical separation of redundant safety electrical equipment (emergency diesel generators, medium voltage, electrical cabinets, etc.) and physical separation of circuits and electrical conduits.

77 FR 71717 - Federal Motor Vehicle Safety Standards; Lamps, Reflective Devices, and Associated Equipment

Science.gov (United States)

2012-12-04

... compliance strategies, potentially imposing costs on manufacturers while not improving safety. V. Regulatory... tort cause of action is impliedly preempted. See Geier v. American Honda Motor Co., 529 U.S. 861 (2000...

30 CFR 75.518-1 - Electric equipment and circuits; overload and short circuit protection; minimum requirements.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Electric equipment and circuits; overload and short circuit protection; minimum requirements. 75.518-1 Section 75.518-1 Mineral Resources MINE SAFETY... short circuit protection; minimum requirements. A device to provide either short circuit protection or...

On the preparation of fire-wood splitting machines equipped with feeder devices

International Nuclear Information System (INIS)

Jaeaeskelaeinen, M.

1995-01-01

As part of the Bionergy research programme, the TTS Institute's Department of Forestry conducted a study on firewood splitting machines manufactured by Bilke Oy and Peurala Oy. The said machines are the first of their kind in Finland to be equipped with a feeder device. The Bilke unit is fed by a conveyor belt arrangement while the Peurala unit is equipped with a feeder roll. In addition, both machine types are equipped with a conveyor belt discharging device (e.g. for discharging split wood directly into a trailer). The Bilke unit can also be operated on extraction racks in the woods as the stems due to be split are fed into it from the side and the conveyor discharges the split wood rearwards into the trailer. The trailer can be hooked onto the splitting unit's draw-hook. At the landing, the Bilke unit was used to split a total of 14.2 m 3 and the Peurala unit 8.0 m 3 of approx. 3-metrelong stems averaging 9 cm in diameter. In addition to this, the Bilke unit was used to split ca. 17 m 3 of 3.5 metre-long stems with on average diameter of ca. 6 cm; the stems were in bunches alongside the extraction racks. The person operating the machines for the purposes of this study was a 27-year- old forest worker. The mean productivity achieved at the landing when using the Bilke unit was 7.7 m 3 while that of the Peurala unit was 5.8 m 3 per effective hour. When operated in the woods, the productivity achieved with the Bilke unit (excluding felling-cross cutting-delimbing-bunching and forest haulage work) was 2.8 m 3 /h. When applying a productivity of 1.7 m 3 for felling-cross cutting- delimbing-bunching work and 5.5. m 3 for forest haulage, the entire harvesting chain's productivity was 0.9 m 3 per effective hour

Perspective channel-type reactor with enhanced safety

International Nuclear Information System (INIS)

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

1994-01-01

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

10 CFR 32.101 - Schedule B-prototype tests for luminous safety devices for use in aircraft.

Science.gov (United States)

2010-01-01

....101 Schedule B—prototype tests for luminous safety devices for use in aircraft. An applicant for a... 10 Energy 1 2010-01-01 2010-01-01 false Schedule B-prototype tests for luminous safety devices for use in aircraft. 32.101 Section 32.101 Energy NUCLEAR REGULATORY COMMISSION SPECIFIC DOMESTIC LICENSES...

Hydrogen Safety Issues Compared to Safety Issues with Methane and Propane

International Nuclear Information System (INIS)

Green, Michael A.

2005-01-01

The hydrogen economy is not possible if the safety standards currently applied to liquid hydrogen and hydrogen gas by many laboratories are applied to devices that use either liquid or gaseous hydrogen. Methane and propane are commonly used by ordinary people without the special training. This report asks, 'How is hydrogen different from flammable gasses that are commonly being used all over the world?' This report compares the properties of hydrogen, methane and propane and how these properties may relate to safety when they are used in both the liquid and gaseous state. Through such an analysis, sensible safety standards for the large-scale (or even small-scale) use of liquid and gaseous hydrogen systems can be developed. This paper is meant to promote discussion of issues related to hydrogen safety so that engineers designing equipment can factor sensible safety standards into their designs

Hydrogen Safety Issues Compared to Safety Issues with Methane andPropane

Energy Technology Data Exchange (ETDEWEB)

Green, Michael A.

2005-08-20

The hydrogen economy is not possible if the safety standards currently applied to liquid hydrogen and hydrogen gas by many laboratories are applied to devices that use either liquid or gaseous hydrogen. Methane and propane are commonly used by ordinary people without the special training. This report asks, 'How is hydrogen different from flammable gasses that are commonly being used all over the world?' This report compares the properties of hydrogen, methane and propane and how these properties may relate to safety when they are used in both the liquid and gaseous state. Through such an analysis, sensible safety standards for the large-scale (or even small-scale) use of liquid and gaseous hydrogen systems can be developed. This paper is meant to promote discussion of issues related to hydrogen safety so that engineers designing equipment can factor sensible safety standards into their designs.

An on-line monitoring system for navigation equipment

Science.gov (United States)

Wang, Bo; Yang, Ping; Liu, Jing; Yang, Zhengbo; Liang, Fei

2017-10-01

Civil air navigation equipment is the most important infrastructure of Civil Aviation, which is closely related to flight safety. In addition to regular flight inspection, navigation equipment's patrol measuring, maintenance measuring, running measuring under special weather conditions are the important means of ensuring aviation flight safety. According to the safety maintenance requirements of Civil Aviation Air Traffic Control navigation equipment, this paper developed one on-line monitoring system with independent intellectual property rights for navigation equipment, the system breakthroughs the key technologies of measuring navigation equipment on-line including Instrument Landing System (ILS) and VHF Omni-directional Range (VOR), which also meets the requirements of navigation equipment ground measurement set by the ICAO DOC 8071, it provides technical means of the ground on-line measurement for navigation equipment, improves the safety of navigation equipment operation, and reduces the impact of measuring navigation equipment on airport operation.

Semiconductor Manufacturing equipment introduction

International Nuclear Information System (INIS)

Im, Jong Sun

2001-02-01

This book deals with semiconductor manufacturing equipment. It is comprised of nine chapters, which are manufacturing process of semiconductor device, history of semiconductor manufacturing equipment, kinds and role of semiconductor manufacturing equipment, construction and method of semiconductor manufacturing equipment, introduction of various semiconductor manufacturing equipment, spots of semiconductor manufacturing, technical elements of semiconductor manufacturing equipment, road map of technology of semiconductor manufacturing equipment and semiconductor manufacturing equipment in the 21st century.

Safety equipment list for the light duty utility arm system

International Nuclear Information System (INIS)

Barnes, G.A.

1998-01-01

The initial issue (Revision 0) of this Safety Equipment List (SEL) for the Light Duty Utility Arm (LDUA) requires an explanation for both its existence and its being what it is. All LDUA documentation leading up to creation of this SEL, and the SEL itself, is predicated on the LDUA only being approved for use in waste tanks designated as Facility Group 3, i.e., it is not approved for use in Facility Group 1 or 2 waste tanks. Facility Group 3 tanks are those in which a spontaneous or induced hydrogen gas release would be small, localized, and would not exceed 25% of the LFL when mixed with the remaining air volume in the dome space; exceeding these parameters is considered unlikely. Thus, from a NFPA flammable gas environment perspective the waste tank interior is not classified as a hazardous location. Furthermore, a hazards identification and evaluation (HNF-SD-WM-HIE-010, REV 0) performed for the LDUA system concluded that the consequences of actual LDUA system postulated accidents in Flammable Gas Facility Group 3 waste tanks would have either NO IMPACT or LOW IMPACT on the offsite public and onsite worker. Therefore, from a flammable gas perspective, there is not a rationale for classifying any of SSCs associated with the LDUA as either Safety Class (SC) or Safety Significant (SS) SSCs, which, by default, categorizes them as General Service (GS) SSCs. It follows then, based on current PHMC procedures (HNF-PRO-704 and HNF-IP-0842, Vol IV, Section 5.2) for SEL creation and content, and from a flammable gas perspective, that an SEL is NOT REQ at sign D HOWEVER exclamation point exclamation point exclamation point There is both a precedent and a prudency to capture all SSCS, which although GS, contribute to a Defense-In-Depth (DID) approach to the design and use of equipment in potentially flammable gas environments. This Revision 0 of the LDUA SEL has been created to capture these SSCs and they are designated as GS-DID in this document. The specific reasons for

Medical Device Safety

Science.gov (United States)

A medical device is any product used to diagnose, cure, or treat a condition, or to prevent disease. They ... may need one in a hospital. To use medical devices safely Know how your device works. Keep ...

Strategy for conformity of non-standard cryogenic equipment

CERN Multimedia

CERN. Geneva

2016-01-01

CERN as an intergovernmental organization establishes its own Safety Rules as necessary for its proper functioning. In particular, the CERN General Safety Instruction for cryogenic equipment requires that cryogenic pressure equipment at CERN shall comply with the European Pressure Equipment Directive (PED). However, due to the particular features of some of the cryogenic equipment required for the accelerators, as well as the existence of international collaborations with in-kind contributions from non-EU countries, full compliance with the PED may not always be achieved. This situation is foreseen in the Safety Rules, where CERN HSE will define the Safety requirements applicable to such equipment as well as any eventual additional compensatory measure as to ensure a commensurate level of Safety for our pressure equipment. Where compliance with PED may not be achieved, CERN HSE will become the de facto Notified Body and therefore be in charge of the assessment of the conformity of the equipment to the applica...

An update on mobile phones interference with medical devices.

Science.gov (United States)

Mahmoud Pashazadeh, Ali; Aghajani, Mahdi; Nabipour, Iraj; Assadi, Majid

2013-10-01

Mobile phones' electromagnetic interference with medical devices is an important issue for the medical safety of patients who are using life-supporting medical devices. This review mainly focuses on mobile phones' interference with implanted medical devices and with medical equipment located in critical areas of hospitals. A close look at the findings reveals that mobile phones may adversely affect the functioning of medical devices, and the specific effect and the degree of interference depend on the applied technology and the separation distance. According to the studies' findings and the authors' recommendations, besides mitigating interference, using mobile phones at a reasonable distance from medical devices and developing technology standards can lead to their effective use in hospital communication systems.

An update on mobile phones interference with medical devices

International Nuclear Information System (INIS)

Pashazadeh, A. M.; Aghajani, M.; Nabipour, I.; Assadi, M.

2013-01-01

Mobile phones' electromagnetic interference with medical devices is an important issue for the medical safety of patients who are using life-supporting medical devices. This review mainly focuses on mobile phones' interference with implanted medical devices and with medical equipment located in critical areas of hospitals. A close look at the findings reveals that mobile phones may adversely affect the functioning of medical devices, and the specific effect and the degree of interference depend on the applied technology and the separation distance. According to the studies' findings and the authors' recommendations, besides mitigating interference, using mobile phones at a reasonable distance from medical devices and developing technology standards can lead to their effective use in hospital communication systems. (authors)

Equipment Qualification and Environment Establishment for COTS Dedication of Safety Grade PC

International Nuclear Information System (INIS)

Ahn, Kwang Chul; Bin, Chang Sun; Kwon, Yoon Kwang; Kang, Shin Woo; Koh, Sung Won; Shon, Eui Chan; Jang, Hyun Doo; Song, Il Sup; Lee, Hyun Noh

2010-08-01

Safety grade PCs are required for protection systems of SKN 3 and 4 nuclear power plant and subsequent plants. Commercial grade item (CGI) dedication should be carried out to utilize a commercial PC as a safety grade PC of nuclear power plants. This project is aimed to perform the equipment qualification of the commercial PC, and review and improve the quality system of the PC supplier. As a result of the EQ for the CGI dedication, selected military PCs have passed the environment test, the seismic test, and the EMI test required for the digital controllers of nuclear plants. In addition, a walk-through of the quality system of the PC supplier, ISO 9001, was carried out and the quality system was improved. History data for the PC was gathered. As the analysis of the history data showed that operating experience time of the PC is longer than the plant life time, the history data could be used as an evidence of acceptance. After dedicated according to the CGI dedication process, military rugged PCs could be used for safety grade PCs

Radiation Safety in Industrial Radiography. Specific Safety Guide (French Edition); Surete radiologique en radiographie industrielle

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-05-15

This Safety Guide provides recommendations for ensuring radiation safety in industrial radiography used in non-destructive testing. This includes industrial radiography work that utilizes X ray and gamma sources, both in Horizontal-Ellipsis shielded facilities that have effective engineering controls and in outside shielded facilities using mobile sources. Contents: 1. Introduction; 2. Duties and responsibilities; 3. Safety assessment; 4. Radiation protection programme; 5. Training and qualification; 6. Individual monitoring of workers; 7. Workplace monitoring; 8. Control of radioactive sources; 9. Safety of industrial radiography sources and exposure devices; 10. Radiography in shielded enclosures; 11. Site radiography; 12. Transport of radioactive sources; 13. Emergency preparedness and response; Appendix: IAEA categorization of radioactive sources; Annex I: Example safety assessment; Annex II: Overview of industrial radiography sources and equipment; Annex III: Examples of accidents in industrial radiography.

Comparison and Analysis of IEEE 344 and IEC 60980 standards for harmonization of seismic qualification of safety-related equipment

International Nuclear Information System (INIS)

Lee, Young Ok; Kim, Jong Seog; Seo, Jeong Ho; Kim, Myung Jun

2011-01-01

The seismic qualification of safety related equipment in nuclear power plants should demonstrate an equipment's ability to perform its safety function during/or after the time it is subjected to the forces resulting from one SSE. In addition, the equipment must withstand the effects of a number of OBEs, preceding the SSE. IEEE 344 and IEC 60980 present the criteria for establishing procedures demonstrating that the Class 1E equipment can meet its performance requirement during seismic events. Currently, IEEE 344 is used for regulation of nuclear power plant in the United State whereas IEC 60980 is mainly used in Europe. In particular, NPPs of France and China apply with RCC-E and GB that are domestic standards, respectively. Equipment supplier and Utility have difficulties because of different applicable standards. Equipment supplier to export S/R components/equipment to other standard area performs additional seismic qualification. For example, equipment are qualifies according to IEC 60980, RCC-E, GB although they have been qualified in accordance with IEEE 344. Also, utility to attempt power up-rate, life extension of NPP constructed under rules of RCC-E such as Ulchin NPP 1 and 2 has similar difficulties. RCC-E endorses IEC 60980 and GB is almost same as IEC 60980 except minor difference of earthquake environment definition. Therefore this paper surveys the similarities and differences between IEEE 344 and IEC 60980. In addition, this paper considers how the two sets of standards may be used in a complementary fashion to be possible using one or the other standard area

Free-world microelectronic manufacturing equipment

Science.gov (United States)

Kilby, J. S.; Arnold, W. H.; Booth, W. T.; Cunningham, J. A.; Hutcheson, J. D.; Owen, R. W.; Runyan, W. R.; McKenney, Barbara L.; McGrain, Moira; Taub, Renee G.

1988-12-01

Equipment is examined and evaluated for the manufacture of microelectronic integrated circuit devices and sources for that equipment within the Free World. Equipment suitable for the following are examined: single-crystal silicon slice manufacturing and processing; required lithographic processes; wafer processing; device packaging; and test of digital integrated circuits. Availability of the equipment is also discussed, now and in the near future. Very adequate equipment for most stages of the integrated circuit manufacturing process is available from several sources, in different countries, although the best and most widely used versions of most manufacturing equipment are made in the United States or Japan. There is also an active market in used equipment, suitable for manufacture of capable integrated circuits with performance somewhat short of the present state of the art.

Personal Protective Equipment

National Research Council Canada - National Science Library

1998-01-01

... of personal protective equipment A safety program for new employees is a necessary part of any orientation program An on-going safety program should be used to motivate employees to continue to use...

21 CFR 866.4830 - Rocket immunoelectro-phoresis equipment.

Science.gov (United States)

2010-04-01

... (CONTINUED) MEDICAL DEVICES IMMUNOLOGY AND MICROBIOLOGY DEVICES Immunology Laboratory Equipment and Reagents... equipment for clinical use is a device used to perform a specific test on proteins by using a procedure...

Reliability analysis of PLC safety equipment

Energy Technology Data Exchange (ETDEWEB)

Yu, J.; Kim, J. Y. [Chungnam Nat. Univ., Daejeon (Korea, Republic of)

2006-06-15

FMEA analysis for Nuclear Safety Grade PLC, failure rate prediction for nuclear safety grade PLC, sensitivity analysis for components failure rate of nuclear safety grade PLC, unavailability analysis support for nuclear safety system.

Reliability analysis of PLC safety equipment

International Nuclear Information System (INIS)

Yu, J.; Kim, J. Y.

2006-06-01

FMEA analysis for Nuclear Safety Grade PLC, failure rate prediction for nuclear safety grade PLC, sensitivity analysis for components failure rate of nuclear safety grade PLC, unavailability analysis support for nuclear safety system

76 FR 41181 - Federal Motor Vehicle Safety Standards; Lamps, Reflective Devices, and Associated Equipment

Science.gov (United States)

2011-07-13

... to restore the blue and green color boundaries to Federal Motor Vehicle Safety Standard (FMVSS) No... number in the heading of this document, by any of the following methods: Federal eRulemaking Portal: Go... comment, if submitted on behalf of an association, business, labor union, etc.). You may review DOT's...

New Safety rules

CERN Multimedia

Safety Commission

2008-01-01

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

Permitting product liability litigation for FDA-approved drugs and devices promotes patient safety.

Science.gov (United States)

Kesselheim, A S

2010-06-01

In 2008 and 2009, the Supreme Court reviewed the question of whether patients injured by dangerous prescription drugs or medical devices can bring tort lawsuits against pharmaceutical and device manufacturers. The Court ruled that claims against device manufacturers were preempted while claims against pharmaceutical manufacturers were not. The threat of product liability lawsuits promotes patient safety by encouraging manufacturers to take greater responsibility in providing clear warnings about known adverse effects of their products.

Radiation Safety in Industrial Radiography. Specific Safety Guide (Spanish Edition); Seguridad radiologica en la radiografia industrial

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-12-15

This Safety Guide provides recommendations for ensuring radiation safety in industrial radiography used in non-destructive testing. This includes industrial radiography work that utilizes X ray and gamma sources, both in shielded facilities that have effective engineering controls and in outside shielded facilities using mobile sources. Contents: 1. Introduction; 2. Duties and responsibilities; 3. Safety assessment; 4. Radiation protection programme; 5. Training and qualification; 6. Individual monitoring of workers; 7. Workplace monitoring; 8. Control of radioactive sources; 9. Safety of industrial radiography sources and exposure devices; 10. Radiography in shielded enclosures; 11. Site radiography; 12. Transport of radioactive sources; 13. Emergency preparedness and response; Appendix: IAEA categorization of radioactive sources; Annex I: Example safety assessment; Annex II: Overview of industrial radiography sources and equipment; Annex III: Examples of accidents in industrial radiography.

Research Devices Maintenance Programs and Safety Network Infrastructures in Nuclear Malaysia

International Nuclear Information System (INIS)

Zainudin Jaafar; Muhammad Zahidee Taat; Ishak Mansor

2015-01-01

Instrumentation and Automation Center (PIA) is responsible in carrying out maintenance work for building safety infrastructure and area for nuclear scientific and research work. Care cycle and nuclear scientific tools starting from the preparation of specifications until devices disposal- to get the maximum output from devices therefore PIA has introduced Effective and Comprehensive Maintenance Plan under Management/ Trust/ Development/ Science Fund budgets and also user, Asset Management, caring and handling of the devices. This paper also discussed more on case study related to using and handling so that it can be guidance and standard when its involving mishandling, improper maintenance, inadequacy of supervision and others including improvement suggestion programs. (author)

Regulation E 69-14. Monitoring requirements for medical devices

International Nuclear Information System (INIS)

2015-01-01

In the 'Regulations for the State Evaluation and Registration of Medical Equipment' force (Hereinafter Rules) set forth in Chapter VII, Articles 79 and 86, the monitoring activity as one of the programs necessary for evaluating the safety and effectiveness of medical monitoring equipment. In the years 2008 and 2011 were approved and implemented by the Center for State Control of Medical Equipment (CCEEM) Regulations and -1.1 ER and ER-1 that support and regulatory requirements 'Control and monitoring of pacemakers and implantable defibrillators' and 'Assessment, recording and control after market surgical silicone implants,' which are specific to these products and have provided a useful result for the performance of the activity. Given the number and diversity of high-risk medical devices as implantable or sustain human life that are brought into our National Health System (SNS), a regulation establishing control over the behavior becomes necessary safety and effectiveness of this equipment during use, which provide inputs to risk management. The objective of this regulation is to establish the regulatory requirements for tracking medical equipment introduced in the NHS. The provisions of this Regulation is aimed at health institutions, to CECMED as manufacturers, suppliers, distributors and importers of medical equipment.

30 CFR 56.4230 - Self-propelled equipment.

Science.gov (United States)

2010-07-01

....4230 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR METAL AND NONMETAL MINE SAFETY AND HEALTH SAFETY AND HEALTH STANDARDS-SURFACE METAL AND NONMETAL MINES Fire Prevention and Control Firefighting Equipment § 56.4230 Self-propelled equipment. (a)(1) Whenever a fire or its effects...

Safety of information in electronic equipment influenced by the charged space particles

Directory of Open Access Journals (Sweden)

Ksenia Gennad’evna Sizova

2016-10-01

Full Text Available A version of the existing evaluation method of electronic equipment to the influence of charged space particles causing single event effects for the purpose of improving the accuracy of calculation in the field of information safety is suggested. On the basis of the existing and modified methods radiation tolerance of real payload spacecraft responsible for the security of transmitted information are defined. The results of comparison are introduced. Significant differences not only in quantitative but also in qualitative character of tolerance indicators are revealed. It is demonstrated that the modified method allows to take into account the functional complexity of the hardware and the application efficiency of the sophisticated single event effects protection tools. To confirm the applicability of the modified method of equipment tolerance evaluation method to the influence of charged space particles causing single event effects proposals to the procedure of ground tests of the payload and the space experiment are developed.

Utilization of ocular safety devices among Sawmill workers in Nigeria

African Journals Online (AJOL)

Objective: The study was carried out to assess the use of eye safety devices in sawmill workers in Nigeria. Methods: A cross-sectional study of sawmill workers was carried out using pretested questionnaires. Ocular examination was done on site with a pen torch, portable hand-held slit lamp bio-microscope and direct ...

Renewal of radiological equipment.

Science.gov (United States)

2014-10-01

In this century, medical imaging is at the heart of medical practice. Besides providing fast and accurate diagnosis, advances in radiology equipment offer new and previously non-existing options for treatment guidance with quite low morbidity, resulting in the improvement of health outcomes and quality of life for the patients. Although rapid technological development created new medical imaging modalities and methods, the same progress speed resulted in accelerated technical and functional obsolescence of the same medical imaging equipment, consequently creating a need for renewal. Older equipment has a high risk of failures and breakdowns, which might cause delays in diagnosis and treatment of the patient, and safety problems both for the patient and the medical staff. The European Society of Radiology is promoting the use of up-to-date equipment, especially in the context of the EuroSafe Imaging Campaign, as the use of up-to-date equipment will improve quality and safety in medical imaging. Every healthcare institution or authority should have a plan for medical imaging equipment upgrade or renewal. This plan should look forward a minimum of 5 years, with annual updates. Teaching points • Radiological equipment has a definite life cycle span, resulting in unavoidable breakdown and decrease or loss of image quality which renders equipment useless after a certain time period.• Equipment older than 10 years is no longer state-of-the art equipment and replacement is essential. Operating costs of older equipment will be high when compared with new equipment, and sometimes maintenance will be impossible if no spare parts are available.• Older equipment has a high risk of failure and breakdown, causing delays in diagnosis and treatment of the patient and safety problems both for the patient and the medical staff.• Every healthcare institution or authority should have a plan for medical imaging equipment upgrade or replacement. This plan should look forward a

ALARA issues arising for safety and security of radiation sources and security screening devices - Summary and recommendations of the 12. European ALARA network workshop

International Nuclear Information System (INIS)

Shaw, P.; Crouail, P.; Drouet, F.

2010-01-01

The 12. European ALARA Network (EAN) workshop on 'ALARA issues arising for safety and security of radiation sources and security screening devices' took place in Vienna (Austria) in October 2009. The aim of that workshop was to consider how the implementation of ALARA3, in terms of planned and emergency situations, involving worker and public doses, is affected by the introduction of security-related measures. In the case of new equipment and procedures, there was also the question of whether exposures arising from security screening devices can be justified and optimised. This workshop consisted of invited oral presentations, which highlighted the main issues, and half of the programme was devoted to discussions within working groups on specific topics. During their discussions, the working groups identified recommendations dealing with the following topics: the implementation of the Code of Conduct and HASS4 - ensuring ALARA; balancing security and safety - how to achieve an optimum solution; the management of an emergency exposure situation from an ALARA perspective; the justification and optimisation of the use of security devices. The objective of this paper is to present the main conclusions and recommendations produced during the workshop. Individual presentations (papers and slides) as well as the reports from the working groups are available to download on the EAN web site (http://www.eu-alara.net). (authors)

A Wii-controlled safety device for electric chainsaws

Directory of Open Access Journals (Sweden)

R. Gubiani

2013-09-01

Full Text Available Forestry continues to represent one of the most hazardous economic sectors of human activity, and historically, the operation of chainsaws has mainly been restricted to professional lumberjacks. In recent years, because of low cost, chainsaws have become popular among unprofessionals, e.g. for cutting firewood and trimming trees. Serious or lethal lesions due to the use of chainsaws or electric chainsaws are often observed by traumatologists or forensic pathologists. Such serious accidents often occur during occupational activities and are essentially due to kickback or uncorrected use of the tool, or when the operator falls down losing the control of the implement. A new device in order to stop a cutting chain was developed and adapted to an electric chainsaw. The device is based on a Wiimote controller (Nintendo™, including two accelerometers and two gyroscopes for detecting rotation and inclination. A Bluetooth wireless technology is used to transfer data to a portable computer. The data collected about linear and angular acceleration are filtered by an algorithm, based on the Euclid norm, capable to distinguishing between normal movements and dangerous chainsaw movements. The result show a good answer to device and when happen a dangerous situation an alarm signal is sent back to the implement in order to stop the cutting chain. The device show a correct behavior in tested dangerous situations and is envisaged to extend to combustion engine chainsaws, as well as to other portable equipment used in agriculture and forestry operations and for this objectives were patented.

77 FR 60704 - Medical Devices; Availability of Safety and Effectiveness Summaries for Premarket Approval...

Science.gov (United States)

2012-10-04

... regulations provide that FDA publish a quarterly list of available safety and effectiveness summaries of PMA...-0638] Medical Devices; Availability of Safety and Effectiveness Summaries for Premarket Approval... Administration (FDA) is publishing a list of premarket approval applications (PMAs) that have been approved. This...

78 FR 35284 - Medical Devices; Availability of Safety and Effectiveness Summaries for Premarket Approval...

Science.gov (United States)

2013-06-12

... summaries of safety and effectiveness data to the Division of Dockets Management (HFA-305), Food and Drug... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket Nos. FDA-2013-M-0036... Devices; Availability of Safety and Effectiveness Summaries for Premarket Approval Applications AGENCY...

76 FR 31965 - Medical Devices; Availability of Safety and Effectiveness Summaries for Premarket Approval...

Science.gov (United States)

2011-06-02

... summaries of safety and effectiveness data to the Division of Dockets Management (HFA-305), Food and Drug... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket Nos. FDA-2011-M-0034... Devices; Availability of Safety and Effectiveness Summaries for Premarket Approval Applications AGENCY...

Risk assessment of medical devices: evaluation of microbiological and toxicological safety

International Nuclear Information System (INIS)

Dorpema, J.W.

1995-01-01

Safety assessment of medical devices includes sterilization and biological evaluation or biocompatability testing. Sterilization by ETO gas is criticised for their carcinogenic potency or even banned. Mutual acceptance of biological evaluation test results is promoted by a laboratory accreditation and qualification program. (Author)

Passive safety device and internal short tested method for energy storage cells and systems

Science.gov (United States)

Keyser, Matthew; Darcy, Eric; Long, Dirk; Pesaran, Ahmad

2015-09-22

A passive safety device for an energy storage cell for positioning between two electrically conductive layers of the energy storage cell. The safety device also comprising a separator and a non-conductive layer. A first electrically conductive material is provided on the non-conductive layer. A first opening is formed through the separator between the first electrically conductive material and one of the electrically conductive layers of the energy storage device. A second electrically conductive material is provided adjacent the first electrically conductive material on the non-conductive layer, wherein a space is formed on the non-conductive layer between the first and second electrically conductive materials. A second opening is formed through the non-conductive layer between the second electrically conductive material and another of the electrically conductive layers of the energy storage device. The first and second electrically conductive materials combine and exit at least partially through the first and second openings to connect the two electrically conductive layers of the energy storage device at a predetermined temperature.

Practical approaches to implementing facility wide equipment strengthening programs

International Nuclear Information System (INIS)

Kincaid, R.H.; Smietana, E.A.

1989-01-01

Equipment strengthening programs typically focus on components required to ensure operability of safety related equipment or to prevent the release of toxic substances. Survival of non-safety related equipment may also be crucial to ensure rapid recovery and minimize business interruption losses. Implementing a strengthening program for non-safety related equipment can be difficult due to the large amounts of equipment involved and limited budget availability. EQE has successfully implemented comprehensive equipment strengthening programs for a number of California corporations. Many of the lessons learned from these projects are applicable to DOE facilities. These include techniques for prioritizing equipment and three general methodologies for anchoring equipment. Pros and cons of each anchorage approach are presented along with typical equipment strengthening costs

78 FR 17415 - Medical Devices; Availability of Safety and Effectiveness Summaries for Premarket Approval...

Science.gov (United States)

2013-03-21

... its decision. The regulations provide that FDA publish a quarterly list of available safety and..., FDA-2012-M-1183, and FDA-2012-M-1184] Medical Devices; Availability of Safety and Effectiveness.... SUMMARY: The Food and Drug Administration (FDA) is publishing a list of premarket approval applications...

Equipment design guidance document for flammable gas waste storage tank new equipment

International Nuclear Information System (INIS)

Smet, D.B.

1996-01-01

This document is intended to be used as guidance for design engineers who are involved in design of new equipment slated for use in Flammable Gas Waste Storage Tanks. The purpose of this document is to provide design guidance for all new equipment intended for application into those Hanford storage tanks in which flammable gas controls are required to be addressed as part of the equipment design. These design criteria are to be used as guidance. The design of each specific piece of new equipment shall be required, as a minimum to be reviewed by qualified Unreviewed Safety Question evaluators as an integral part of the final design approval. Further Safety Assessment may be also needed. This guidance is intended to be used in conjunction with the Operating Specifications Documents (OSDs) established for defining work controls in the waste storage tanks. The criteria set forth should be reviewed for applicability if the equipment will be required to operate in locations containing unacceptable concentrations of flammable gas

Life extension of low and medium voltage equipment

International Nuclear Information System (INIS)

Bharteey, B.M.; Hart, T.J.

1990-01-01

Nuclear plant life extension is becoming a very important issue with the passing of each day. Within 3 to 10 years after the turn of the century, licenses of a number of nuclear power plants in the United States will expire. For the near future, new construction of nuclear power plants in the United States is expected to be inhibited, if the current economic and regulatory environment continues to persist. This situation, coupled with aging of utility equipment and the high cost of financing new construction is resulting in a growing emphasis on preserving and extending the capability of existing power plants. Until now, the utilities have placed more emphasis on high cost items, but experience shows that extending life of low cost of device/components in items like Motor Control Center Centers and switchgear pays big dividends. According to the current practice, devices of these items are replaced at the end of their assigned qualified life or attended to when there is a problem resulting in an unplanned outage. In this paper based on extensive experience in the field of motor control centers and medium switchgear, the authors proposed a cookbook methodology to determine the extent or absence of degradation and establish trends of the pertinent operational properties of devices of this type of equipment. The test results also provide satisfactory evidence of class 1E nuclear safety-related function

Operation monitor for plant equipment

International Nuclear Information System (INIS)

Kondo, Tetsufumi; Kanemoto, Shigeru.

1991-01-01

In a nuclear power plant, states of each of equipment in the plant are monitored accurately even under such a operation condition that the power is changed. That is, the fundamental idea is based on a model comparison method. A deviation between an output signal upon normal plant state obtained in a forecasting model device and that of the objective equipment in the plant are compared with a predetermined value. The result of the comparison is inputted to an alarm device to alarm the abnormality of the states of the equipment to an operator. The device of the present invention thus constituted can monitor the abnormality of the operation of equipment accurately even under such a condition that a power level fluctuates. As a result, it can remarkably contribute to mitigate operator's monitoring operation under the condition such as during load following operation. (I.S.)

INDIVIDUAL AND ORGANIZATIONAL VARIABLES AFFECTING THE USE OF PERSONAL PROTECTIVE EQUIPMENT

Directory of Open Access Journals (Sweden)

TUNÇ DEMİRBİLEK

2013-06-01

Full Text Available Management’s safety approach and commitment are related to occupational health and safety applications in workplaces. However, personal characteristics and attitudes on their health of employees are very influential factors on occupational health and safety applications. For examine of interaction between behaviors and the health and safety applications it is required that determine of employee’s perceptions. For this reason this paper’s purpose is to establish of safety needs, attitudes and behaviors of employees and their perceptions regarding management’s safety approach and applications. The study’s focal point is use of personal protective equipment as an indicator “safety behavior”. In empirical study, assumption variables regarding the use of personal protective equipment are safety effectively, safety need, management attitudes and protective equipment conditions. The fundamental hypothesis of this paper is use of personal protective equipment is related to individual and organizational variables. Implications of research findings are to indicate impelling the workers to safety behaviour or using the personal protective equipment by their feeling of the safety behaviour and availability of personal protective equipment.

14 CFR 101.35 - Equipment and marking requirements.

Science.gov (United States)

2010-01-01

... unmanned free balloon unless— (1) It is equipped with at least two payload cut-down systems or devices that operate independently of each other; (2) At least two methods, systems, devices, or combinations thereof... envelope; and (3) The balloon envelope is equipped with a radar reflective device(s) or material that will...

41 CFR 102-34.250 - Do Federal employees in Government motor vehicles have to use all safety devices and follow all...

Science.gov (United States)

2010-07-01

... safety devices and follow all safety guidelines? Yes, Federal employees in Government motor vehicles have... 41 Public Contracts and Property Management 3 2010-07-01 2010-07-01 false Do Federal employees in Government motor vehicles have to use all safety devices and follow all safety guidelines? 102-34.250 Section...

Two Different Maintenance Strategies in the Hospital Environment: Preventive Maintenance for Older Technology Devices and Predictive Maintenance for Newer High-Tech Devices.

Science.gov (United States)

Sezdi, Mana

2016-01-01

A maintenance program generated through the consideration of characteristics and failures of medical equipment is an important component of technology management. However, older technology devices and newer high-tech devices cannot be efficiently managed using the same strategies because of their different characteristics. This study aimed to generate a maintenance program comprising two different strategies to increase the efficiency of device management: preventive maintenance for older technology devices and predictive maintenance for newer high-tech devices. For preventive maintenance development, 589 older technology devices were subjected to performance verification and safety testing (PVST). For predictive maintenance development, the manufacturers' recommendations were used for 134 high-tech devices. These strategies were evaluated in terms of device reliability. This study recommends the use of two different maintenance strategies for old and new devices at hospitals in developing countries. Thus, older technology devices that applied only corrective maintenance will be included in maintenance like high-tech devices.

Contributions to the research programs in nuclear and industrial electronics, domestic production of instrumentation, safety and control systems and equipment for nuclear reactors and auxiliary installations

International Nuclear Information System (INIS)

Talpariu, C; Talpariu, J.; Matei, C.

2001-01-01

Domestic production of component system and equipment for the control and safety of nuclear facilities was one of the priority objective of the Nuclear Research Institute Pitesti. The problems addressed were particularly related to design and production of analog and digital equipment for measurements, triggering and display of the values of process parameters as well as to regulating complex functions of this equipment. Associated to this effort were the research works concerning: - reliability and in-service life-time of the electronic components and equipment in the safety and control systems for nuclear processes; - radiation endurance of industrial electronic components; utilization of whirling currents in calandria tube testing; - expert systems and applications in nuclear reactor control and safety; design and testing methods of process real time software packages for safety in control critical systems for nuclear domain. There are presented characteristics of the following equipment: 1. amplifier for ionization chambers with triggering comparator circuits for the CANDU 600 reactor shut down system; 2. amplifier for ionization chambers without triggering comparator circuits for power regulating system; 3. safety and regulating computerized system for C9 and C5 cans; 4. acquisition system for dosimetric data in nuclear facilities; 5. program able digital comparator for the reactor shut down system; 6. stationary gamma areal monitors for CANDU 600 reactors and other nuclear facilities

Agricultural injuries in Korea and errors in systems of safety

Directory of Open Access Journals (Sweden)

Hyocher Kim

2016-07-01

It was found that most agricultural injuries were caused by a complex layer of root causes which were classified as errors in the systems of safety. This result indicates that not only training and personal protective equipment, but also regulation of safety design, mitigation devices, inspection/maintenance of workplaces, and other factors play an important role in preventing agricultural injuries. The identification of errors will help farmers to implement easily an effective prevention programme.

77 FR 35745 - Highway Safety Programs; Conforming Products List of Screening Devices To Measure Alcohol in...

Science.gov (United States)

2012-06-14

..., battery powered device with a semiconductor sensor. (2) Alcohol Countermeasure Systems Corp., submitted...-0062] Highway Safety Programs; Conforming Products List of Screening Devices To Measure Alcohol in... Screening Devices to Measure Alcohol in Bodily Fluids dated, March 31, 2008 (73 FR 16956). DATES: Effective...

21 CFR 870.4200 - Cardiopulmonary bypass accessory equipment.

Science.gov (United States)

2010-04-01

... Cardiopulmonary bypass accessory equipment. (a) Identification. Cardiopulmonary bypass accessory equipment is a... mounting bracket or system-priming equipment. (b) Classification. (1) Class I. The device is classified as class I if it does not involve an electrical connection to the patient. The device is exempt from the...

Interim safety equipment list for 241-C-106 waste retrieval, project W-320

International Nuclear Information System (INIS)

Conner, J.C.

1996-01-01

The purpose of this supporting document is to provide safety classifications for systems, structures, and components of the Tank 241-C-106 Waste Retrieval Sluicing System (WRSS) and to document the methodology used to develop these safety classifications. The WRSS requires two transfer lines, one to carry sluiced waste slurry to tank 241-AY-102 and the other to return supernatant to tank 241-C-106; pumps in each tank; sluicers to direct the supernatant stream inside tank 241-C-106; a slurry distributor in tank 241-AY-102; heating, ventilation, and air conditioning for tank 241-C-106; and instrumentation and control devices

Interim safety equipment list for 241-C-106 waste retrieval, project W-320

Energy Technology Data Exchange (ETDEWEB)

Conner, J.C.

1996-01-25

The purpose of this supporting document is to provide safety classifications for systems, structures, and components of the Tank 241-C-106 Waste Retrieval Sluicing System (WRSS) and to document the methodology used to develop these safety classifications. The WRSS requires two transfer lines, one to carry sluiced waste slurry to tank 241-AY-102 and the other to return supernatant to tank 241-C-106; pumps in each tank; sluicers to direct the supernatant stream inside tank 241-C-106; a slurry distributor in tank 241-AY-102; heating, ventilation, and air conditioning for tank 241-C-106; and instrumentation and control devices.

Nuclear safety: a large scale quality audit of pressurized equipment

International Nuclear Information System (INIS)

Faudon, Valerie

2016-01-01

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

Underground coal mining - methods, equipment developments and trends

Energy Technology Data Exchange (ETDEWEB)

Singhal, R

1988-12-01

Underground mines are truly beginning to accept the so-called 'high tech' technology evident in other industries. Automation, remote control and robotics have taken an added significance. Wireless communication, mine-wide equipment health and performance monitoring, and transmission of data from deeper levels to surface is moving towards becoming the norm. There is emphasis on developing and applying continuous mining systems, as well as on modifying cyclical discontinuous methods to continuous systems. Multi-purpose equipment is also being developed. Technology transfer is playing its role - equipment and systems from surface coal mining are being applied to underground mining and vice-versa. At the American Mining Congress Exhibition held in Chicago in April 1988, a variety of equipment for underground mining was displayed including coal face equipment such as shearer loaders, conveyors and powered supports, and equipment for room-and-pillar coal mining. The trend continues to be towards high power machines equipped with a variety of electronics and sensors, safety devices, and alarm systems. Ancillary equipment on display covered a variety of cutting drums, cutting tools, conveying equipment and so on. In room-and-pillar mining, the overall emphasis was on moving away from the cyclical nature of the work. Transportation by shuttle cars must be replaced by continuous transport systems such as conveyors. Experience from Australia has shown that the application of continuous haulage and breaker line supports has permitted a doubling of production from room-and-pillar systems. Production levels of 3,000tpd have already been achieved, and 4,000tpd is considered achievable.

Equipment qualification testing - a practical approach

International Nuclear Information System (INIS)

Davies, G.A.; McDougall, R.I.; Poirier, M.P.

1996-01-01

When nuclear safety equipment is credited with a Required Safety Function it must properly perform that function to facilitate safe control and/or shutdown of the plant during a design basis accident. When such equipment is required to be environmentally (EQ) and/or seismically qualified (SQ) for safety related use in CANDU nuclear power plants, the preferred method of qualification is by type testing. The qualification testing process requires that the test specimen equipment be subjected to the aging stressors associated with the normal service conditions that it would experience during it's required qualified (or service) life. Following the aging process, the test specimen is in a condition representative of that in which it would be at the end of its service life in the plant. The test specimen is then subjected to a simulated accident during which it must satisfy performance requirements thereby demonstrating that it can perform its required safety function. The performance requirements specified for the qualification testing must be designed to ensure that satisfactory performance of the safety function is demonstrated during the qualification program. This paper provides descriptions of practical methods used in the deriving and satisfying of relevant performance requirements during the qualification testing of safety related equipment. (author)

Framework conditions and requirements to ensure the technical functional safety of reprocessed medical devices.

Science.gov (United States)

Kraft, Marc

2008-09-03

Testing and restoring technical-functional safety is an essential part of medical device reprocessing. Technical functional tests have to be carried out on the medical device in the course of the validation of reprocessing procedures. These ensure (in addition to the hygiene tests) that the reprocessing procedure is suitable for the medical device. Functional tests are, however, also a part of reprocessing procedures. As a stage in the reprocessing, they ensure for the individual medical device that no damage or other changes limit the performance. When determining which technical-functional tests are to be carried out, the current technological standard has to be taken into account in the form of product-specific and process-oriented norms. Product-specific norms primarily define safety-relevant requirements. The risk management method described in DIN EN ISO 14971 is the basis for recognising hazards; the likelihood of such hazards arising can be minimised through additional technical-functional tests, which may not yet have been standardised. Risk management is part of a quality management system, which must be bindingly certified for manufacturers and processors of critical medical devices with particularly high processing demands by a body accredited by the competent authority.

Screening of external hazards for NPP with bank type reactor. Modeling of safety related systems and equipment for RBMK. Probabilistic assessment of NPP safety on aircraft impact. Progress report

International Nuclear Information System (INIS)

Kostarev, V.

1999-01-01

This progress report was produced within the frame of IAEA research project on screening the hazards for NPP with bank type reactor. It covers the following tasks; development of the model for the primary loop system of RBMK; developing the models for safety related equipment of RBMK; developing of models for safety related models of EGP-6 type reactor (Bilibinskaya Nuclear Co-generated heat and Power Plant); and probabilistic assessment of NPP safety on aircraft impact

IEEE Std 600: IEEE trial-use standard requirements for organizations that conduct qualification testing of safety systems equipment for use in nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1992-01-01

The purpose of this standard is to provide requirements for establishing a program for conducting qualification tests of safety systems equipment used in nuclear power generating stations. Compliance with the requirements of this standard does not assure the adequacy of the qualification tests performed. This standard applies to organizations that conduct qualification tests on equipment that has a definable safety function and is an identifiable part of a safety system for use in nuclear power generating stations. It requires a technical program, a quality assurance program, and a demonstrated ability to meet specified technical requirements. It does not apply to materials tests, production tests, normal performance testing, qualification by analysis, qualification by operating experience, or reliability tests such as diesel-generator multiple start tests. The intent of this standard is to achieve greater consistency, reliability, and reproducibility of test results and to provide adequate control of qualification testing of safety systems equipment

21 CFR 866.4500 - Immunoelectrophoresis equipment.

Science.gov (United States)

2010-04-01

... (CONTINUED) MEDICAL DEVICES IMMUNOLOGY AND MICROBIOLOGY DEVICES Immunology Laboratory Equipment and Reagents... clinical use with its electrical power supply is a device used for separating protein molecules...

Procurement of medical equipment in Sweden

Directory of Open Access Journals (Sweden)

Heikki Terio

2010-02-01

Full Text Available In many hospitals in Sweden the importance of technology management is already accepted and accepted since the hospital managements have recognised that technology is an integral part of all major policy and planning decisions. Today’s medical devices are technically complex and sometimes a system of interacting devices is required to achieve the desired clinical function. If the hospitals want to use the latest, modern technology, then they need to make substantial investments in both equipment and competence. Complex technology, large investments and need of highly qualii ed personnel to handle the medical devices are factors that indicate a need of well-dei ned procurement process as an essential part of the total health technology management system that should be used in a hospital. In such a procurement process, carefully prepared planning of technology investments can reduce the running costs and costs for maintenance substantially. In addition, a well-dei ned procurement process contributes to increase the patient safety. In Karolinska University Hospital goods and services are purchased for more than 20% of the hospital’s €1.2 billion turnover. It is therefore very important that the procurement is carried out ef ectively.

Preliminary safety equipment list for Tank 241-C-106 Manipulator Retrieval System, Project W-340

International Nuclear Information System (INIS)

Guthrie, R.L.

1994-01-01

This document identifies the anticipated safety classification of the estimated major subsystems, based on the projected major functions, that will be used as guidance for the development of the conceptual design of the Manipulator Retrieval System for Tank 241-C-106. This document is intended to be updated as the design of the Manipulator Retrieval System evolves through the conceptual and definitive design phases. The Manipulator Retrieval System is to be capable of removing the hardened sludge heel at the bottom of single shell Tank 241-C-106 and to perform an overall clean out of the tank that leaves a maximum of 360 ft 3 (TPA milestone M-45-00). The thickness of the heel prior to initiation of waste retrieval with the Manipulator Retrieval System is estimated to be 1- to 2-ft. The Manipulator Retrieval System is currently in the pre-conceptual phase with no definitive systems or subsystems. The anticipated retrieval functions for the Manipulator Retrieval System is based on Table 6-2 of WHC-SD-W340-ES-001, Rev. 1. Projected equipment to accomplish these functions were based on the following systems and equipment: Rotary Mode Core Sampling Equipment (WHC-SD-WM-SEL-032); Light Duty Utility Arm System Equipment (WHC-SD-WM-SEL-034); Single Shell Tanks Equipment (WHC-SD-WM-SEL-020)

Periodic orbits of solar sail equipped with reflectance control device in Earth-Moon system

Science.gov (United States)

Yuan, Jianping; Gao, Chen; Zhang, Junhua

2018-02-01

In this paper, families of Lyapunov and halo orbits are presented with a solar sail equipped with a reflectance control device in the Earth-Moon system. System dynamical model is established considering solar sail acceleration, and four solar sail steering laws and two initial Sun-sail configurations are introduced. The initial natural periodic orbits with suitable periods are firstly identified. Subsequently, families of solar sail Lyapunov and halo orbits around the L1 and L2 points are designed with fixed solar sail characteristic acceleration and varying reflectivity rate and pitching angle by the combination of the modified differential correction method and continuation approach. The linear stabilities of solar sail periodic orbits are investigated, and a nonlinear sliding model controller is designed for station keeping. In addition, orbit transfer between the same family of solar sail orbits is investigated preliminarily to showcase reflectance control device solar sail maneuver capability.

Internal Arc: People safety in the electrical wiring

International Nuclear Information System (INIS)

Inchausti, J. M.

2009-01-01

The aim of this article is to describe the internal arc phenomenon, an extremely fast, almost explosive and unattended process of transformation form an initial electric power to the generation of a pressure and heat wave inside the medium its produced its consequences for safety, current methods of limiting them and current regulations in general for equipment used in medium-voltage electrical distribution networks. Taking into account that this type of equipment is found thought the distribution network in both public buildings and unrestricted access areas, safety (of operators and the general public) must be taken into account in the design of equipment and installations to minimize the risk of internal arcs occurring. This is the gist of, for example, ITC 16 of the Spanish Regulation on Power Plants and transformer substations. In addition to the construction aspects specific to each device in which the manufacturer has to takes steps to minimize the risks of an internal arcs occurring. This is the gist of, for example, ITC 16 of the Spanish Regulation on Power Plants and transformer substations. In addition to the construction aspects specific to each device in which an internal arc occurring, it is understood to be vitally important that users, installers and designers of Medium Voltage installations are familiar with the installation conditions stated by the manufacturer and thus avoid risks. (Author) 14 refs

Factors Influencing the Safety Behavior of German Equestrians: Attitudes towards Protective Equipment and Peer Behaviors

Directory of Open Access Journals (Sweden)

Christina-Maria Ikinger

2016-02-01

Full Text Available Human interactions with horses entail certain risks. Although the acceptance and use of protective gear is increasing, a high number of incidents and very low or inconsistent voluntary use of safety equipment are reported. While past studies have examined factors influencing the use of safety gear, they have explored neither their influence on the overall safety behavior, nor their relative influence in relation to each other. The aim of the present study is to fill this gap. We conducted an online survey with 2572 participants. By means of a subsequent multiple regression analysis, we explored 23 different variables in view of their influence on the protective behavior of equestrians. In total, we found 17 variables that exerted a significant influence. The results show that both having positive or negative attitudes towards safety products as well as the protective behavior of other horse owners or riding pupils from the stable have the strongest influence on the safety behavior of German equestrians. We consider such knowledge to be important for both scientists and practitioners, such as producers of protective gear or horse sport associations who might alter safety behavior in such a way that the number of horse-related injuries decreases in the long term.

Safety catching device for pipes in missile shielding cylinders of nuclear power plants

International Nuclear Information System (INIS)

Hering, S.; Doll, B.

1976-01-01

The safety catching device consists of a steel wire passed in U-shape around the pipe to be caught and supported by two anchor ties embedded in the concrete of the missile shielding cylinder. This flexible catching device is to cause the energy released in case of a pipe rupture to be absorbed and no dangerous bending shesses to be transferred to the walls of the missile shielding cylinder. (UWI) [de

Fiscal 1975 Sunshine Project research report. Research on safety technology for hydrogen energy systems; 1975 nendo suiso energy system ni okeru hoan gijutsu ni kansuru chosa kenkyu seika hokokusho

Energy Technology Data Exchange (ETDEWEB)

NONE

1976-05-01

Important notices and problems on the safety for hydrogen gas were analyzed. Analysis was made on hydrogen gas property, flammability, explosivility, bio-toxicity, equipment, storage, transport, leakage, fire, technology and education for safety management, and quality and analysis of products. Study was also made on the relation between the above items and every domestic or overseas standard. Important notices and problems on the safety for liquid hydrogen were analyzed. Analysis was made on liquid hydrogen property, liquefaction and refining equipment, transport, storage, materials concerned, bio-toxicity, leakage, fire fighting technique, and safety management. Among them, such problems are pointed out from the viewpoint of accident prevention, as O-P conversion, refining of hydrogen gas for liquefaction, selection of structural materials, hydrogen embrittlement, layout of various equipment and devices, explosion-proof electric devices, and leakage detection. Research on effective fire fighting and fire preventive measures against hydrogen leakage and diffusion from tanks or piping are also in demand. (NEDO)

Safety evaluation of stamp type digital microneedle devices in hairless mice.

Science.gov (United States)

Park, Kui Young; Jang, Woo Sun; Lim, Yun Young; Ahn, Joo Hee; Lee, Sang Jin; Kim, Chan Woong; Kim, Sung Eun; Kim, Beom Joon; Kim, Myeung Nam

2013-02-01

Microneedles provide a minimally invasive means to transport molecules into the skin. A number of specific strategies have been employed to use microneedles for transdermal delivery. The purpose of this study was to investigate the safety of two new digital microneedle devices (Digital Hand® and Digital Pro®; Bomtech Electronics Co., Ltd., Seoul, Korea) for the perforation of skin in skin-hairless-1 mice. This device replaces conventional needles and is designed specifically for intradermal delivery. We used two newly developed digital microneedle devices to perforate the skin of skin-hairless-1 mice. We conducted a comparative study of the two digital microneedle devices and DTS® (Disk type-microneedle Therapy System; DTS lab., Seoul, Korea). To evaluate skin stability, we performed visual and dermatoscopic inspections, measurements of transepidermal water loss, and biopsies. The two novel digital microneedle devices did not induce significant abnormalities of the skin on visual or dermatoscopic inspection, regardless of needle size (0.25~2.0 mm). No significant histopathological changes, such as inflammatory cell infiltration, desquamation of the stratum corneum, or disruption of the basal layer, were observed. The digital microneedle devices and microneedle therapy system produced similar results on measures of skin stability. These two novel digital microneedle devices are safe transdermal drug delivery systems.

30 CFR 75.811 - High-voltage underground equipment; grounding.

Science.gov (United States)

2010-07-01

...-voltage equipment supplying power to such equipment receiving power from resistance grounded systems shall... 30 Mineral Resources 1 2010-07-01 2010-07-01 false High-voltage underground equipment; grounding... COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Underground High-Voltage...

Design of hoisting device used in nuclear power plants. KTA safety engineering code. Draft amendment, as of 6/98

International Nuclear Information System (INIS)

1998-06-01

The draft amendment specifies, according to the hazards involved, (a) the general provisions, (b) additional provisions supplementing the general provisions, (c) more stringent provisions relating to aggravated risks, applicable to lifting gear, and (d) additional requirements for elevators in reactor containments and refuelling equipment, to be taken into account in the design of hoisting device used in nuclear power plants. The term hoisting device in this context covers elevators, cranes, winches, trolleys, load carrying equipment, and LWR refuelling machines as are used in nuclear power plants. (orig./CB) [de

Study concerning the power plant control and safety equipment by integrated distributed systems

International Nuclear Information System (INIS)

Optea, I.; Oprea, M.; Stanescu, P.

1995-01-01

The paper deals with the trends existing in the field of nuclear control and safety equipment and systems, proposing a high-efficiency integrated system. In order to enhance the safety of the plant and reliability of the structure system and components, we present a concept based on the latest computer technology with an open, distributed system, connected by a local area network with high redundancy. A modern conception for the control and safety system is to integrate all the information related to the reactor protection, active engineered safeguard and auxiliary systems parameters, offering a fast flow of information between all the agencies concerned so that situations can be quickly assessed. The integrated distributed control is based on a high performance operating system for realtime applications, flexible enough for transparent networking and modular for demanding configurations. The general design considerations for nuclear reactors instrumentation reliability and testing methods for real-time functions under dynamic regime are presented. Taking into account the fast progress in information technology, we consider the replacement of the old instrumentation of Cernavoda-1 NPP by a modern integrated system as an economical and efficient solution for the next units. (Author) 20 Refs

Normal people working in normal organizations with normal equipment: system safety and cognition in a mid-air collision.

Science.gov (United States)

de Carvalho, Paulo Victor Rodrigues; Gomes, José Orlando; Huber, Gilbert Jacob; Vidal, Mario Cesar

2009-05-01

A fundamental challenge in improving the safety of complex systems is to understand how accidents emerge in normal working situations, with equipment functioning normally in normally structured organizations. We present a field study of the en route mid-air collision between a commercial carrier and an executive jet, in the clear afternoon Amazon sky in which 154 people lost their lives, that illustrates one response to this challenge. Our focus was on how and why the several safety barriers of a well structured air traffic system melted down enabling the occurrence of this tragedy, without any catastrophic component failure, and in a situation where everything was functioning normally. We identify strong consistencies and feedbacks regarding factors of system day-to-day functioning that made monitoring and awareness difficult, and the cognitive strategies that operators have developed to deal with overall system behavior. These findings emphasize the active problem-solving behavior needed in air traffic control work, and highlight how the day-to-day functioning of the system can jeopardize such behavior. An immediate consequence is that safety managers and engineers should review their traditional safety approach and accident models based on equipment failure probability, linear combinations of failures, rules and procedures, and human errors, to deal with complex patterns of coincidence possibilities, unexpected links, resonance among system functions and activities, and system cognition.

Environmental qualification - walkdowns: The documentation of configuration information for safety related components, equipment and systems

International Nuclear Information System (INIS)

Melmer, J.; Waters, M.

1995-01-01

Environmental Qualification walkdowns are conducted to collect field data to verify/validate/document configurations of safety related equipment and systems. This paper describes the process for conducting walkdowns and the justification for using an electronic format. The following are described: a) Background; b) Preparing, executing and processing walkdowns; c) Hardware/software; d) Impact of a paperless system on walkdown execution, maintenance and work planning; e) Other applications for the technology

Safety analysis for the use of new digital safety I and C systems

International Nuclear Information System (INIS)

Buehler, Cornelia

2012-01-01

Age-induced replacement or modernization of safety I and C systems by digital equipment technology has been one of the topical subjects in nuclear technology for more than a decade. Digital equipment technology in this case means microcontroller- or microprocessor-based systems which implement I and C functions in software (SW) and, on the other hand, systems with programmed hardware (HW) components, such as Application-specific Integrated Circuits (ASIC), Field Programmable Gate Arrays (FPGA) or Programmable Logic Devices (PLS), which can be developed only by means of sophisticated SW development environments. The switch to digital equipment technology is more than a mere change in equipment technology even though the I and C functions remain almost identical in most cases. The switch not only leads to a different approach in equipment qualification, but also requires new focal points in plant design when it comes to assessing plant design, and needs new or adapted methods of analysis and evaluation. The main reason lies in the greater possibilities of systematic errors caused mainly by software-based development, manufacture and maintenance. New and adapted methods of analysis and evaluation for I and C systems are presented and explained. It is safe to say that safety I and C technology in the highest category of requirements necessitates a very far reaching realignment in design and evaluation as well as the use of new analytical techniques. This meets the claim of an I and C technology fit for use, reliable and comparable to the technology it replaces. (orig.)

The Challenges of Balancing Safety and Security in Implantable Medical Devices.

Science.gov (United States)

Katzis, Konstantinos; Jones, Richard W; Despotou, George

2016-01-01

Modern Implantable Medical Devices (IMDs), implement capabilities that have contributed significantly to patient outcomes, as well as quality of life. The ever increasing connectivity of IMD's does raise security concerns though there are instances where implemented security measures might impact on patient safety. The paper discusses challenges of addressing both of these attributes in parallel.

ACCIDENT WITH NEEDLESTICK: KNOWLEDGE AND USE OF SAFETY DEVICE

Directory of Open Access Journals (Sweden)

Sandra Maria Souza da Silva

2016-07-01

Full Text Available Health workers engaged in labour activities in environments surrounded the occupational hazards. Identify knowledge and use of safety devide for preventing accidents with sharp objects between nurses and nurse technicians, workers of the Intensive Care Unit, Emergency and Surgical Block, during the month of may 2015. Exploratory study, quantitative, developed in a teaching hospital in in Recife-PE. The data collection was conducted using a questionnaire prepared by the research authors. The results were submitted to descriptive statistical analysis, being evidenced that, although data indicate high rate of respondents know and use products with referencing safety devices to prevent accidents, cite gloves and masks as representatives of those materials, which requires clarification in discussion of the study. It is necessary to guide and clarify as to such mechanisms, through the permanent education, and training among workers.

Integrated software system for improving medical equipment management.

Science.gov (United States)

Bliznakov, Z; Pappous, G; Bliznakova, K; Pallikarakis, N

2003-01-01

The evolution of biomedical technology has led to an extraordinary use of medical devices in health care delivery. During the last decade, clinical engineering departments (CEDs) turned toward computerization and application of specific software systems for medical equipment management in order to improve their services and monitor outcomes. Recently, much emphasis has been given to patient safety. Through its Medical Device Directives, the European Union has required all member nations to use a vigilance system to prevent the reoccurrence of adverse events that could lead to injuries or death of patients or personnel as a result of equipment malfunction or improper use. The World Health Organization also has made this issue a high priority and has prepared a number of actions and recommendations. In the present workplace, a new integrated, Windows-oriented system is proposed, addressing all tasks of CEDs but also offering a global approach to their management needs, including vigilance. The system architecture is based on a star model, consisting of a central core module and peripheral units. Its development has been based on the integration of 3 software modules, each one addressing specific predefined tasks. The main features of this system include equipment acquisition and replacement management, inventory archiving and monitoring, follow up on scheduled maintenance, corrective maintenance, user training, data analysis, and reports. It also incorporates vigilance monitoring and information exchange for adverse events, together with a specific application for quality-control procedures. The system offers clinical engineers the ability to monitor and evaluate the quality and cost-effectiveness of the service provided by means of quality and cost indicators. Particular emphasis has been placed on the use of harmonized standards with regard to medical device nomenclature and classification. The system's practical applications have been demonstrated through a pilot

Seismic qualification of equipment in operating nuclear power plants. Unresolved safety issue A-46, draft report for comment

International Nuclear Information System (INIS)

Chang, T.Y.

1985-08-01

The margin of safety provided in existing nuclear power plant equipment to resist seismically induced loads and perform their intended safety functions may vary considerably, because of significant changes in design criteria and methods for the seismic qualification of equipment over the years. Therefore, the seismic qualification of equipment in operating plants should be reassessed to determine whether requalification is necessary. The objective of technical studies performed under the Task Action Plan A-46 was to establish an explicit set of guidelines and acceptance criteria to judge the adequacy of equipment under seismic loading at all operating plants, in lieu of requiring qualification to the current criteria that are applied to new plants. This report summarizes the work accomplished on USI A-46 by the Nuclear Regulatory Commission staff and its contractors, Idaho National Engineering Laboratory, Southwest Research Institute, Brookhaven National Laboratory, and Lawrence Livermore National Laboratory. In addition, the collection and review of seismic experience data by the Seismic Qualification Utility Group and the review and recommendations of a group of seismic consultants, the Senior Seismic Review Advisory Panel, are presented. Staff assessment of work accomplished under USI A-46 leads to the conclusion that the use of seismic experience data provides the most reasonable alternative to current qualification criteria. Consideration of seismic qualification by use of experience data was a specific task in USI A-46. Several other A-46 tasks serve to support the use of an experience data base

76 FR 78 - Federal Motor Vehicle Safety Standard; Engine Control Module Speed Limiter Device

Science.gov (United States)

2011-01-03

... [Docket No. NHTSA-2007-26851] Federal Motor Vehicle Safety Standard; Engine Control Module Speed Limiter... occupants. IIHS stated that on-board electronic engine control modules (ECM) will maintain the desired speed... be equipped with an electronic control module (ECM) that is capable of limiting the maximum speed of...

Monitoring readiness of safety relevant devices in nuclear power plants by means of CRT-colour displays

International Nuclear Information System (INIS)

Haubert, R.; Stokke, R.

1980-01-01

The development of an information system for monitoring readiness of safety relevant devices is encouraged by the requirements of KTA-rule 3501 (DIN 25434), which states in section 4.9.1.1. 'A display shall be provided for giving a survey of the condition of the components of the reactor protection system and the active engineered safeguards including their energy and auxiliary media supplies'. In the first stage of the development which was reported at the Enlarged Halden Programme Group Meeting in Loen, Norway, 5th-9th June, 1978, only the components of parts of a BWR-protection system were considered and no display was provided. This paper outlines the next step in the development which comprises implementation of the active engineered safeguards into the system and development of a display system based on a colour CRT-screen. A prototype of this computer-based system for monitoring of protection systems has been established, and it is planned to demonstrate this prototype system using the computer equipment at GRS, Garching (orig./HP)

Leaving patients to their own devices? Smart technology, safety and therapeutic relationships.

Science.gov (United States)

Ho, Anita; Quick, Oliver

2018-03-06

This debate article explores how smart technologies may create a double-edged sword for patient safety and effective therapeutic relationships. Increasing utilization of health monitoring devices by patients will likely become an important aspect of self-care and preventive medicine. It may also help to enhance accurate symptom reports, diagnoses, and prompt referral to specialist care where appropriate. However, the development, marketing, and use of such technology raise significant ethical implications for therapeutic relationships and patient safety. Drawing on lessons learned from other direct-to-consumer health products such as genetic testing, this article explores how smart technology can also pose regulatory challenges and encourage overutilization of healthcare services. In order for smart technology to promote safer care and effective therapeutic encounters, the technology and its utilization must be safe. This article argues for unified regulatory guidelines and better education for both healthcare providers and patients regarding the benefits and risks of these devices.

Evaluation of Generic Issue 57: Effects of fire protection system actuation on safety-related equipment

International Nuclear Information System (INIS)

Lambright, J.; Bohn, M.; Lynch, J.; Ross, S.; Brosseau, D.

1992-12-01

Nuclear power plants have experienced actuations of fire protection systems (FPSs) under conditions for which these systems were not intended to actuate and also have experienced advertent actuations with the presence of a fire. These actuations have often damaged safety-related equipment. A review of the impact of past occurrences of both types of such events and their impact on plant safety systems, an analysis of the risk impacts of such events on nuclear power plant safety, and a cost-benefit analysis of potential corrective measures have been performed. Thirteen different scenarios leading to actuation of fire protection systems due to a variety of causes were identified. These scenarios ranged from inadvertent actuation caused by human error to hardware failure, and include seismic root causes and seismic/fire interactions. A quantification of these thirteen root causes, where applicable, was performed on generically applicable scenarios. This document, Volume 4, contains appendices E and F of this report

Regulatory analysis for the resolution of generic issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment

International Nuclear Information System (INIS)

Woods, H.W.

1993-10-01

Actuation of Fire Protection Systems (FPS) in Nuclear Power Plants have resulted in adverse interactions with equipment important to safety. Precursor operational experience has shown that 37% of all FPS actuations damaged some equipment, and 20% of all FPS actuations have resulted in a plant transient and reactor trip. On an average 0.17 FPS actuations per reactor year have been experienced in nuclear power plants in this country. This report presents the regulatory analysis for GI-57, ''Effects of Fire Protection System Actuation on Safety-Related Equipment''. The risk reduction estimates, cost/benefit analyses, and other insights gained during this effort have shown that implementation of the recommendations contained in this report can significantly reduce risk, and that these improvements can be warranted in accordance with the backfit rule, 10 CFR 50.109(a)(3). However, plant specific analyses are required in order to identify such improvements. Generic analyses can not serve to identify improvements that could be warranted for individual, specific plants. Plant specific analyses of the type needed for this purpose are underway as part of the Individual Plant Examination of External Events (IPEEE) program

46 CFR 109.347 - Pilot boarding equipment.

Science.gov (United States)

2010-10-01

... 46 Shipping 4 2010-10-01 2010-10-01 false Pilot boarding equipment. 109.347 Section 109.347... OPERATIONS Operation and Stowage of Safety Equipment § 109.347 Pilot boarding equipment. (a) The master or person in charge shall ensure that pilot boarding equipment is maintained as follows: (1) The equipment...

Equipment inspection function; A funcao inspecao de equipamentos

Energy Technology Data Exchange (ETDEWEB)

Bressan, Edemir [PETROBRAS (Brazil). Refinaria Alberto Pasqualini

1994-04-01

Development of the safety engineering and equipment inspection policy in petroleum industry, with emphasis to the refineries equipment, are discussed. Presentation of the accidents percentages in petroleum plants under international researches, with details of involved equipment, kind of accident, plant and causes are reported. The start and actual stage of the safety inspection program in the PETROBRAS are also presented 5 refs., 3 figs.

Safety Analysis of 'Older/Aged' Handling and Transportation Equipment for Heavy Loads, Radioactive Waste and Materials in Accordance with German Nuclear Standards KTA 3902, 3903 and 3905

International Nuclear Information System (INIS)

Macias, P.; Prucker, E.; Stang, W.

2006-01-01

The purpose of this paper is to present a general safety analysis of important handling and transportation processes and their related equipment ('load chains' consisting of cranes, load-bearing equipment and load-attaching points). This project was arranged by the responsible Bavarian ministry for environment, health and consumer protection (StMUGV) in agreement with the power plant operators of all Bavarian nuclear power plants to work out potential safety improvements. The range of the equipment (e.g. reactor building, crane, refuelling machine, load-bearing equipment and load-attaching points) covers the handling and transportation of fuel elements (e. g. with fuel flasks), heavy loads (e.g. reactor pressure vessel closure head, shielding slabs) and radioactive materials and waste (e.g. waste flasks, control elements, fuel channels, structure elements). The handling equipment was subjected to a general safety analysis taking into account the ageing of the equipment and the progress of standards. Compliance with the current valid requirements of the state of science and technology as required by German Atomic Act and particularly of the nuclear safety KTA-standards (3902, 3903 and 3905) was examined. The higher protection aims 'safe handling and transportation of heavy loads and safe handling of radioactive materials and waste' of the whole analysis are to avoid a criticality accident, the release of radioactivity and inadmissible effects on important technical equipment and buildings. The scope of the analysis was to check whether these protection aims were fulfilled for all important technical handling and transportation processes. In particularly the design and manufacturing of the components and the regulations of the handling itself were examined. (authors)

An overview of equipment survivability studies at Sandia National Laboratories (SNL)

International Nuclear Information System (INIS)

Bonzon, L.L.; Craft, Ch.M.; McCulloch, W.H.; Sebrell, W.A.

1983-01-01

The USNRC sponsors a number of programs at Sandia National Laboratories (SNL) specifically addressing safety-related equipment survivability. The major thrust of these programs has been the physical testing of equipment. Test results illustrate the importance of a dedicated equipment design effort giving particular attention to the safety implications of the equipment operation. Several equipment survivability tests here have revealed equipment design and test-related deficiencies

Certification of boiler safety equipment with ALSPA P320 system, to IEC 61508 standard; Certification des equipements de securite chaudiere avec le systeme ALSPA P320 selon la norme IEC 61508

Energy Technology Data Exchange (ETDEWEB)

Dalzon, J.P. [Alstom Power (France)

2002-02-01

Safety and environmental protection are major priorities governing Alstom work on control systems (Alspa P320) for power plant applications, especially when potentially dangerous processes like high-power flame boilers (typically rated at 100 to 600 MW) are involved. Here, automatic protection chains are implemented to guard against the risk of serious incident such as explosion and equipment destruction. In this kind of situation, the IEC 61508 standard provides baseline specifications for certification of safety systems. (authors)

Automatic monitoring of vibration welding equipment

Science.gov (United States)

Spicer, John Patrick; Chakraborty, Debejyo; Wincek, Michael Anthony; Wang, Hui; Abell, Jeffrey A; Bracey, Jennifer; Cai, Wayne W

2014-10-14

A vibration welding system includes vibration welding equipment having a welding horn and anvil, a host device, a check station, and a robot. The robot moves the horn and anvil via an arm to the check station. Sensors, e.g., temperature sensors, are positioned with respect to the welding equipment. Additional sensors are positioned with respect to the check station, including a pressure-sensitive array. The host device, which monitors a condition of the welding equipment, measures signals via the sensors positioned with respect to the welding equipment when the horn is actively forming a weld. The robot moves the horn and anvil to the check station, activates the check station sensors at the check station, and determines a condition of the welding equipment by processing the received signals. Acoustic, force, temperature, displacement, amplitude, and/or attitude/gyroscopic sensors may be used.

Design of active feedback for rehabilitation device

Directory of Open Access Journals (Sweden)

Liska Ondrej

2016-01-01

Full Text Available Sensor systems are an essential part of automated equipment. They are even more important in machines that come in contact with people, because they have a significant impact on safety. This paper describes the design of active feedback for rehabilitation device driven by pneumatic artificial muscles. Here are presented three methods for measuring the load of the robot. The first is a system composed of Force Sensitive Resistors (FSR placed in the handle of the device. Two other methods are intended to measure the load of the actuator composed of artificial muscles. The principle of one method is to measure the difference in filling pressures of the muscles, second is based on strain measurement in the drive cables. The paper describes advantages and disadvantages of using each of these methods in a rehabilitation device

CONSIDERATIONS FOR THE DEVELOPMENT OF A DEVICE FOR THE DECOMMISSIONING OF THE HORIZONTAL FUEL CHANNELS IN THE CANDU 6 NUCLEAR REACTOR. PART 6 - PRESENTATION OF THE DECOMMISSIONING DEVICE

Directory of Open Access Journals (Sweden)

Gabi ROSCA FARTAT

2015-05-01

Full Text Available The objective of this paper is to present a possible solution for the designing of a device for the decommissioning of the horizontal fuel channels in the CANDU 6 nuclear reactor. The decommissioning activities are dismantling, demolition, controlled removal of equipment, components, conventional or hazardous waste (radioactive, toxic in compliance with the international basic safety standards on radiation protection. One as the most important operation in the final phase of the nuclear reactor dismantling is the decommissioning of fuel channels. For the fuel channels decommissioning should be taken into account the detailed description of the fuel channel and its components, the installation documents history, adequate radiological criteria for decommissioning guidance, safety and environmental impact assessment, including radiological and non-radiological analysis of the risks that can occur for workers, public and environment, the description of the proposed program for decommissioning the fuel channel and its components, the description of the quality assurance program and of the monitoring program, the equipments and methods used to verify the compliance with the decommissioning criteria, the planning of performing the final radiological assessment at the end of the fuel channel decommissioning. These will include also, a description of the proposed radiation protection procedures to be used during decommissioning. The dismantling of the fuel channel is performed by one device which shall provide radiation protection during the stages of decommissioning, ensuring radiation protection of the workers. The device shall be designed according to the radiation protection procedures. The decommissioning device assembly of the fuel channel components is composed of the device itself and moving platform support for coupling of the selected channel to be dismantled. The fuel channel decommissioning device is an autonomous device designed for

Seismic qualification method of equipment for nuclear power plant

International Nuclear Information System (INIS)

Kim, J.S.; Choi, T.H.; Sulaimana, R.A.

1995-01-01

Safety related equipment installed in Korean Nuclear Power Plants are required to perform a safety function during and after a seismic event. To accomplish this safety function, they must be seismically qualified in accordance with the intent and requirements of the USNRC Reg. Guide 1.100 Rev. 02 and IEEE Std. 344-1987. This paper defines and summarizes acceptable criteria and procedures, based on the Korean experience, for seismic qualification of purchased equipment to be installed in a nuclear power plant. As such the paper is intended to be a concise reference by equipment designers, architectural engineering company and plant owners in uniform implementation of commitments to nuclear regulatory agencies such as the USNRC or Korea Institute of Nuclear Safety (KINS) relating to adequacy of seismic Category 1 equipment. Thus, the paper provides the methodologies which can be used for qualifying equipment for safely related service in Nuclear Power Plants in a cost effective manner

Shields calculations for teletherapy equipment. Regulatory approach of the National Center of Nuclear Safety

International Nuclear Information System (INIS)

Fuente P, A. de la; Dumenigo G, C.; Quevedo G, J.R.; Lopez F, Y.

2006-01-01

The evaluation of applications of construction licenses for the new services of radiotherapy has occupied a significant space in the activity developed by the National Center of Nuclear Safety (CNSN) in the last 2 years. Presently work the experiences of the authors in the evaluation of the required shield for the local where cobalt therapy equipment and lineal accelerators of medical use are used its are exposed, the practical problems detected are approached during the application of the methodologies recommended in both cases and its are discussed which have been the suppositions of items accepted by the Regulatory Authority for the realization of these shield calculations. The accumulated experience allows to assure that the realistic application of the item data and the rational use of the engineering logic makes possible to design local for radiotherapy equipment that fulfill the established dose restrictions in the in use legislation in Cuba, without it implies an excessive expense of construction materials. (Author)

Electronic equipment for spectrometric data processing

International Nuclear Information System (INIS)

Antonov, L.J.; Trenev, A.M.; Todorova, E.I.; Dimitrov, V.D.

1978-01-01

Electronic equipment carrying out logical operations and a full set of the arithmetic operations was developed for spectrometric data processing. The flowsheet of the computing part of the device, made on the basis of a specialized integral circuit, is given. The device includes input registers, multiplexor, matrix commutator, arithmetic unit and indication unit. The equipment is rated to carry out calculations according to comparatively complex formulae in several seconds

The establish and application of equipment reliability database in Nuclear Power Plant

International Nuclear Information System (INIS)

Zheng Wei; Li He

2006-03-01

Take the case of Daya Bay Nuclear Power Plant, the collecting and handling of equipment reliability data, the calculation method of reliability parameters and the establish and application of reliability databases, etc. are discussed. The data source involved the design information of the equipment, the operation information, the maintenance information and periodically test record, etc. Equipment reliability database built on a base of the operation experience. It provided the valid tool for thoroughly and objectively recording the operation history and the present condition of various equipment of the plant; supervising the appearance of the equipment, especially the safety-related equipment, provided the very practical worth information for enhancing the safety and availability management of the equipment and insuring the safety and economic operation of the plant; and provided the essential data for the research and applications in safety management, reliability analysis, probabilistic safety assessment, reliability centered maintenance and economic management in nuclear power plant. (authors)

Materials for electrochemical device safety

Science.gov (United States)

Vissers, Daniel R.; Amine, Khalil; Thackeray, Michael M.; Kahaian, Arthur J.; Johnson, Christopher S.

2015-04-07

An electrochemical device includes a thermally-triggered intumescent material or a gas-triggered intumescent material. Such devices prevent or minimize short circuits in a device that could lead to thermal run-away. Such devices may include batteries or supercapacitors.

46 CFR 184.220 - Cooking equipment.

Science.gov (United States)

2010-10-01

... 46 Shipping 7 2010-10-01 2010-10-01 false Cooking equipment. 184.220 Section 184.220 Shipping...) VESSEL CONTROL AND MISCELLANEOUS SYSTEMS AND EQUIPMENT Cooking and Heating § 184.220 Cooking equipment. (a) Doors on a cooking appliance must be provided with hinges and locking devices to prevent...

Orthopaedic Rehabilitation Device Actuated with Pneumatic Muscles

Directory of Open Access Journals (Sweden)

Ioana Petre

2014-07-01

Full Text Available Year after year recovery clinics worldwide report significant numbers of lower limb bearing joint disabilities. An effective method for the speedy rehabilitation of patients with such afflictions is Continuous Passive Motion (CPM, drawing upon a range of specific equipment. This paper presents an innovative constructive solution for such orthopaedic rehabilitation equipment, designed to ensure a swift reintegration of patients at as low a cost as possible. The absolute novelty consists in the utilization of the linear pneumatic muscle as actuator of the orthopaedic rehabilitation equipment, thus achieving a light and highly compliant construction that satisfies safety requirements related to man-machine interaction. Pneumatic muscles are bio-inspired actuation systems characterized by a passive variable compliant behaviour. This property, deployed in rehabilitation systems, enables the development of human friendly devices, which are comfortable for the patients, and capable of safe interaction. This paper presents the constructive schematic of the orthopaedic rehabilitation equipment, the structure of the actuation and positioning system, and several of its functional characteristics.

78 FR 25916 - Authorization of Radiofrequency Equipment

Science.gov (United States)

2013-05-03

...] Authorization of Radiofrequency Equipment AGENCY: Federal Communications Commission. ACTION: Proposed rule... bodies, and measurement procedures used to determine RF equipment compliance. The Commission believes... Commission is responsible for an equipment authorization program for radiofrequency (RF) devices under part 2...

Safety shutdowns and failures of the RA reactor equipment; Sigurnosna zaustavljanja i kvarovi opreme na reaktoru RA

Energy Technology Data Exchange (ETDEWEB)

Mitrovic, S [Institut za nuklearne nauke ' Boris Kidric' , Vinca, Belgrade (Yugoslavia)

1966-07-01

This report is an attempt of statistical analysis of the failures occurred during RA reactor operation. A list of failures occurred on the RA equipment during 1965 is included. Failures were related to the following systems: dosimetry system (22%), safety and control system (7%), heavy water system (2%), technical water (4%), helium system (2%), measuring instruments (30%), transport, ventilation, power supply systems (32%). A review of safety shutdowns from 1962 to 1966 is included as well, as a comparison with three similar reactors. Although the number of events used for statistical analysis was not adequate, it has been concluded that RA reactor operation was stable and reliable.

Statistical analysis of the behaviour of the mechanical equipment of EDFs power plants - evaluation of the availability and safety of thermal and nuclear units

International Nuclear Information System (INIS)

Procaccia, H.; Brillon, A.; Cravero, M.; Lucenet, G.

1975-01-01

The investigation and research directorate of EDF has undertaken a statistical analysis of the behaviour of large mechanical equipment at conventional power stations during the ten years following the operating reports of these stations. It has thus been possible to determine the intrinsic reliability, the failure rate, the mean repair time, and the mean good operating time of feed water reheating points, power turbines, pumps and boilers of the various EDF plants (125 and 250 MW) leading to a consideration of the feasibility of an extrapolation to present and future plants. Based on these elementary investigation two methods of calculation have been developed. One is used to assess the overall availability of a thermal or nuclear power station based on the knowledge of the failure rates of the equipment, each piece of equipment being associated with an idea of its technical importance in the functioning of the equipment. A numerical application is given for 125 and 250 MW conventional plants. The purpose of the other method is to estimate the operational safety of the safety equipment of nuclear power stations, based on the development of tree diagrams for faults in basic equipment. A numerical example is given for the cooling systems for Phenix and for one of the Super Phenix versions. (author)

Modernization of Unit 2 at Oskarshamn NPP- Main Objectives, Experience from Design, Separation of Operational and Nuclear Safety Equipment - Lessons Learned

International Nuclear Information System (INIS)

Kanaan, Salah K.

2015-01-01

This paper aims to give a picture of Oskarshamn Nuclear Power Plant (OKG) experience from design for one of the biggest modernization project in the world and focuses on what was learned that is specific to robustness of electrical power systems, especially through Fukushima Station Blackout (SBO). The planning for unit 2 at OKG was initiated in 1967 and the plant was completed on time and was synchronized to the grid October 2, 1974 and is of type BWR. Unit 2 was originally on 580 MW. In 1982 a thermal power up-rate was performed, from 1700 MWh to 1800 MWh (106% reactor output). A decision was made to perform a modernization and a new power up-rate to 850 MW and there were several reasons for this decision; New safety regulations from Swedish Radiation Safety Authority (SSM), Ageing of important components and the initial focus was on safety and availability - Project Plant Life Extension (Plex) was established and became the largest nuclear power modernization in the world. The modernization will lead to: - New safety concept with 4 divisions instead for existing 2 with 2 new buildings South Electrical Building (SEB) and North Electrical Building (NEB); - Completely new software - based equipments for monitoring, control and I and C; - New Low Pressure Turbine, new generator and main transformer; - New MCR and simulator; - Compliance with modern reactor safety requirements; - Redundancy, Separation, Diversification, Earthquake; - Reinforcement of existing safety functions; - New Electricity - I and C (electric power incl. reinforced emergency power and control systems); - New buildings for Electricity - I and C; - Reinforcement of existing process systems as well as installation of new ones. Based on studies and good experiences on how to separate the operational and the safety equipment, the project led to a completely new safety concept. The safety concept is based on fully understanding the safety system that shall encompass all of the elements required to

Challenges and Prospects of Equipment Health Monitoring with Wireless Sensor Network in Nuclear Power Plants

International Nuclear Information System (INIS)

Chen, Dongyi; Jiang, Jin; Bari, Ataul; Wang, Quan; Hashemian, Hash-M.

2014-01-01

A wireless sensor network (WSN) system can offer tremendous benefits to equipment condition monitoring in newly-constructed and/or refurbished nuclear power plants (NPPs). However, it has not been widely accepted so far because of the following requirements by the NPP operators ectromagnetic (EM) emissions from the wireless transceivers must not interfere with the functionalities of the sensitive safety and protection systems in the plant, WSN must perform reliably in the presence of high levels of EM interference from devices such as relays and motor driven pumps, and ionizing radiation sources, dependable WSN performance in harsh industrial environments that are cluttered with cable trays, piping, valves, pumps, motors, and concrete and steel structures, and trict compliance with nuclear regulatory guidelines on EM emissions by the wireless devices. This paper will review the key issues associated with the deployment of WSN for equipment condition monitoring in NPPs. Some promising WSN technologies that can be used in NPP applications are also discussed

Challenges and Prospects of Equipment Health Monitoring with Wireless Sensor Network in Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Chen, Dongyi [University of Electronic Science and Technology of China, Chengdu (China); Jiang, Jin; Bari, Ataul; Wang, Quan [University of Western Ontario, Ontario (Canada); Hashemian, Hash-M. [AMS Technology Center Knoxville (United States)

2014-08-15

A wireless sensor network (WSN) system can offer tremendous benefits to equipment condition monitoring in newly-constructed and/or refurbished nuclear power plants (NPPs). However, it has not been widely accepted so far because of the following requirements by the NPP operators ectromagnetic (EM) emissions from the wireless transceivers must not interfere with the functionalities of the sensitive safety and protection systems in the plant, WSN must perform reliably in the presence of high levels of EM interference from devices such as relays and motor driven pumps, and ionizing radiation sources, dependable WSN performance in harsh industrial environments that are cluttered with cable trays, piping, valves, pumps, motors, and concrete and steel structures, and trict compliance with nuclear regulatory guidelines on EM emissions by the wireless devices. This paper will review the key issues associated with the deployment of WSN for equipment condition monitoring in NPPs. Some promising WSN technologies that can be used in NPP applications are also discussed.

Systems analysis of radiation safety during dismantling of power-plant equipment at a nuclear power station

International Nuclear Information System (INIS)

Bylkin, B.K.; Shpitser, V.Ya.

1993-01-01

A systems analysis of the radiation safety makes possible an ad hoc determination of the elements forming the system, as well as the establishment of the characteristics of their interaction with radiation-effect factors. Here the authors will present part of the hierarchical analysis procedure, consisting in general of four separate procedures. The purpose is to investigate and analyze the mean and stable (on the average) indices of radiation safety, within the framework of alternative mathematical models of dismantling the power-plant equipment of a nuclear power station. The following three of the four procedures are discussed: (1) simulated projection, of the processing of radioactive waste; (2) analysis of the redistribution of radionuclides during the industrial cycle of waste treatment; (3) planning the collective dose load during the dismantling operation. Within the framework of the first of these procedures, the solutions to the problem of simulating a waste-treatment operation of maximum efficiency are analyzed. This analysis is based on the use of a data base for the parameters of the installations, assemblies, and equipment, enabling the integration of these in a simulation of a complex automated facility. The results were visualized in an AUTOCAD-10 medium using a graphical data base containing an explanation of the rooms

Days individual equipment of protection and professional risks; Equipements de protection individuelle et risques professionnelles

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

The personal protection equipment is studied in the legal way (legal liabilities, certification, European texts), technical way (ergonomics, painfulness of ventilated equipment wearing, reliability of a respirable air line, protection gloves against the chemical risk, exposure to nano particulates, working in hot area), human factors (hostile area and emotion management), studies on personal equipment such evaluation, efficiency, conception of new equipment, physiological tolerance, limit of use, and some general safety studies on the working places. (N.C.)

Economic benefits of safety-engineered sharp devices in Belgium - a budget impact model.

Science.gov (United States)

Hanmore, Emma; Maclaine, Grant; Garin, Fiona; Alonso, Alexander; Leroy, Nicolas; Ruff, Lewis

2013-11-25

Measures to protect healthcare workers where there is risk of injury or infection from medical sharps became mandatory in the European Union (EU) from May 2013. Our research objective was to estimate the net budget impact of introducing safety-engineered devices (SEDs) for prevention of needlestick injuries (NSIs) in a Belgian hospital. A 5-year incidence-based budget impact model was developed from the hospital inpatient perspective, comparing costs and outcomes with SEDs and prior-used conventional (non-safety) devices. The model accounts for device acquisition costs and costs of NSI management in 4 areas of application where SEDs are currently used: blood collection, infusion, injection and diabetes insulin administration. Model input data were sourced from the Institut National d'Assurance Maladie-Invalidité, published studies, clinical guidelines and market research. Costs are discounted at 3%. For a 420-bed hospital, 100% substitution of conventional devices by SEDs is estimated to decrease the cumulative 5-year incidence of NSIs from 310 to 75, and those associated with exposure to blood-borne viral diseases from 60 to 15. Cost savings from managing fewer NSIs more than offset increased device acquisition costs, yielding estimated 5-year overall savings of €51,710. The direction of these results is robust to a range of sensitivity and model scenario analyses. The model was most sensitive to variation in the acquisition costs of SEDs, rates of NSI associated with conventional devices, and the acquisition costs of conventional devices. NSIs are a significant potential risk with the use of sharp devices. The incidence of NSIs and the costs associated with their management can be reduced through the adoption of safer work practices, including investment in SEDs. For a Belgian hospital, the budget impact model reports that the incremental acquisition costs of SEDs are offset by the savings from fewer NSIs. The availability of more robust data for NSI reduction

Changing nature of equipment and parts qualification

International Nuclear Information System (INIS)

Bucci, R.M.

1988-01-01

Ideally, the original supplier of a piece of nuclear safety-related equipment has performed a qualification program and will continue to support that equipment throughout the lifetime of the nuclear power plants in which in equipment is installed. The supplier's nuclear quality assurance program will be maintained and he will continue to offer all necessary replacement parts. These parts will be identical to the original parts, certified to the original purchase order requirements, and the parts will be offered at competitive prices. Due to the changing nature of the nuclear plant equipment market, however, one or more of those ideal features are frequently unavailable when safety-related replacement equipment or parts are required. Thus, the process of equipment and parts qualification has had to adjust in order to ensure obtaining qualified replacements when needed. This paper presents some new directions taken in the qualification of replacement equipment and parts to meet changes in the marketplace

The efficacy and safety of a novel posterior scleral reinforcement device in rabbits

Energy Technology Data Exchange (ETDEWEB)

Yuan, Yongguang; Zong, Yao; Zheng, Qishan [State Key Laboratory of Ophthalmology, Zhongshan Ophthalmic Center, Sun Yat-sen University, Guangzhou (China); Qian, Garrett [University of New South Wales (Australia); Qian, Xiaobin; Li, Yujie; Shao, Wanwen [State Key Laboratory of Ophthalmology, Zhongshan Ophthalmic Center, Sun Yat-sen University, Guangzhou (China); Gao, Qianying, E-mail: gaoqy@mail.sysu.edu.cn [State Key Laboratory of Ophthalmology, Zhongshan Ophthalmic Center, Sun Yat-sen University, Guangzhou (China)

2016-05-01

Purpose: To evaluate the efficacy and safety of posterior scleral reinforcement (PSR) device for myopia suppression in rabbits' eyes. Methods: PSR surgery was performed on the normal 12 8-week-old New Zealand white rabbits' right eyes. To determine efficacy of the device, ophthalmic examination would be taken at pre-operation and post-operation (1 week, 1 month, 3 months, 6 months, and 1 year), such as A-ultrasound, diopter and B-ultrasound. Evaluation of safety were based on the following indicators: intraocular pressure (IOP), slit lamp, fundus photography, fundus fluorescein angiography and pathological examination after surgery. The efficacy and safety of PSR device were evaluated by comparison (treated eyes and contralateral eyes) of pre and post-operation. Results: The novel PSR device could significantly shorten axial length (preoperative axial length: 16.36 ± 0.14 mm, postoperative 1 week, 1 month, 3 months, 6 months and 1 year axial lengths: 15.03 ± 0.28 mm, 15.23 ± 0.32 mm, 15.39 ± 0.31 mm, 15.45 ± 0.22 mm and 15.45 ± 0.22 mm; P = 0.00037 < 0.001) in the treated eyes (right eyes) after surgery. At different postoperative time points, the B-ultrasound images showed that the PSR located in appropriate position and supported the posterior sclera very well. At the same time, IOP of treated eyes kept a relatively stable level (preoperative IOP: 12.56 ± 2.01 mmHg, postoperative IOP: ranging from 11.33 ± 1.23 mmHg to 13.44 ± 2.19 mmHg, P > 0.05) post-operation 1 year. During observation period, there was no significant inflammatory reaction and complications such as anterior chamber flare, empyema, endophthalmitis, vitreous hemorrhage, retina detachment and retinal choroid neovascularization by slit lamp, fundus photography and fundus fluorescein angiography. In addition, there were no pathologic changes be found by comparison treated eyes group and contralateral group eyes based on pathological examinations. Conclusions: In vivo study

IE Bulletin No. 79-01: Environmental qualification of Class IE equipment

International Nuclear Information System (INIS)

Anon.

1993-01-01

The intent of IE Circular 78-08 was to highlight to all licensees important lessons learned from environmental qualification deficiencies reported by individual licensees. In this regard, licensees were requested to examine installed safety-related electrical equipment and determine that proper documentation existed which provided assurance that this equipment would function under postulated accident conditions. The intent of this Bulletin is to raise the threshold of IE Circular 78-08 to the level of a Bulletin; i.e., action requiring a licensee response. Inspections conducted to date by the NRC of licensees' activities in response to IE Circular 78-08 have identified one component which licensees have found to be unqualified for service within the LOCA environment. Specifically, unqualified stem mounted limit switches (SMLS), other than those identified in previously issued IE Bulletin 78-04, were found to be installed on safety-related valves inside containment at both Duane Arnold and Quad Cities 1 and 2 Nuclear Generating Stations. According to the manufacturer, these switches are designed only for general purpose applications and are not considered suitable devices for service in the LOCA environment. Consequently, switches are being replaced at the above power plants with qualified components

Terms standardization between the rules of diagnosis radiation equipment safety management and atomic energy law: problems and suggestions

Energy Technology Data Exchange (ETDEWEB)

Kim, Hwa Gon; Kang, Se Sik; Kim, Chang Soo; Park, Cheol Seo [Catholic University of Pusan, Busan (Korea, Republic of)

2006-03-15

The rules and terms are described different meaning in this results the research is accomplished for preventing practical workers from confusion. Atomic law are kept up modification and development in our situation by the ICRP's recommendation, on the other hand, the rules of diagnosis radiation equipment safety managements are modified partial, then resulted in confusion. The study was comparison between the rules of diagnosis radiation equipment safety management and atomic energy law, and the modification items obtained were as follows. With each other different the terms and units are used. With the exception of special terms for affairs usage, it is needless to say that common term uniformity is standardized. The standardization of rules and guidance have not need to confusion radiological practical workers. The following is omitted. The radiation protection against the patient and the hospital visitor. Radiation dose limit of the woman patient who is in the process of becoming pregnant. Radiation dose limit of the person who is not regarded as medical exposure. The control of the exposure of pregnant of women at work.

Terms standardization between the rules of diagnosis radiation equipment safety management and atomic energy law: problems and suggestions

International Nuclear Information System (INIS)

Kim, Hwa Gon; Kang, Se Sik; Kim, Chang Soo; Park, Cheol Seo

2006-01-01

The rules and terms are described different meaning in this results the research is accomplished for preventing practical workers from confusion. Atomic law are kept up modification and development in our situation by the ICRP's recommendation, on the other hand, the rules of diagnosis radiation equipment safety managements are modified partial, then resulted in confusion. The study was comparison between the rules of diagnosis radiation equipment safety management and atomic energy law, and the modification items obtained were as follows. With each other different the terms and units are used. With the exception of special terms for affairs usage, it is needless to say that common term uniformity is standardized. The standardization of rules and guidance have not need to confusion radiological practical workers. The following is omitted. The radiation protection against the patient and the hospital visitor. Radiation dose limit of the woman patient who is in the process of becoming pregnant. Radiation dose limit of the person who is not regarded as medical exposure. The control of the exposure of pregnant of women at work

Inherent Risk or Risky Decision? Coach's Failure to Use Safety Device an Assumed Risk

Science.gov (United States)

Dodds, Mark A.; Bochicchio, Kristi Schoepfer

2013-01-01

The court examined whether a coach's failure to implement a safety device during pitching practice enhanced the risk to the athlete or resulted in a suboptimal playing condition, in the context of the assumption of risk doctrine.

Unique aspects of downhill ski injuries part 1: epidemiology and equipment.

Science.gov (United States)

Buck, P G; Sophocles, A M; Beckenbauch, R D

1982-03-01

Skiing is an exciting sport with a significant potential /or serious injury. This potential for injury can be minimized but never entirely eliminated by modern safety equipment.Upper extremity injuries have become relatively more common as the incidence of lower extremity injuries has decreased. Ankle and foot injuries have become infrequent since the advent of the rigid plastic boot, while the incidence of knee injuries has remained essentially constant.Three major mechanisms of injury to the lower extremity include external rotation and abduction, forward fall, and internal rotation. Each mechanism can produce a distinctive set of injured structures.The "skier at risk" is characterized by a lower level of ability, lighter weight, and extremes of age. Injuries can be minimized by purchasing good quality equipment and maintaining it properly; discarding obsolete equipment; using ski brakes, antifriction devices and pistol grip poles; using multirelease bindings for beginners or intermediates; good physical conditioning; taking ski lessons and coupling this with skiing experience; and skiing in control and using common sense on the slopes.Areas which need the most improvement in equipment design include multi-release bindings suitable for all skiers and children's boots. Copyright 2013, SLACK Incorporated.

Radiation protection and safety in industrial radiography

International Nuclear Information System (INIS)

1999-01-01

The use of ionizing radiation, particularly in medicine and industry, is growing throughout the world, with further expansion likely as technical developments result from research. One of the longest established applications of ionizing radiation is industrial radiography, which uses both X radiation and gamma radiation to investigate the integrity of equipment and structures. Industrial radiography is widespread in almost all Member States. It is indispensable to the quality assurance required in modern engineering practice and features in the work of multinational companies and small businesses alike. Industrial radiography is extremely versatile. The equipment required is relatively inexpensive and simple to operate. It may be highly portable and capable of being operated by a single worker in a wide range of different conditions, such as at remote construction sites, offshore locations and cross-country pipelines as well as in complex fabrication facilities. The associated hazards demand that safe working practices be developed in order to minimize the potential exposure of radiographers and other persons who may be in the vicinity of the work. The use of shielded enclosures (fixed facilities), with effective safety devices, significantly reduces any radiation exposures arising from the work. This Safety Report summarizes good and current state of the art practices in industrial radiography and provides technical advice on radiation protection and safety. It contains information for Regulatory Authorities, operating organizations, workers, equipment manufacturers and client organizations, with the intention of explaining their responsibilities and means to enhance radiation protection and safety in industrial radiography

30 CFR 75.509 - Electric power circuit and electric equipment; deenergization.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Electric power circuit and electric equipment... LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Electrical Equipment-General § 75.509 Electric power circuit and electric equipment; deenergization. [Statutory Provisions] All...

Waste heat recovering device for reactors

International Nuclear Information System (INIS)

Sonoda, Masanobu; Shiraishi, Tadashi; Mizuno, Hiroyuki; Sekine, Yasuhiro.

1982-01-01

Purpose: To enable utilization of auxiliary-equipment-cooling water from a non-regenerative heat exchanger as a heat source, as well as prevent radioactive contamination. Constitution: A water warming device for recovering the heat of auxiliary equipment cooling water from a non-regenerative heat exchanger is disposed at the succeeding stage of the heat exchanger. Heat exchange is performed in the water warming device between the auxiliary equipment cooling water and a heat source water set to a higher pressure and recycled through the water warming device. The heat recovered from the auxiliary equipment cooling water is utilized in the heat source water for operating relevant equipments. (Aizawa, K.)

Regulatory process for material handling equipment

International Nuclear Information System (INIS)

Rajendran, S.; Agarwal, Kailash

2017-01-01

Atomic Energy (Factories) Rules (AEFR) 1996, Rule 35 states, 'Thorough inspection and load testing of a Crane shall be done by a Competent Person at least once every 12 months'. To adhere to this rule, BARC Safety Council constituted 'Material Handling Equipment Committee (MHEC)' under the aegis of Conventional Fire and Safety Review Committee (CFSRC) to carry out periodical inspection and certification of Material Handling Equipment (MHE), tools and tackles used in BARC Facilities at Trombay, Tarapur and Kalpakkam

Access Safety Systems – New Concepts from the LHC Experience

CERN Document Server

Ladzinski, T; di Luca, S; Hakulinen, T; Hammouti, L; Riesco, T; Nunes, R; Ninin, P; Juget, J-F; Havart, F; Valentini, F; Sanchez-Corral Mena, E

2011-01-01

The LHC Access Safety System has introduced a number of new concepts into the domain of personnel protection at CERN. These can be grouped into several categories: organisational, architectural and concerning the end-user experience. By anchoring the project on the solid foundations of the IEC 61508/61511 methodology, the CERN team and its contractors managed to design, develop, test and commission on time a SIL3 safety system. The system uses a successful combination of the latest Siemens redundant safety programmable logic controllers with a traditional relay logic hardwired loop. The external envelope barriers used in the LHC include personnel and material access devices, which are interlocked door-booths introducing increased automation of individual access control, thus removing the strain from the operators. These devices ensure the inviolability of the controlled zones by users not holding the required credentials. To this end they are equipped with personnel presence detectors and th...

Maintenance program guidelines for programmatic equipment

International Nuclear Information System (INIS)

1994-11-01

The Division Directors at Lawrence Berkeley Laboratory are responsible for implementing a maintenance program for research equipment (also referred to as programmatic equipment) assigned to them. The program must allow maintenance to be accomplished in a manner that promotes operational safety, environmental protection and compliance, and cost effectiveness; that preserves the intended functions of the facilities and equipment; and that supports the programmatic mission of the Laboratory. Programmatic equipment -- such as accelerators, lasers, radiation detection equipment, and glove boxes -- is dedicated specifically to research. Installed equipment, by contrast, includes the mechanical and electrical systems installed as part of basic building construction, equipment essential to the normal functioning of the facility and its intended use. Examples of installed equipment are heating, ventilating, and air conditioning systems; elevators; and communications systems. The LBL Operating and Assurance Program Plan (PUB-3111, Revision 4) requires that a maintenance program be prepared for programmatic equipment and defines the basic maintenance program elements. Such a program of regular, documented maintenance is vital to the safety and quality of research activities. As a part of that support, this document offers guidance to Laboratory organizations for developing their maintenance programs. It clarifies the maintenance requirements of the Operating and Assurance Program (OAP) and presents an approach that, while not the only possibility, can be expected to produce an effective maintenance program for research equipment belonging to the Laboratory's organizations

Medium-voltage switching devices: State-of-the art on technical standards; Mittelspannungs-Schaltanlagen: Stand der technischen Normen

Energy Technology Data Exchange (ETDEWEB)

Voss, Gerhard [Ingenieurbuero IGV Elektrotechnik, Ladenburg (Germany)

2008-11-15

With enhanced exchange box systems many low voltage switch devices can be equipped more compact (less volume demand), cost friendly and more reliable because of advanced arc discharge safety engineering. Presented is utilization and operation in the facility managment and industrial applications in detail. In the last years operation-important standards have been revised for planners and users. So users and planners have to occupy with new standards for medium-voltage switching devices. This knowledge forms the conditions to design devices in future extensively to individual demands of the company and according to standards. (GL)

Supplement to safety analysis report. 306-W building operations safety requirement

International Nuclear Information System (INIS)

Richey, C.R.

1979-08-01

The operations safety requirements (OSRs) presented in this report define the conditions, safe boundaries, and management control needed for safely conducting operations with radioactive materials in the Pacific Northwest Laboratory (PNL) 306-W building. The safety requirements are organized in five sections. Safety limits are safety-related process variables that are observable and measurable. Limiting conditions cover: equipment and technical conditions and characteristics of the facility and operations necessary for continued safe operation. Surveillance requirements prescribe the requirements for checking systems and components that are essential to safety. Equipment design controls require that changes to process equipment and systems be independently checked and approved to assure that the changes will have no adverse effect on safety. Administrative controls describe and discuss the organization and administrative systems and procedures to be used for safe operation of the facility. Details of the implementation of the operations safety requirements are prescribed by internal PNL documents such as criticality safety specifications and radiation work procedures

Wheeled mobility device transportation safety in fixed route and demand-responsive public transit vehicles within the United States.

Science.gov (United States)

Frost, Karen L; van Roosmalen, Linda; Bertocci, Gina; Cross, Douglas J

2012-01-01

An overview of the current status of wheelchair transportation safety in fixed route and demand-responsive, non-rail, public transportation vehicles within the US is presented. A description of each mode of transportation is provided, followed by a discussion of the primary issues affecting safety, accessibility, and usability. Technologies such as lifts, ramps, securement systems, and occupant restraint systems, along with regulations and voluntary industry standards have been implemented with the intent of improving safety and accessibility for individuals who travel while seated in their wheeled mobility device (e.g., wheelchair or scooter). However, across both fixed route and demand-responsive transit systems a myriad of factors such as nonuse and misuse of safety systems, oversized wheeled mobility devices, vehicle space constraints, and inadequate vehicle operator training may place wheeled mobility device (WhMD) users at risk of injury even under non-impact driving conditions. Since WhMD-related incidents also often occur during the boarding and alighting process, the frequency of these events, along with factors associated with these events are described for each transit mode. Recommendations for improving WhMD transportation are discussed given the current state of

A fail-safe design for X-ray safety shutters

International Nuclear Information System (INIS)

Cramer, W.E.; Port, E.A.

1982-01-01

The purpose of any safety shutter device is to help minimize radiation exposure to personnel. Many such devices for analytical X-ray work may fail in a mode with great potential for injury. The authors present a design that may be used to modify any existing mechanical or electro-mechanical system that utilizes a gate which blocks an aperture to control exposure. The system is of 'fail-safe' design, as defined in the National Bureau of Standards Handbook 111 (American National Standards Institute, 1972); One in which all reasonable anticipated failures of indicator or safety components will cause the equipment to respond in a mode ensuring that personnel are safe from exposure to radiation. The system has visible indicators that make the user aware that a particular failure has occurred; in addition, X-ray generation ceases. (Auth.)

TU-G-213-02: IEC Subcommittee 62B (Diagnostic Imaging Equipment): Recent and Active Projects

International Nuclear Information System (INIS)

Supanich, M.

2015-01-01

The International Electrotechnical Commission (IEC) writes standards that manufacturers of electrical equipment must comply with. Medical electrical equipment, such as medical imaging, radiation therapy, and radiation dosimetry devices, fall under Technical Committee 62. Of particular interest to medical physicists are the standards developed within Subcommittees (SC) 62B, which addresses diagnostic radiological imaging equipment, and 62C, which addresses equipment for radiation therapy, nuclear medicine and dosimetry. For example, a Working Group of SC 62B is responsible for safety and quality assurance standards for CT scanners and a Working Group of SC 62C is responsible for standards that set requirements for dosimetric safety and accuracy of linacs and proton accelerators. IEC standards thus have an impact on every aspect of a medical physicist’s job, including equipment testing, shielding design, room layout, and workflow. Consequently, it is imperative that US medical physicists know about existing standards, as well as have input on those under development or undergoing revision. The structure of the IEC and current standards development work will be described in detail. The presentation will explain how US medical physicists can learn about IEC standards and contribute to their development. Learning Objectives: Learn about the structure of the IEC and the influence that IEC standards have on the design of equipment for radiology and radiation therapy. Learn about the mechanisms by which the US participates in the development and revision of standards. Understand the specific requirements of several standards having direct relevance to diagnostic and radiation therapy physicists

TU-G-213-02: IEC Subcommittee 62B (Diagnostic Imaging Equipment): Recent and Active Projects

Energy Technology Data Exchange (ETDEWEB)

Supanich, M. [Rush University Medical Center (United States)

2015-06-15

The International Electrotechnical Commission (IEC) writes standards that manufacturers of electrical equipment must comply with. Medical electrical equipment, such as medical imaging, radiation therapy, and radiation dosimetry devices, fall under Technical Committee 62. Of particular interest to medical physicists are the standards developed within Subcommittees (SC) 62B, which addresses diagnostic radiological imaging equipment, and 62C, which addresses equipment for radiation therapy, nuclear medicine and dosimetry. For example, a Working Group of SC 62B is responsible for safety and quality assurance standards for CT scanners and a Working Group of SC 62C is responsible for standards that set requirements for dosimetric safety and accuracy of linacs and proton accelerators. IEC standards thus have an impact on every aspect of a medical physicist’s job, including equipment testing, shielding design, room layout, and workflow. Consequently, it is imperative that US medical physicists know about existing standards, as well as have input on those under development or undergoing revision. The structure of the IEC and current standards development work will be described in detail. The presentation will explain how US medical physicists can learn about IEC standards and contribute to their development. Learning Objectives: Learn about the structure of the IEC and the influence that IEC standards have on the design of equipment for radiology and radiation therapy. Learn about the mechanisms by which the US participates in the development and revision of standards. Understand the specific requirements of several standards having direct relevance to diagnostic and radiation therapy physicists.

47 CFR 15.305 - Equipment authorization requirement.

Science.gov (United States)

2010-10-01

... Section 15.305 Telecommunication FEDERAL COMMUNICATIONS COMMISSION GENERAL RADIO FREQUENCY DEVICES Unlicensed Personal Communications Service Devices § 15.305 Equipment authorization requirement. PCS devices... 2 of this chapter before marketing. The application for certification must contain sufficient...

Radiation therapy sources, equipment and installations

International Nuclear Information System (INIS)

2011-03-01

The safety code for Telegamma Therapy Equipment and Installations, (AERB/SC/MED-1) and safety code for Brachytherapy Sources, Equipment and Installations, (AERB/SC/MED-3) were issued by AERB in 1986 and 1988 respectively. These codes specified mandatory requirements for radiation therapy facilities, covering the entire spectrum of operations ranging from the setting up of a facility to its ultimate decommissioning, including procedures to be followed during emergency situations. The codes also stipulated requirements of personnel and their responsibilities. With the advent of new techniques and equipment such as 3D-conformal radiation therapy, intensity modulated radiation therapy, image guided radiation therapy, treatment planning system, stereotactic radiosurgery, stereotactic radiotherapy, portal imaging, integrated brachytherapy and endovascular brachytherapy during the last two decades, AERB desires that these codes be revised and merged into a single code titled Radiation Therapy Sources, Equipment, and Installations

AERB information booklet: personal protective equipment- safety footwear

International Nuclear Information System (INIS)

1992-01-01

The main classes of safety footwear required for industrial operations in the units of Department of Atomic Energy are the following; leather safety boots and shoes, firemen's leather boots - Wellington type, electrical safety shoes, chemical safety shoes, shoes suitable for mining operations. The criteria to be adopted for selection of safety shoes for nuclear installations are given. (M.K.V.). 5 annexures, 1 appendix

Equipment abnormality monitoring method and device therefor

International Nuclear Information System (INIS)

Yamada, Izumi; Asakura, Yamato; Uemura, Hiroshi; Uchida, Shunsuke; Oyamada, Osamu; Oyobe, Koji.

1994-01-01

In the present invention, it is judged whether the operation state of equipments used in a plant are normal or not by using learning performances. That is, a plurality of monitoring parameters are measured for an equipment. Previously determined monitoring parameters are extracted. A leaning mode or a monitoring mode is selected. In the leaning mode, based on the values of previously determined monitoring parameters, values of other monitoring parameters during normal states are learned. In the monitoring mode, based on the values of the previously determined monitoring parameters, typical values of other leaned monitoring parameters are outputted. The typical values of other normal monitoring parameters after learning and the values of other parameters at the present time are compared. If the values of the other parameters at the present time are out of normal range, it is judged as abnormal, and the result is alarmed and displayed. (I.S.)

Selected fault testing of electronic isolation devices used in nuclear power plant operation

International Nuclear Information System (INIS)

Villaran, M.; Hillman, K.; Taylor, J.; Lara, J.; Wilhelm, W.

1994-05-01

Electronic isolation devices are used in nuclear power plants to provide electrical separation between safety and non-safety circuits and systems. Major fault testing in an earlier program indicated that some energy may pass through an isolation device when a fault at the maximum credible potential is applied in the transverse mode to its output terminals. During subsequent field qualification testing of isolators, concerns were raised that the worst case fault, that is, the maximum credible fault (MCF), may not occur with a fault at the maximum credible potential, but rather at some lower potential. The present test program investigates whether problems can arise when fault levels up to the MCF potential are applied to the output terminals of an isolator. The fault energy passed through an isolated device during a fault was measured to determine whether the levels are great enough to potentially damage or degrade performance of equipment on the input (Class 1E) side of the isolator

Safety, efficacy, and performance of implanted recycled cardiac rhythm management (CRM) devices in underprivileged patients.

Science.gov (United States)

Hasan, Reema; Ghanbari, Hamid; Feldman, Dustin; Menesses, Daniel; Rivas, Daniel; Zakhem, Nicole C; Duarte, Carlos; Machado, Christian

2011-06-01

Patients in underdeveloped nations have limited access to life-saving medical technology including cardiac rhythm management (CRM) devices. We evaluated alternative means to provide such technology to this patient population while assessing the safety and efficacy of such a practice. Patients in the United States with clinical indications for extraction of CRM devices were consented. Antemortem CRM devices were cleaned and sterilized following a protocol established at our institution. Surveillance in vitro cultures were performed for quality assurance. The functional status of pulse generators was tested with a pacing system analyzer to confirm at least 70% battery life. Most generators were transported, in person, to an implanting institution in Nicaragua. Recipients with a Class I indication for CRM implantation, and meeting economical criteria set forth, were consented for implantation of a recycled device. Between 2003 and 2009, implantation was performed in 17 patients with an average age of 42.1 ± 20.3 years. Of the 17 patients, nine were male and eight were female. Mean follow-up was 68 ± 38 months. Device evaluation occurred prior to discharge, 4 weeks post implantation, and every 6 months thereafter. There were three deaths during the follow-up period secondary to myocardial infarction, stroke, and heart failure. Hematoma formation occurred in one patient. No infections, early battery depletion, or device malfunction were identified during follow-up. Our case series is the longest follow-up of recipients of recycled antemortem CRM devices. Our findings support the feasibility and safety of this alternative acquisition of life-saving technology. ©2011, The Authors. Journal compilation ©2011 Wiley Periodicals, Inc.

Management methodology for pressure equipment

Science.gov (United States)

Bletchly, P. J.

Pressure equipment constitutes a significant investment in capital and a major proportion of potential high-risk plant in many operations and this is particularly so in an alumina refinery. In many jurisdictions pressure equipment is also subject to statutory regulation that imposes obligations on Owners of the equipment with respect to workplace safety. Most modern technical standards and industry codes of practice employ a risk-based approach to support better decision making with respect to pressure equipment. For a management system to be effective it must demonstrate that risk is being managed within acceptable limits.

In-use NOx emissions from model year 2010 and 2011 heavy-duty diesel engines equipped with aftertreatment devices.

Science.gov (United States)

Misra, Chandan; Collins, John F; Herner, Jorn D; Sax, Todd; Krishnamurthy, Mohan; Sobieralski, Wayne; Burntizki, Mark; Chernich, Don

2013-07-16

The California Air Resources Board (ARB) undertook this study to characterize the in-use emissions of model year (MY) 2010 or newer diesel engines. Emissions from four trucks: one equipped with an exhaust gas recirculation (EGR) and three equipped with EGR and a selective catalytic reduction (SCR) device were measured on two different routes with three different payloads using a portable emissions measurement system (PEMS) in the Sacramento area. Results indicated that brake-specific NOx emissions for the truck equipped only with an EGR were independent of the driving conditions. Results also showed that for typical highway driving conditions, the SCR technology is proving to be effective in controlling NOx emissions. However, under operations where the SCR's do not reach minimum operating temperature, like cold starts and some low load/slow speed driving conditions, NOx emissions are still elevated. The study indicated that strategies used to maintain exhaust temperature above a certain threshold, which are used in some of the newer SCRs, have the potential to control NOx emissions during certain low-load/slow speed driving conditions.

46 CFR 111.51-3 - Protection of vital equipment.

Science.gov (United States)

2010-10-01

...-GENERAL REQUIREMENTS Coordination of Overcurrent Protective Devices § 111.51-3 Protection of vital equipment. (a) The coordination of overcurrent protective devices must be demonstrated for all potential... 46 Shipping 4 2010-10-01 2010-10-01 false Protection of vital equipment. 111.51-3 Section 111.51-3...

An overview of equipment survivability studies at Sandia National Labs. (SNL): Chapter 3

International Nuclear Information System (INIS)

Bonzon, L.L.; Craft, C.M.; McCulloch, W.H.; Sebrell, W.A.

1983-01-01

The USNRC sponsors a number of programs at Sandia National Laboratories (SNL) specifically addressing safety-related equipment survivability. The major thrust of these programs has been the physical testing of equipment. Test results illustrate the importance of a dedicated equipment design effort giving particular attention to the safety implications of the equipment operation. Several equipment survivability tests here have revealed equipment design and test-related deficiencies

The design study of the JT-60SU device. No.8. Nuclear shielding and safety design

Energy Technology Data Exchange (ETDEWEB)

Miya, Naoyuki; Kikuchi, Mitsuru; Ushigusa, Kenkichi [Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment] [and others

1998-03-01

Results of nuclear shielding design study and safety analysis for the steady-state tokamak device JT-60SU are described. D-T operation (option) for two years is adopted in addition to ten years operation using deuterium. Design work has been done in accordance with general laws for radioisotopes handling in Japan as a guideline of safety evaluation, which is applied to the operation of present JT-60U device. Optimization of the shielding design for the device structure including vacuum vessel has been presented to meet with allowable limits of biological shielding determined in advance. It is shown that JT-60SU can be operated safely in the present JT-60 experimental building. It is planed to use 100g/year of tritium in D-T operation phase. A concept of multiple -barrier system is applied to the facility design to prevent propagation of tritium, in which the torus hall and the tritium removal room provide the tertiary confinement. From the design of atmosphere detritiation system for accidental tritium release, it is shown that tritium concentration level can be reduced to the allowable level after two weeks with reasonable compact size components. Safety assessment related to activation of coolant/air, and atmospheric tritium effluents are discussed. (author)

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...

The safety of non-incineration waste disposal devices in four hospitals of Tehran.

Science.gov (United States)

Farshad, Aliasghar; Gholami, Hamid; Farzadkia, Mahdi; Mirkazemi, Roksana; Kermani, Majid

2014-01-01

The safe management of hospital waste is a challenge in many developing countries. The aim of this study was to compare volatile organic compounds (VOCs) emissions and the microbial disinfectant safety in non-incineration waste disposal devices. VOC emissions and microbial infections were measured in four non-incineration waste disposal devices including: autoclave with and without a shredder, dry heat system, and hydroclave. Using NIOSH and US EPA-TO14 guidelines, the concentration and potential risk of VOCs in emitted gases from four devices were assessed. ProSpore2 biological indicators were used to assess the microbial analysis of waste residue. There was a significant difference in the type and concentration of VOCs and microbial infection of residues in the four devices. Emissions from the autoclave with a shredder had the highest concentration of benzene, ethyl benzene, xylene, and BTEX, and emissions from the hydroclave had the highest concentration of toluene. The highest level of microbial infection was observed in the residues of the autoclave without a shredder. There is an increased need for proper regulation and control of non-incinerator devices and for monitoring and proper handling of these devices in developing countries.

A collision model for safety evaluation of autonomous intelligent cruise control.

Science.gov (United States)

Touran, A; Brackstone, M A; McDonald, M

1999-09-01

This paper describes a general framework for safety evaluation of autonomous intelligent cruise control in rear-end collisions. Using data and specifications from prototype devices, two collision models are developed. One model considers a train of four cars, one of which is equipped with autonomous intelligent cruise control. This model considers the car in front and two cars following the equipped car. In the second model, none of the cars is equipped with the device. Each model can predict the possibility of rear-end collision between cars under various conditions by calculating the remaining distance between cars after the front car brakes. Comparing the two collision models allows one to evaluate the effectiveness of autonomous intelligent cruise control in preventing collisions. The models are then subjected to Monte Carlo simulation to calculate the probability of collision. Based on crash probabilities, an expected value is calculated for the number of cars involved in any collision. It is found that given the model assumptions, while equipping a car with autonomous intelligent cruise control can significantly reduce the probability of the collision with the car ahead, it may adversely affect the situation for the following cars.

Use of Active-Play Video Games to Enhance Aerobic Fitness in Schizophrenia: Feasibility, Safety, and Adherence.

Science.gov (United States)

Kimhy, David; Khan, Samira; Ayanrouh, Lindsey; Chang, Rachel W; Hansen, Marie C; Lister, Amanda; Ballon, Jacob S; Vakhrusheva, Julia; Armstrong, Hilary F; Bartels, Matthew N; Sloan, Richard P

2016-02-01

Active-play video games have been used to enhance aerobic fitness in various clinical populations, but their use among individuals with schizophrenia has been limited. Feasibility, acceptability, safety, and adherence data were obtained for use of aerobic exercise (AE) equipment by 16 individuals with schizophrenia during a 12-week AE program consisting of three one-hour exercise sessions per week. Equipment included exercise video games for Xbox 360 with Kinect motion sensing devices and traditional exercise equipment. Most participants (81%) completed the training, attending an average of 79% of sessions. The proportion of time spent playing Xbox (39%) exceeded time spent on any other type of equipment. When using Xbox, participants played 2.24±1.59 games per session and reported high acceptability and enjoyment ratings, with no adverse events. Measures of feasibility, acceptability, adherence, and safety support the integration of active-play video games into AE training for people with schizophrenia.

Cryogenic Safety Rules and Guidelines at CERN

CERN Multimedia

CERN. Geneva

2016-01-01

CERN defines and implements a Safety Policy that sets out the general principles governing safety at CERN. As an intergovernmental organisation, CERN further establishes its own Safety Rules as necessary for its proper functioning. In this process, it takes into account the laws and regulation of the Host States (France and Switzerland), EU regulations and directives, as well as international regulations, standards and directives. For the safety of cryogenic equipment, this is primarily covered by the Safety Regulation for Mechanical Equipment and the General Safety Instruction for Cryogenic Equipment. In addition, CERN has also developed Safety Guidelines to support the implementation of these safety rules, covering cryogenic equipment and oxygen deficiency hazard assessment and mitigation. An overview of the cryogenic safety rules and these safety guidelines will be presented.

Dukovany nuclear power plant safety

International Nuclear Information System (INIS)

1999-01-01

Presentation covers recommended safety issues for the Dukovany NPP which have been solved with satisfactory conclusions. Safety issues concerned include: radiation safety; nuclear safety; security; emergency preparedness; health protection at work; fire protection; environmental protection; chemical safety; technical safety. Quality assurance programs at all stages on NPP life time is described. Report includes description of NPP staff training provision, training simulator, emergency operating procedures, emergency preparedness, Year 2000 problem, inspections and life time management. Description of Dukovany Plant Safety Analysis Projects including integrity of the equipment, modernisation, equipment innovation and safety upgrading program show that this approach corresponds to the actual practice applied in EU countries, and fulfilment of current IAEA requirements for safety enhancement of the WWER 440/213 units in the course of MORAWA Equipment Upgrading program

[Equipment design for magnetic therapy and "Polus" devices].

Science.gov (United States)

Viktorov, V A; Malkov, Iu V

1994-01-01

Low-frequency magnetotherapy is among the most original therapeutical techniques since it is effective in treating most diseases and has practically no contraindications. Due to atraumaticity of a low-frequency electromagnetic field, the application of magnetotherapy is indicated in geriatric care, in particular. The VNIIMP-VITA Joint-Stock Company has developed a family of the Polyus system equipment for magnetotherapy, whereby all the well-known therapeutical procedures of low-frequency magnetotherapy can be performed. The magnetotherapeutic room equipped with Polyus-2D, Polyus-3, and Polyus-4 ensures a complete set of magneto-therapeutical exposure. The rooms are supplied by the VNIIMP-VITA Joint-Stock Company.

Complementary Safety Assessments: technical and organisational proposals from Areva

International Nuclear Information System (INIS)

Anon.

2012-01-01

The safety experts of the Areva group have worked on the definition of a hard core of safety measures necessary to assure the vital functions in any situation (event the most unlikely) of the following nuclear facilities: La Hague, Tricastin, Melox, and FBFC Romans. Areva proposes to reinforce its crisis management by deploying new equipment for the intervention and communication (pumps, robots, diesel sets, measuring devices, satellite phone...). More than 1500 people with training and skills related to nuclear crisis will be able to help local teams on nuclear facilities if necessary. Areva has announced that it will invest more than 2 billion euros for upgrading the industrial plants, the implementation of new technologies and the improvement of safety. (A.C.)

Chemistry laboratory safety manual available

Science.gov (United States)

Elsbrock, R. G.

1968-01-01

Chemistry laboratory safety manual outlines safe practices for handling hazardous chemicals and chemistry laboratory equipment. Included are discussions of chemical hazards relating to fire, health, explosion, safety equipment and procedures for certain laboratory techniques and manipulations involving glassware, vacuum equipment, acids, bases, and volatile solvents.

Some questions of monitoring on nuclear installations and quality of safety assessments

International Nuclear Information System (INIS)

Labazov, V.

1998-01-01

The paper is prepared on the basis of assessment performed by the State Scientific and Technical Centre on Nuclear and Radiation safety which deals with scientific and technical support of the Regulatory Authorities of Ukraine concerning integrity of pressurised elements in the NPP. A number of acute issues on control equipment could be distinguished: placement of sensors should provide adequate information on the data under control necessary for safety analysis; properties of instrumentation should provide trustworthy information about measured values; accurate recommendations should be imposed to operating organisations for performing special analyses for control devices

Development of nuclear equipment qualification technology

Energy Technology Data Exchange (ETDEWEB)

Choi, Heon O; Kim, Wu Hyun; Kim, Jin Wuk; Kim, Jeong Hyun; Lee, Jeong Kyu; Kim, Yong Han; Jeong, Hang Keun [Korea Institute of Machinery and Materials, Taejon (Korea)

1999-03-01

In order to enhance testing and evaluation technologies, which is one of the main works of the Chanwon branch of KIMM(Korea Institute of Machinery and Materials), in addition to the present work scope of the testing and evaluation in the industrial facilities such as petroleum and chemical, plants, the qualification technologies of the equipments important to safety used in the key industrial facilities such as nuclear power plants should be localized: Equipments for testing and evaluation is to be set up and the related technologies must be developed. In the first year of this study, of vibration aging qualification technologies of equipments important to safety used in nuclear power plants have been performed. (author). 27 refs., 81 figs., 17 tabs.

Plant equipment integrity monitoring and diagnosing method and device therefor, plant equipment maintenance and inspection time determining method and device therefor, as well as nuclear power plant

International Nuclear Information System (INIS)

Kato, Takahiko; Ando, Masashi; Osumi, Katsumi; Horiuchi, Tetsuo; Asakura, Yamato; Akamine, Kazuhiko.

1995-01-01

The present invention can accurately forecast a time for occurrence of troubles of plant equipments in contact with recycling water, to conduct its maintenance and inspection before occurrence of the troubles. Namely, change of water quality in plant equipments caused by corrosion of recycling water occurred in constitutional parts of the plant equipments is measured. The time upon occurrence of the troubles of the plant equipments to corrosion of the recycling water is forecast based on the measured value. A time till the occurrence of the change of water quality after starting the use of the plant equipments is calculated based on the measured value. The calculated time is compared with a correlation between the time of occurrence of the troubles after starting the use of the plant equipments and the time of occurrence of change of the water quality, to forecast the time of occurrence of the troubles. Preferably, electroconductivity and pH of recycling water in the inside or at the exit of the plant equipments are measured as an object for the measurement of change of water quality. (I.S.)

Electrodermal Activity Based Wearable Device for Drowsy Drivers

Science.gov (United States)

Malathi, D.; Dorathi Jayaseeli, JD; Madhuri, S.; Senthilkumar, K.

2018-04-01

Road safety and road accident mortality rate are a serious concern for the government. With rise in fatal road accidents, who’s leading cause is the driver being drowsy behind the wheel, measures to alleviate this problem becomes the prime task. To meet the purpose, methods adopted must be of minimum discomfort for the driver, easy to install, provide good detection accuracy and timely alert to circumvent a probable accident. A good candidate to meet these specifications is EDA. As it detects the level of sweat which directly corresponds to the mental state of the person, using EDA for the purposes of driver safety forms a good option. The novelty of this project lies in making use of EDA as a measure to detect if a person is drowsy or not. Much of the challenge lies in building a device equipped with the necessary sensors and processing the data on real-time. The novelty of this work lies in development of an embedded device interfaced with sensors and actuators to detect and alert a driver when found drowsy using sweat as a parameter.

Prevention of Medical Device-Related Pressure Injuries Associated With Respiratory Equipment Use in a Critical Care Unit: A Quality Improvement Project.

Science.gov (United States)

Padula, Cynthia A; Paradis, Heidi; Goodwin, Robert; Lynch, Judith; Hegerich-Bartula, Deborah

Medical devices have been identified as an extrinsic risk factor for development of pressure injuries, with as many as 30% to 70% of medical device-related pressure injuries resulting from respiratory equipment. This article describes a quality improvement project undertaken to reduce the occurrence of respiratory device-related pressure injuries in a critically care unit. Multiple actions were implemented to achieve this goal. Respiratory therapists were trained to document occurrences on a daily basis, and apparent cause analyses were conducted on each occurrence. An interdisciplinary team conducted biweekly rounds on patients with respiratory devices and consulted other professionals as indicated. Nurses and respiratory therapists attended an evidence-based, collaborative, educational offering and completed a measure of team functioning before the program and at the end of the study period. The occurrence rates of respiratory device-related pressure injuries were reduced over the project period, and these changes were sustained over the subsequent 12 months.

Safety motion increase of trains by improvement diagnostics process devices of railway automation

Directory of Open Access Journals (Sweden)

B.M.Bondarenko

2012-12-01

Full Text Available The complex use of methods of nondestructive check for the automated diagnostics electromagnetic relays of railway automation the first class reliability is offered. The methods determination of their mechanical parameters are resulted, that allows to exclude a human factor from the control, promote reliability of devices railway automation and safety motion of railway transport.

Developing equipment for AGR remote visual inspection

International Nuclear Information System (INIS)

James, P.W.; Walton, P.J.

1985-01-01

The Remote Inspection Group is part of the CEGB's Generation Development and Construction Division, and has responsibility for the design, development, procurement, testing and setting to work of the equipment provided to carry out routine remote visual inspections of its AGRs. This equipment includes both the viewing devices and the necessary placement equipment. (author)

Design and fabrication of equipment and devices for a Radiotherapy department; Diseno y fabricacion de equipos y aditamentos para un departamento de Radioterapia

Energy Technology Data Exchange (ETDEWEB)

Picon, C.L.; Zaharia B, M. [Departamento de Radioterapia. Instituto de Enfermedades Neoplasicas, Av. Angamos Este 2520, Lima (Peru)

1998-12-31

The objective of this work is to present the possibility to design and construct utilizing local technology, a series of equipment and devices necessaries for a routine in a Radiotherapy Department with typical budget in the Latin-American hospitals. (Author)

33 CFR 142.24 - Use of equipment.

Science.gov (United States)

2010-07-01

... CONTINENTAL SHELF ACTIVITIES WORKPLACE SAFETY AND HEALTH Personal Protective Equipment § 142.24 Use of equipment. (a) Each holder of a lease or permit issued under the Act shall ensure that all personnel who are required by this subpart to use or wear personal protective equipment do so when within the lease area or...

14 CFR 27.1413 - Safety belts.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Safety belts. 27.1413 Section 27.1413 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF TRANSPORTATION AIRCRAFT AIRWORTHINESS STANDARDS: NORMAL CATEGORY ROTORCRAFT Equipment Safety Equipment § 27.1413 Safety belts. Each safety belt...

Human factors evaluation of man-machine interface for periodic safety review of nuclear power plants

International Nuclear Information System (INIS)

Lee, Yong Hee; Lee, Jung Woon; Park, Jae Chang; Hwang, In Koo; Lee, Hyun Cheol; Jang, Tong Il; Ku, Jin Young; Kim, Soo Jin

2004-12-01

This report describes the research results of human factors assessment on the MMI(Man Machine Interface) equipment as part of Periodic Safety Review(PSR) of Nuclear Power Plants(NPPs). As MMI is a key factor among human factors to be reviewed in PSR, we reviewed the MMI components of nuclear power plants in aspect of human factors engineering. The availability, suitability, and effectiveness of the MMI devices were chosen to be reviewed. The MMI devices were investigated through the review of design documents related to the MMI, survey of control panels, evaluation of experts, and experimental assessment. Checklists were used to perform this assessment and record the review results. The items mentioned by the expert comments to review in detail in relation with task procedures were tested by experiments with operators' participation. For some questionable issues arisen during this MMI review, operator workload and possibility of errors in operator actions were analysed. The reviewed MMI devices contain MCR(Main Control Room), SPDS(Safety Parameter Display System), RSP(Remote Shutdown Panel), and the selected LCBs(Local Control Boards) importantly related to safety. As results of the assessments, any significant problem challenging the safety was not found on human factors in the MMI devices. However, several small items to be changed and improved in suitability of MMI devices were discovered. An action plan is recommended to accommodate the suggestions and review comments. It will enhance the plant safety on MMI area

30 CFR 57.12027 - Grounding mobile equipment.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Grounding mobile equipment. 57.12027 Section 57.12027 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR METAL AND NONMETAL MINE SAFETY AND HEALTH SAFETY AND HEALTH STANDARDS-UNDERGROUND METAL AND NONMETAL MINES Electricity...

Sodium cleaning device for nuclear reactor equipments

International Nuclear Information System (INIS)

Fujisawa, Morio.

1985-01-01

Purpose: To enable sodium cleaning over the entire length of large size equipments such as control rod drives and primary coolant recycling pumps for use in FBR type reactors. Constitution: A plurality of warm water supply nozzles each having a valve are connected at varying height on the side of a cleaning tank, to which an exhaust line is connected. These nozzles are connected with an exhaust port at the bottom of the tank to constitute a pipeway for cleaning warm water recycling line including a water feed pump and a feedwater heater. The water level in the tank is changed stepwise by successively selecting the warm water feed nozzles. Further, the warm water in the tank is recyclically fed through the nozzles selected at each step of the water level through the recycle line while warming. On the other hand, the pressure inside the tank is reduced through the exhaust line, whereby the warm water in the tank is boiled at low temperature to clean-up sodium on the equipments to be cleaned over the entire length. (Horiuchi, T.)

Market Potential for Residential Biomass Heating Equipment: Stochastic and Econometric Assessments

OpenAIRE

Adee Athiyaman

2015-01-01

This paper provides estimates of market potential for biomass-residential-heating equipment in the US: that is, the greatest amount of biomass-residential-heating equipment that can be sold by the industry. The author's analysis is limited to biomass equipment used most to heat the housing unit. Assuming that households equipped with 10+ year old primary heating devices will replace rather than repair the devices he predicts that approximately 1.4 million units of residential home heating equ...

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)

Methodology of assessment of the impact on the risk of changes in peak times of unavailability of safety equipment integrating treatment and analysis of uncertainties

International Nuclear Information System (INIS)

Martorell, S.; Villamizar, M.; Marton, I.; Villanueva, J. f.; Carlos, S.; Sanchez, A. I.

2013-01-01

Surveillance of safety equipment requirements form parts of the technical specifications of Performance included in the bases of operation of nuclear power plants license, so they are center of attention in the study of improvements to the safety of the operation of the plant using different methods, both traditional deterministic as probabilistic.

The safety of non-incineration waste disposal devices in four hospitals of Tehran

Science.gov (United States)

Farshad, Aliasghar; Gholami, Hamid; Farzadkia, Mahdi; Mirkazemi, Roksana; Kermani, Majid

2014-01-01

Background: The safe management of hospital waste is a challenge in many developing countries. Objectives: The aim of this study was to compare volatile organic compounds (VOCs) emissions and the microbial disinfectant safety in non-incineration waste disposal devices. Methods: VOC emissions and microbial infections were measured in four non-incineration waste disposal devices including: autoclave with and without a shredder, dry heat system, and hydroclave. Using NIOSH and US EPA-TO14 guidelines, the concentration and potential risk of VOCs in emitted gases from four devices were assessed. ProSpore2 biological indicators were used to assess the microbial analysis of waste residue. Results: There was a significant difference in the type and concentration of VOCs and microbial infection of residues in the four devices. Emissions from the autoclave with a shredder had the highest concentration of benzene, ethyl benzene, xylene, and BTEX, and emissions from the hydroclave had the highest concentration of toluene. The highest level of microbial infection was observed in the residues of the autoclave without a shredder. Conclusions: There is an increased need for proper regulation and control of non-incinerator devices and for monitoring and proper handling of these devices in developing countries. PMID:25000113

30 CFR 56.12027 - Grounding mobile equipment.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Grounding mobile equipment. 56.12027 Section 56.12027 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR METAL AND NONMETAL MINE SAFETY AND HEALTH SAFETY AND HEALTH STANDARDS-SURFACE METAL AND NONMETAL MINES Electricity § 56...

The application of GIS equipment in nuclear power plant

International Nuclear Information System (INIS)

Ji Lin; Huang Pengbo; Chang Xin'ai

2012-01-01

In this paper, the advantage and disadvantage of gas insulated switchgear (GIS) in environmental adaptability, operation safety and economic benefit are analyzed. Issues concerning the manufacture, transportation, on-site installation, operation, maintenance and extension of GIS equipment are discussed. Comparing those characteristics with air insulated switchgear (AIS), GIS is characterized by better aseismic ability, less occupied area and installation process, lower fault rate, longer maintenance period, easier for extension and higher economic benefit, SF6 gas insures the operation safety and reliability of GIS equipment, modular transport and re-assembling improves the installation flexibility. Therefore, GIS equipment may be the first choice for the primary equipment of nuclear power plant. (authors)

RESUME95 Nordic field test of mobile equipment for nuclear fall-out monitoring

Energy Technology Data Exchange (ETDEWEB)

Bourgeois, C.; Bresson, J.; Chiffot, T.; Guillot, L. [Centre d`Etudes de Valduc, Direction des Applications Militaires, Commissaiat a L`Energie Atomique, Tille (France)

1997-12-31

Nordic Safety Research (NKS) organised in August 1995 a field test of various techniques and instrumentation for monitoring radioactive fall-out. In an emergency situation, after a major release of radioactive material, many different measuring systems are going to be used, ranging from small hand hold intensitometer to complex spectrometer systems. In this test the following type of equipment were tested: Airborne spectrometers; Carborne spectrometers and dose rate meters; In situ spectrometers and intensitometers. Helinuc team was equipped of an airborne system and of a germanium device for in situ measurements. Different tasks were specified for each team: Mapping caesium fall-out and natural activity over two areas of 18 and 5 km{sup 2}; Research of hidden sources. For measurements and data processing the respect of time allowed was strictly controlled for testing the ability of each team. (au).

RESUME95 Nordic field test of mobile equipment for nuclear fall-out monitoring

Energy Technology Data Exchange (ETDEWEB)

Bourgeois, C; Bresson, J; Chiffot, T; Guillot, L [Centre d` Etudes de Valduc, Direction des Applications Militaires, Commissaiat a L` Energie Atomique, Tille (France)

1998-12-31

Nordic Safety Research (NKS) organised in August 1995 a field test of various techniques and instrumentation for monitoring radioactive fall-out. In an emergency situation, after a major release of radioactive material, many different measuring systems are going to be used, ranging from small hand hold intensitometer to complex spectrometer systems. In this test the following type of equipment were tested: Airborne spectrometers; Carborne spectrometers and dose rate meters; In situ spectrometers and intensitometers. Helinuc team was equipped of an airborne system and of a germanium device for in situ measurements. Different tasks were specified for each team: Mapping caesium fall-out and natural activity over two areas of 18 and 5 km{sup 2}; Research of hidden sources. For measurements and data processing the respect of time allowed was strictly controlled for testing the ability of each team. (au).

Environmental, safety, and health engineering

International Nuclear Information System (INIS)

Woodside, G.; Kocurek, D.

1997-01-01

A complete guide to environmental, safety, and health engineering, including an overview of EPA and OSHA regulations; principles of environmental engineering, including pollution prevention, waste and wastewater treatment and disposal, environmental statistics, air emissions and abatement engineering, and hazardous waste storage and containment; principles of safety engineering, including safety management, equipment safety, fire and life safety, process and system safety, confined space safety, and construction safety; and principles of industrial hygiene/occupational health engineering including chemical hazard assessment, personal protective equipment, industrial ventilation, ionizing and nonionizing radiation, noise, and ergonomics

New neutron and gamma dosimetry equipment at the RB reactor; Nova merna neutronska i gama dozimetrijska oprema na reaktoru RB

Energy Technology Data Exchange (ETDEWEB)

Pesic, M; Stefanovic, D; Jevremovic, M; Petronijevic, M; Vranic, S; Ilic, I [Boris Kidric Institute of Nuclear Sciences Vinca, Beograd (Yugoslavia)

1992-07-15

In the frame of bilateral cooperation between Germany and Yugoslavia, complete control, safety and dosimetry equipment of the shut-down SNEAK reactor was donated to Vinca Institute and transported to be installed at the RB reactor. This report contains detailed description of instrumentation components including detectors, electronic components and electronic circuits. Experimental data which verified correct functioning of the installed devices are part of this document. The objective of the RB reactor staff is to achieve new safety and dosimetry system in order to improve the reliability and availability of the RB reactor for future experiments.

Prototype equipment status monitor for plant operational configuration management

International Nuclear Information System (INIS)

DeVerno, M.; Trask, D.; Groom, S.

1998-01-01

CANDU plants, such as the Point Lepreau GS, have tens of thousands of operable devices. The status of each operable device must be immediately available to plan and execute future changes to the plant. Historically, changes to the plant's operational configuration have been controlled using manual and administrative methods where the status of each operable device is maintained on operational flowsheets located in the work control area of the main control room. The operational flowsheets are used to plan and develop Operating Orders (OOs) or Order-to-Operate (OTOs) and the control centre work processes are used to manage their execution. After performing each OO procedure, the operational flowsheets are updated to reflect the new plant configuration. This process can be very time consuming, and due to the manual processes, can lead to the potential for time lags and errors in the recording of the current plant configuration. Through a cooperative research and development program, Canadian CANDU utilities and Atomic Energy of Canada Limited, the design organization, have applied modern information technologies to develop a prototype Equipment Status Monitor (ESM) to address processes and information flow for efficient operational configuration management. The ESM integrates electronic operational flowsheets, equipment databases, engineering and work management systems, and computerized procedures to assess, plan, execute, track, and record changes to the plant's operational configuration. This directly leads to improved change control, more timely and accurate plant status information, fewer errors, and better decision making regarding future changes. These improvements to managing the plant's operational configuration are essential to increasing plant safety, achieving a high plant availability, and maintaining high capability and capacity factors. (author)

Interventional suite and equipment management: cradle to grave

Energy Technology Data Exchange (ETDEWEB)

Strauss, Keith J. [Harvard Medical School, Radiology Physics and Engineering, Children' s Hospital Boston, Boston, MA (United States)

2006-09-15

The acquisition process for interventional equipment and the care that this equipment receives constitute a comprehensive quality improvement program. This program strives to (a) achieve the production of good image quality that meets clinical needs, (b) reduce radiation doses to the patient and personnel to their lowest possible levels, and (c) provide overall good patient care at reduced cost. Interventional imaging equipment is only as effective and efficient as its supporting facility. The acquisition process of interventional equipment and the development of its environment demand a clinical project leader who can effectively coordinate the efforts of the many professionals who must communicate and work effectively on this type of project. The clinical project leader needs to understand (a) clinical needs of the end users, (b) how to justify the cost of the project, (c) the technical needs of the imaging and all associated equipment, (d) building and construction limitations, (e) how to effectively read construction drawings, and (f) how to negotiate and contract the imaging equipment from the appropriate vendor. After the initial commissioning of the equipment, it must not be forgotten. The capabilities designed into the imaging device can be properly utilized only by well-trained operators and staff who were initially properly trained and receive ongoing training concerning the latest clinical techniques throughout the equipment's lifetime. A comprehensive, ongoing maintenance and repair program is paramount to reducing costly downtime of the imaging device. A planned periodic maintenance program can identify and eliminate problems with the imaging device before these problems negatively impact patient care. (orig.)

Interventional suite and equipment management: cradle to grave

International Nuclear Information System (INIS)

Strauss, Keith J.

2006-01-01

The acquisition process for interventional equipment and the care that this equipment receives constitute a comprehensive quality improvement program. This program strives to (a) achieve the production of good image quality that meets clinical needs, (b) reduce radiation doses to the patient and personnel to their lowest possible levels, and (c) provide overall good patient care at reduced cost. Interventional imaging equipment is only as effective and efficient as its supporting facility. The acquisition process of interventional equipment and the development of its environment demand a clinical project leader who can effectively coordinate the efforts of the many professionals who must communicate and work effectively on this type of project. The clinical project leader needs to understand (a) clinical needs of the end users, (b) how to justify the cost of the project, (c) the technical needs of the imaging and all associated equipment, (d) building and construction limitations, (e) how to effectively read construction drawings, and (f) how to negotiate and contract the imaging equipment from the appropriate vendor. After the initial commissioning of the equipment, it must not be forgotten. The capabilities designed into the imaging device can be properly utilized only by well-trained operators and staff who were initially properly trained and receive ongoing training concerning the latest clinical techniques throughout the equipment's lifetime. A comprehensive, ongoing maintenance and repair program is paramount to reducing costly downtime of the imaging device. A planned periodic maintenance program can identify and eliminate problems with the imaging device before these problems negatively impact patient care. (orig.)

Criticality safety evaluation in Tokai Reprocessing Plant

International Nuclear Information System (INIS)

Shirai, Nobutoshi; Nakajima, Masayoshi; Takaya, Akikazu; Ohnuma, Hideyuki; Shirouzu, Hidetomo; Hayashi, Shinichiro; Yoshikawa, Koji; Suto, Toshiyuki

2000-04-01

Criticality limits for equipments in Tokai Reprocessing Plant which handle fissile material solution and are under shape and dimension control were reevaluated based on the guideline No.10 'Criticality safety of single unit' in the regulatory guide for reprocessing plant safety. This report presents criticality safety evaluation of each equipment as single unit. Criticality safety of multiple units in a cell or a room was also evaluated. The evaluated equipments were ones in dissolution, separation, purification, denitration, Pu product storage, and Pu conversion processes. As a result, it was reconfirmed that the equipments were safe enough from a view point of criticality safety of single unit and multiple units. (author)

29 CFR 1918.106 - Payment for protective equipment.

Science.gov (United States)

2010-07-01

... pay for non-specialty safety-toe protective footwear (including steel-toe shoes or steel-toe boots... Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR (CONTINUED) SAFETY AND HEALTH REGULATIONS FOR LONGSHORING Personal Protective Equipment...

Vibration aging of diesel-engine mounted electrical equipment

International Nuclear Information System (INIS)

Lee, B.J.; Morton, W.C.

1994-01-01

The Emergency Diesel Generator (EDG) in a Nuclear Power Plant is considered to be a component which is essential to safe plant operation. Failures of auxiliary equipment directly mounted on the EDG creates costly repairs, and compromises the engine's availability and reliability. Although IEEE-323 requires addressing of safety-related components due to mechanically induced vibration, very few guidelines exist in the nuclear industry to show how this may be accounted for. Most engine vendors rely on the empirical experience data as the basis of their evaluation for vibration. Upgrade of engine controls, addition of monitoring devices and other engine modifications require design and installation of new equipment to be mounted directly on the engine. This necessitates the evaluation for engine-induced vibration which is considered to be one of the most severe design parameters. This paper discusses the engine vibration characteristics, and the acquisition of extensive field vibration data on the diesel engine under operating conditions. The data is then used to develop life cycle vibration qualification test profiles that can be applied with confidence in a laboratory environment to qualify engine-mounted equipment. The intent is to validate a product's ability to survive under worst case, extended service on-engine conditions. This paper describes the procedures and approaches used to achieve those goals, and provides developed profile examples and test results

Electrical apparatus lockout device

Energy Technology Data Exchange (ETDEWEB)

Gonzales, R.

1999-10-12

A simple lockout device for electrical equipment equipped with recessed power blades is described. The device comprises a face-plate (12) having a threaded member (14) attached thereto and apertures suitable for accommodating the power blades of a piece of electrical equipment, an elastomeric nose (16) abutting the face-plate having a hole for passage of the threaded member therethrough and power blade apertures in registration with those of the face-plate, a block (20) having a recess (34) in its forward face for receiving at least a portion of the hose, a hole therein for receiving the threaded member and an integral extension (26) extending from its rear face. A thumb screw (22) suitable for turning with the hands and having internal threads suitable for engaging the threaded member attached to the face-plate is inserted into a passage in the integral extension to engage the threaded member in such a fashion that when the device is inserted over the recessed power blades of a piece of electrical equipment and the thumb screw (22) tightened, the elastomeric nose (16) is compressed between the face-plate (12) and the block (20) forcing it to expand laterally thereby securing the device in the recess and precluding the accidental or intentional energization of the piece of equipment by attachment of a power cord to the recessed power blades. Means are provided in the interval extension and the thumb screw for the attachment of a locking device (46) which will satisfy OSHA standards.

Electrical apparatus lockout device

International Nuclear Information System (INIS)

Gonzales, R.

1999-01-01

A simple lockout device for electrical equipment equipped with recessed power blades is described. The device comprises a face-plate (12) having a threaded member (14) attached thereto and apertures suitable for accommodating the power blades of a piece of electrical equipment, an elastomeric nose (16) abutting the face-plate having a hole for passage of the threaded member therethrough and power blade apertures in registration with those of the face-plate, a block (20) having a recess (34) in its forward face for receiving at least a portion of the hose, a hole therein for receiving the threaded member and an integral extension (26) extending from its rear face. A thumb screw (22) suitable for turning with the hands and having internal threads suitable for engaging the threaded member attached to the face-plate is inserted into a passage in the integral extension to engage the threaded member in such a fashion that when the device is inserted over the recessed power blades of a piece of electrical equipment and the thumb screw (22) tightened, the elastomeric nose (16) is compressed between the face-plate (12) and the block (20) forcing it to expand laterally thereby securing the device in the recess and precluding the accidental or intentional energization of the piece of equipment by attachment of a power cord to the recessed power blades. Means are provided in the interval extension and the thumb screw for the attachment of a locking device (46) which will satisfy OSHA standards

Equipment nonconformance and degradation: Promptly determining operability and establishing corrective action plans

International Nuclear Information System (INIS)

Hoxie, C.L.; Cotton, K.R.; Emch, R.L. Jr.

1992-01-01

Nine principles for dealing with degraded and nonconforming equipment are presented and some examples are discussed. The distinction between equipment operability (i.e., capability to perform the safety function) and equipment qualification (conformance to all aspects of the current licensing basis, including codes and standards, design criteria, and commitments) is discussed. The concept of finding reasonable assurance of safety for continued plant operation for equipment not covered by technical specifications is also presented. Degraded or nonconforming equipment must be evaluated for its safety impact and for operability. In all cases, degraded or nonconforming conditions must ultimately be resolved, either through prompt corrective action or through some process of showing that the changed state of the plant is acceptable for continued operation, based on 10 CFR 50.59

Research, Calculation for Designing the Technological Equipment Line of Cementation with 3,000 Tonnes of Solid Waste/Year Capacity for ZOC Plan

International Nuclear Information System (INIS)

Tran Van Hoa; Ngo Van Tuyen; Nguyen Ba Tien; Le Ba Thuan; Phung Quoc Khanh; Mai Duc Lanh; Vuong Huu Anh; Luu Cao Nguyen; Duong Dinh Tho; Phung Vu Phong; Nguyen An Thai; Pham Quang Minh

2013-01-01

Technological process and equipment line for cementation with 3,000 tons of solid wastes/year capacity for ZOC plant was studied according to the quantity, the composition and the property of solid wastes from ZOC plant. The influence of several parameters with cementation process such as cement mixing ratio, size, moisture and NaCl content in residue, which affected to mechanical and chemical strength of waste block after cementation was evaluated. The calculation and designing for cementation equipment line were thus conducted and total investment cost of construction and installation as well as operation of this equipment line was also estimated. Radiation safety and environmental protection for waste treatment facility was calculated and the design on radiation safety and environmental protection for equipment line was proposed. Technological process and design document of this production line seemed to be reasonable because it is consistent with properties of wastes as well as it has been commonly used in the world to stabilize solid residues in nuclear industry. The advantages of this propose were simple structure of the devices, locally made, easy operation, locally available and inexpensive materials resulting in low cost of investment and operation. (author)

SRV-automatic handling device

International Nuclear Information System (INIS)

Yamada, Koji

1987-01-01

Automatic handling device for the steam relief valves (SRV's) is developed in order to achieve a decrease in exposure of workers, increase in availability factor, improvement in reliability, improvement in safety of operation, and labor saving. A survey is made during a periodical inspection to examine the actual SVR handling operation. An SRV automatic handling device consists of four components: conveyor, armed conveyor, lifting machine, and control/monitoring system. The conveyor is so designed that the existing I-rail installed in the containment vessel can be used without any modification. This is employed for conveying an SRV along the rail. The armed conveyor, designed for a box rail, is used for an SRV installed away from the rail. By using the lifting machine, an SRV installed away from the I-rail is brought to a spot just below the rail so that the SRV can be transferred by the conveyor. The control/monitoring system consists of a control computer, operation panel, TV monitor and annunciator. The SRV handling device is operated by remote control from a control room. A trial equipment is constructed and performance/function testing is carried out using actual SRV's. As a result, is it shown that the SRV handling device requires only two operators to serve satisfactorily. The required time for removal and replacement of one SRV is about 10 minutes. (Nogami, K.)

Load Bearing Equipment for Bone and Muscle

Science.gov (United States)

Shackelford, Linda; Griffith, Bryan

2015-01-01

Resistance exercise on ISS has proven effective in maintaining bone mineral density and muscle mass. Exploration missions require exercise with similar high loads using equipment with less mass and volume and greater safety and reliability than resistance exercise equipment used on ISS (iRED, ARED, FWED). Load Bearing Equipment (LBE) uses each exercising person to create and control the load to the partner.