Probabilistic safety analysis procedures guide

International Nuclear Information System (INIS)

Papazoglou, I.A.; Bari, R.A.; Buslik, A.J.

1984-01-01

A procedures guide for the performance of probabilistic safety assessment has been prepared for interim use in the Nuclear Regulatory Commission programs. The probabilistic safety assessment studies performed are intended to produce probabilistic predictive models that can be used and extended by the utilities and by NRC to sharpen the focus of inquiries into a range of tissues affecting reactor safety. This guide addresses the determination of the probability (per year) of core damage resulting from accident initiators internal to the plant and from loss of offsite electric power. The scope includes analyses of problem-solving (cognitive) human errors, a determination of importance of the various core damage accident sequences, and an explicit treatment and display of uncertainties for the key accident sequences. Ultimately, the guide will be augmented to include the plant-specific analysis of in-plant processes (i.e., containment performance) and the risk associated with external accident initiators, as consensus is developed regarding suitable methodologies in these areas. This guide provides the structure of a probabilistic safety study to be performed, and indicates what products of the study are essential for regulatory decision making. Methodology is treated in the guide only to the extent necessary to indicate the range of methods which is acceptable; ample reference is given to alternative methodologies which may be utilized in the performance of the study

Evaluating North Carolina Food Pantry Food Safety-Related Operating Procedures.

Science.gov (United States)

Chaifetz, Ashley; Chapman, Benjamin

2015-11-01

Almost one in seven American households were food insecure in 2012, experiencing difficulty in providing enough food for all family members due to a lack of resources. Food pantries assist a food-insecure population through emergency food provision, but there is a paucity of information on the food safety-related operating procedures used in the pantries. Food pantries operate in a variable regulatory landscape; in some jurisdictions, they are treated equivalent to restaurants, while in others, they operate outside of inspection regimes. By using a mixed methods approach to catalog the standard operating procedures related to food in 105 food pantries from 12 North Carolina counties, we evaluated their potential impact on food safety. Data collected through interviews with pantry managers were supplemented with observed food safety practices scored against a modified version of the North Carolina Food Establishment Inspection Report. Pantries partnered with organized food bank networks were compared with those that operated independently. In this exploratory research, additional comparisons were examined for pantries in metropolitan areas versus nonmetropolitan areas and pantries with managers who had received food safety training versus managers who had not. The results provide a snapshot of how North Carolina food pantries operate and document risk mitigation strategies for foodborne illness for the vulnerable populations they serve. Data analysis reveals gaps in food safety knowledge and practice, indicating that pantries would benefit from more effective food safety training, especially focusing on formalizing risk management strategies. In addition, new tools, procedures, or policy interventions might improve information actualization by food pantry personnel.

Health and Safety Procedures Manual for hazardous waste sites

Energy Technology Data Exchange (ETDEWEB)

Thate, J.E.

1992-09-01

The Oak Ridge National Laboratory Chemical Assessments Team (ORNL/CAT) has developed this Health and Safety Procedures Manual for the guidance, instruction, and protection of ORNL/CAT personnel expected to be involved in hazardous waste site assessments and remedial actions. This manual addresses general and site-specific concerns for protecting personnel, the general public, and the environment from any possible hazardous exposures. The components of this manual include: medical surveillance, guidance for determination and monitoring of hazards, personnel and training requirements, protective clothing and equipment requirements, procedures for controlling work functions, procedures for handling emergency response situations, decontamination procedures for personnel and equipment, associated legal requirements, and safe drilling practices.

Human Factors Evaluation of Procedures for Periodic Safety Review of Yonggwang Unit no. 1, 2

Energy Technology Data Exchange (ETDEWEB)

Lee, Yong Hee; Lee, Jung Woon; Park, Jae Chang (and others)

2006-01-15

This report describes the results of human factors assessment on the plant operating procedures as part of Periodic Safety Review(PSR) of Yonggwang Nuclear Power Plant Unit no. 1, 2. The suitability of item and appropriateness of format and structure in the key operating procedures of nuclear power plants were investigated by the review of plant operating experiences and procedure documents, field survey, and experimental assessment on some part of procedures. A checklist was used to perform this assessment and record the review results. The reviewed procedures include EOP(Emergency Operating Procedures), GOP(General Operating Procedures), AOP(Abnormal Operating Procedures), and management procedures of some technical departments. As results of the assessments, any significant problem challenging the safety was not found on the human factors in the operating procedures. However, several small items to be changed and improved were discovered. An action plan is recommended to accommodate the suggestions and review comments. It will enhance the plant safety on the operating procedure.

Improvement of the safety level of installations with the generalization of procedures

International Nuclear Information System (INIS)

Cornille, Y.; Dupraz, B.; Schektman, N.

1986-06-01

The generalization of control procedures to the largest possible spectra of accidental situations which is being developed on pressurized water reactor units will allow to increase the safety level of these installations. This improvement has been quantified for some situations pointing out an appreciable mitigation of meltdown risk which could result. A new improvement is aimed with the definition and the utilization of new procedures ''by states'' which will allow an optimized treatment of situations resulting from multiple failures, now treated in the procedures SPI - SPU - U1. The needs related to these procedures and their development led to joint research and development programs between Electricite de France and the Institute of Protection and Nuclear Safety [fr

Efficacy, Reliability, and Safety of Completely Autologous Fibrin Glue in Neurosurgical Procedures: Single-Center Retrospective Large-Number Case Study.

Science.gov (United States)

Nakayama, Noriyuki; Yano, Hirohito; Egashira, Yusuke; Enomoto, Yukiko; Ohe, Naoyuki; Kanemura, Nobuhiro; Kitagawa, Junichi; Iwama, Toru

2018-01-01

Commercially available fibrin glue (Com-FG), which is used commonly worldwide, is produced with pooled human plasma from multiple donors. However, it has added bovine aprotinin, which involves the risk of infection, allogenic immunity, and allergic reactions. We evaluate the efficacy, reliability, and safety of completely autologous fibrin glue (CAFG). From August 2014 to February 2016, prospective data were collected and analyzed from 153 patients. CAFG was prepared with the CryoSeal System using autologous blood and was applied during neurosurgical procedures. Using CAFG-soaked oxidized regenerated cellulose and/or polyglycolic acid sheets, we performed a pinpoint hemostasis, transposed the offending vessels in a microvascular decompression, and covered the dural incision to prevent cerebrospinal fluid leakage. The CryoSeal System had generated up to a mean of 4.51 mL (range, 3.0-8.4 mL) of CAFG from 400 mL autologous blood. Com-FG products were not used in our procedures. Only 6 patients required an additional allogeneic blood transfusion. The hemostatic effective rate was 96.1% (147 of 153 patients). Only 1 patient who received transsphenoidal surgery for a pituitary adenoma presented with the complication of delayed postoperative cerebrospinal fluid leakage (0.65%). No patient developed allergic reactions or systemic complications associated with the use of CAFG. CAFG effectively provides hemostatic, adhesive, and safety performance. The timing and three-dimensional shape of CAFG-soaked oxidized regenerated cellulose and/or polyglycolic acid sheets solidification can be controlled with slow fibrin formation. The cost to prepare CAFG is similar compared with Com-FG products, and it can therefore be easily used at most institutions. Copyright © 2017 Elsevier Inc. All rights reserved.

Determining quantitative road safety targets by applying statistical prediction techniques and a multi-stage adjustment procedure.

Science.gov (United States)

Wittenberg, P; Sever, K; Knoth, S; Sahin, N; Bondarenko, J

2013-01-01

Due to substantial progress made in road safety in the last ten years, the European Union (EU) renewed the ambitious agreement of halving the number of persons killed on the roads within the next decade. In this paper we develop a method that aims at finding an optimal target for each nation, in terms of being as achievable as possible, and with the cumulative EU target being reached. Targets as an important component in road safety policy are given as reduction rate or as absolute number of road traffic deaths. Determination of these quantitative road safety targets (QRST) is done by a top-down approach, formalized in a multi-stage adjustment procedure. Different QRST are derived under consideration of recent research. The paper presents a method to break the national target further down to regional targets in case of the German Federal States. Generalized linear models are fitted to data in the period 1991-2010. Our model selection procedure chooses various models for the EU and solely log-linear models for the German Federal States. If the proposed targets for the EU Member States are attained, the sum of fatalities should not exceed the total value of 15,465 per year by 2020. Both, the mean level and the range of mortality rates within the EU could be lowered from 28-113 in 2010 to 17-41 per million inhabitants in 2020. This study provides an alternative to the determination of safety targets by political commitments only, taking the history of road fatalities trends and population into consideration. Copyright © 2012 Elsevier Ltd. All rights reserved.

Determination of the number of software tests using probabilistic safety assessment

International Nuclear Information System (INIS)

Kang, H. K.; Seong, T. Y.; Lee, K. Y.

2000-01-01

The broader usage of digital equipment in nuclear power plants gives rise to the safety problems of software. The field test should be performed before the software is used in critical applications because it is well known that software shows non-linear response when it is applied to different target systems in different environment. In the case of safety-critical applications, the result of tests contains usually zero failure case and the satisfiable number of tests is hard to be determined. In this paper, we suggests the method to determine the number of software tests without failure using the probabilistic safety assessment. From the result of the probabilistic safety assessment on total system, the desirable unavailability of software is calculated and the number of tests is determined

Quality and safety of nuclear installations: the role of administration, and, nuclear safety and regulatory procedures

International Nuclear Information System (INIS)

Queniart, D.

1979-12-01

In the first paper the author defines the concepts of safety and quality and describes the means of intervention by the Public Authorities in safety matters of nuclear installations. These include individual authorisations, definition and application of technical rules and surveillance of installations. In the second paper he defines the distinction between radiation protection and safety and presents the legislative and regulatory plan for nuclear safety in France. A central safety service for nuclear installations was created in March 1973 within the Ministry of Industrial and Scientific Development, where, amongst other tasks, it draws up regulatory procedures and organizes inspections of the installations. The main American regulations for light water reactors are outlined and the French regulatory system for different types of reactors discussed

Safety and efficacy of procedural sedation and analgesia (PSA ...

African Journals Online (AJOL)

Safety and efficacy of procedural sedation and analgesia (PSA) conducted by medical officers in a level 1 hospital in Cape Town. ... Respiratory complications were treated with simple airway manoeuvres; no patient required intubation or experienced respiratory problems after waking up. There was no significant difference ...

Splash Safety During Dermatologic Procedures Among US Dermatology Residents.

Science.gov (United States)

Korta, Dorota Z; Chapman, Lance W; Lee, Patrick K; Linden, Kenneth G

2017-07-01

Dermatologists are at potential risk of acquiring infections from contamination of the mucous membranes by blood and body fluids. However, there are little data on splash safety during procedural dermatology. To determine dermatology resident perceptions about splash risk during dermatologic procedures and to quantify the rate of protective equipment use. An anonymous on-line survey was sent to 108 United States ACGME-approved dermatology residency programs assessing frequency of facial protection during dermatologic procedures, personal history of splash injury, and, if applicable, reasons for not always wearing facial protection. A total of 153 dermatology residents responded. Rates of facial protection varied by procedure, with the highest rates during surgery and the lowest during local anesthetic injection. Over 54% of respondents reported suffering facial splash while not wearing facial protection during a procedure. In contrast, 88.9% of respondents correctly answered that there is a small risk of acquiring infection from mucosal splash. Residency program recommendations for facial protection seem to vary by procedure. The authors' results demonstrate that although facial splash is a common injury, facial protection rates and protective recommendations vary significantly by procedure. These data support the recommendation for enhanced facial protection guidelines during procedural dermatology.

Operating procedure automation to enhance safety of nuclear power plants

International Nuclear Information System (INIS)

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

1989-01-01

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

Uncodified safety norms and procedural compliance in nuclear power plants

International Nuclear Information System (INIS)

Ignatov, M.

2000-01-01

The mechanism of procedural compliance in operational teams is analysed. It is investigated the interrelationship between codified (institutional or officials) rules and uncodified safety norm and their influence on the job performance, social behaviour and social interaction of the operational personnel

Convention on nuclear safety. Rules of procedure and financial rules

International Nuclear Information System (INIS)

1999-01-01

The document is the first revision of the Rules of Procedures and Financial Rules that apply mutatis mutandis to any meetings of the Contracting Parties to the Convention on Nuclear Safety (INFCIRC/573), convened in accordance with the Chapter 3 of the Convention

Convention on Nuclear Safety. Rules of procedure and financial rules

International Nuclear Information System (INIS)

2002-01-01

The document is the second revision of the Rules of Procedures and Financial Rules that apply mutatis mutandis to any meetings of the Contracting Parties to the Convention on Nuclear Safety (INFCIRC/573), convened in accordance with the Chapter 3 of the Convention

Risk and safety requirements for diagnostic and therapeutic procedures in allergology: World Allergy Organization Statement

Directory of Open Access Journals (Sweden)

Marek L. Kowalski

2016-10-01

Full Text Available Abstract One of the major concerns in the practice of allergy is related to the safety of procedures for the diagnosis and treatment of allergic disease. Management (diagnosis and treatment of hypersensitivity disorders involves often intentional exposure to potentially allergenic substances (during skin testing, deliberate induction in the office of allergic symptoms to offending compounds (provocation tests or intentional application of potentially dangerous substances (allergy vaccine to sensitized patients. These situations may be associated with a significant risk of unwanted, excessive or even dangerous reactions, which in many instances cannot be completely avoided. However, adverse reactions can be minimized or even avoided if a physician is fully aware of potential risk and is prepared to appropriately handle the situation. Information on the risk of diagnostic and therapeutic procedures in allergic diseases has been accumulated in the medical literature for decades; however, except for allergen specific immunotherapy, it has never been presented in a systematic fashion. Up to now no single document addressed the risk of the most commonly used medical procedures in the allergy office nor attempted to present general requirements necessary to assure the safety of these procedures. Following review of available literature a group of allergy experts within the World Allergy Organization (WAO, representing various continents and areas of allergy expertise, presents this report on risk associated with diagnostic and therapeutic procedures in allergology and proposes a consensus on safety requirements for performing procedures in allergy offices. Optimal safety measures including appropriate location, type and required time of supervision, availability of safety equipment, access to specialized emergency services, etc. for various procedures have been recommended. This document should be useful for allergists with already established

Safety management procedures and practices at Indira Gandhi Centre for Atomic Research

Energy Technology Data Exchange (ETDEWEB)

Rodriguez, P.; Lee, S.M.; Kapoor, R.P.; Raghunath, V.M.; Karthikeyan, S.V. [Indira Gandhi Centre for Atomic Research, Kalpakkam 603 102 (India)]. E-mail: kapoor@igcar.ernet.in

2004-07-01

The Indira Gandhi Centre for Atomic Research (IGCAR) operates FBTR (Fast Breeder Test Reactor), KAMINI (neutron source reactor), radiometallurgical laboratory, radiochemical laboratory, reprocessing plant, industrial scale sodium loops, advanced research laboratories, workshops, etc. Codified safety management procedures with systematic surveillance are essential for safe and reliable operations and these are described under the classifications of radiation safety, industrial safety and reactor operations with special emphasis on the human factor. Health physics teams, independent of the plant facility, supervise the radioactive facilities of the centre. Industrial safety standards are maintained by another independent section. Safety management for the reactors include a clear organisational structure, adequate documentation, compulsory training and licencing, safe working methods taking into account human factors and review by independent safety authorities. (author)

Safety management procedures and practices at Indira Gandhi Centre for Atomic Research

International Nuclear Information System (INIS)

Rodriguez, P.; Lee, S.M.; Kapoor, R.P.; Raghunath, V.M.; Karthikeyan, S.V.

2004-01-01

The Indira Gandhi Centre for Atomic Research (IGCAR) operates FBTR (Fast Breeder Test Reactor), KAMINI (neutron source reactor), radiometallurgical laboratory, radiochemical laboratory, reprocessing plant, industrial scale sodium loops, advanced research laboratories, workshops, etc. Codified safety management procedures with systematic surveillance are essential for safe and reliable operations and these are described under the classifications of radiation safety, industrial safety and reactor operations with special emphasis on the human factor. Health physics teams, independent of the plant facility, supervise the radioactive facilities of the centre. Industrial safety standards are maintained by another independent section. Safety management for the reactors include a clear organisational structure, adequate documentation, compulsory training and licencing, safe working methods taking into account human factors and review by independent safety authorities. (author)

Verification of a primary-to-secondary leaking safety procedure in a nuclear power plant using coloured Petri nets

International Nuclear Information System (INIS)

Nemeth, E.; Bartha, T.; Fazekas, Cs.; Hangos, K.M.

2009-01-01

This paper deals with formal and simulation-based verification methods of a PRImary-to-SEcondary leaking (abbreviated as PRISE) safety procedure. The PRISE safety procedure controls the draining of the contaminated water in a faulty steam generator when a non-compensable leaking from the primary to the secondary circuit occurs. Because of the discrete nature of the verification, a Coloured Petri Net (CPN) representation is proposed for both the procedure and the plant model. We have proved by using a non-model-based strategy that the PRISE safety procedure is safe, there are no dead markings in the state space, and all transitions are live; being either impartial or fair. Further analysis results have been obtained using a model-based verification approach. We created a simple, low dimensional, nonlinear dynamic model of the primary circuit in a VVER-type pressurized water nuclear power plant for the purpose of the model-based verification. This is in contrast to the widely used safety analysis that requires an accurate detailed model. Our model also describes the relevant safety procedures, as well as all of the major leaking-type faults. We propose a novel method to transform this model to a CPN form by discretization. The composed plant and PRISE safety procedure system has also been analysed by simulation using CPN analysis tools. We found by the model-based analysis-using both single and multiple faults-that the PRISE safety procedure initiates the draining when the PRISE event occurs, and no false alarm will be initiated

Levels for Hotline Miami 2: Wrong Number Using Procedural Content Generations

Directory of Open Access Journals (Sweden)

Joseph Alexander Brown

2018-04-01

Full Text Available Procedural Content Generation is the automatic process for generating game content in order to allow for a decrease in developer resources while adding to the replayability of a digital game. It has been found to be highly effective as a method when utilized in rougelike games, of which Hotline Miami 2: Wrong Number shares a number of factors. Search based procedural content, in this case, a genetic algorithm, allows for the creation of levels which meet with a number of designer set requirements. The generator proposed provides for an automatic creation of game content for a commercially available game: the level design, object placement, and enemy placement.

Operational limits and conditions and operating procedures for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

This Safety Guide was prepared as part of the Agency's programme for establishing safety standards relating to nuclear power plants. The present Safety Guide supersedes the IAEA Safety Guide on Operational Limits and Conditions for Nuclear Power Plants which was issued in 1979 as Safety Series No. 50-SG-O3. For a nuclear power plant to be operated in a safe manner, the provisions made in the final design and subsequent modifications shall be reflected in limitations on plant operating parameters and in the requirements on plant equipment and personnel. Under the responsibility of the operating organization, these shall be developed during the design safety evaluation as a set of operational limits and conditions (OLCs). A major contribution to compliance with the OLCs is made by the development and utilization of operating procedures (OPs) that are consistent with and fully implement the OLCs. The requirements for the OLCs and OPs are established in Section 5 of the IAEA Safety Requirements publication Safety of Nuclear Power Plants: Operation, which this Safety Guide supplements. The purpose of this Safety Guide is to provide guidance on the development, content and implementation of OLCs and OPs. The Safety Guide is directed at both regulators and owners/operators. This Safety Guide covers the concept of OLCs, their content as applicable to land based stationary power plants with thermal neutron reactors, and the responsibilities of the operating organization regarding their establishment, modification, compliance and documentation. The OPs to support the implementation of the OLCs and to ensure their observance are also within the scope of this Safety Guide. The particular aspects of the procedures for maintenance, surveillance, in-service inspection and other safety related activities in connection with the safe operation of nuclear power plants are outside the scope of this Safety Guide but can be found in other IAEA Safety Guides. Section 2 indicates the

Operational limits and conditions and operating procedures for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2000-01-01

This Safety Guide was prepared as part of the Agency's programme for establishing safety standards relating to nuclear power plants. The present Safety Guide supersedes the IAEA Safety Guide on Operational Limits and Conditions for Nuclear Power Plants which was issued in 1979 as Safety Series No. 50-SG-O3. For a nuclear power plant to be operated in a safe manner, the provisions made in the final design and subsequent modifications shall be reflected in limitations on plant operating parameters and in the requirements on plant equipment and personnel. Under the responsibility of the operating organization, these shall be developed during the design safety evaluation as a set of operational limits and conditions (OLCs). A major contribution to compliance with the OLCs is made by the development and utilization of operating procedures (OPs) that are consistent with and fully implement the OLCs. The requirements for the OLCs and OPs are established in Section 5 of the IAEA Safety Requirements publication Safety of Nuclear Power Plants: Operation, which this Safety Guide supplements. The purpose of this Safety Guide is to provide guidance on the development, content and implementation of OLCs and OPs. The Safety Guide is directed at both regulators and owners/operators. This Safety Guide covers the concept of OLCs, their content as applicable to land based stationary power plants with thermal neutron reactors, and the responsibilities of the operating organization regarding their establishment, modification, compliance and documentation. The OPs to support the implementation of the OLCs and to ensure their observance are also within the scope of this Safety Guide. The particular aspects of the procedures for maintenance, surveillance, in-service inspection and other safety related activities in connection with the safe operation of nuclear power plants are outside the scope of this Safety Guide but can be found in other IAEA Safety Guides. Section 2 indicates the

Standards for radiation protection instrumentation: design of safety standards and testing procedures

International Nuclear Information System (INIS)

Meissner, Frank

2008-01-01

This paper describes by means of examples the role of safety standards for radiation protection and the testing and qualification procedures. The development and qualification of radiation protection instrumentation is a significant part of the work of TUV NORD SysTec, an independent expert organisation in Germany. The German Nuclear Safety Standards Commission (KTA) establishes regulations in the field of nuclear safety. The examples presented may be of importance for governments and nuclear safety authorities, for nuclear operators and for manufacturers worldwide. They demonstrate the advantage of standards in the design of radiation protection instrumentation for new power plants, in the upgrade of existing instrumentation to nuclear safety standards or in the application of safety standards to newly developed equipment. Furthermore, they show how authorities may proceed when safety standards for radiation protection instrumentation are not yet established or require actualization. (author)

Assessment of the safety of injection practices and injection-related procedures in family health units and centers in Alexandria.

Science.gov (United States)

Elhoseeny, Taghareed A; Mourad, Juidan K

2014-08-01

The Safe Injection Global Network (SIGN) developed an intervention strategy for reducing overuse of injections and promoting the administration of safe injections. Tool C--Revised is designed to assess the safety of the most common procedures that puncture the skin within health services. The aim of the study was to assess injection safety within the primary healthcare facilities in Alexandria using Tool C--Revised. A total of 45 family health units and centers in Alexandria were selected by proportional allocation from the eight regions of Alexandria. The Tool C--Revised of the WHO was used for observation of the entire facility, injection practices and injection-related procedures, and sterilization practices. Interview of different health providers and immediate supervisor of injections was carried out. Indicators that reflect risk included: deficiency of alcohol-based hand rub for cleansing hands (13.3%), compliance with hand wash before preparing a procedure (56.9% before injection practices, 61.3% before phlebotomy, and 67.6% before lancet puncture), and wearing a new pair of gloves before new procedures (48.6% before injection practices, 9.7% for phlebotomy, 11.8% for lancet puncture, and 80% for both intravenous injections and infusions). Enough disposable equipment in all facilities for at least 2 weeks dependent on the statement of the average numbers of procedures per week was shown. Only 38% of the providers had received training regarding injection safety in the last 2 years and 62.5% had completed their three doses of hepatitis B vaccine. Only 42.2% of staffs who handled healthcare waste had access to heavy gloves. Indicators related to injection and injection-related practices that reflect risk to patients include deficiency of alcohol-based hand rub tools, nonadherence to hand hygiene before preparing an injection, and inadequate adherence to using a clean barrier when opening a glass ampule and use of gloves. Indicators that may reflect risk to

Leading Edge. Volume 7, Number 3. Systems Safety Engineering

Science.gov (United States)

2010-01-01

foods were not always safe to eat given the sanitary conditions of the day. In 1943, the psychologist Abraham Maslow proposed a five-level... hierarchy of basic human needs, and safety was number two on this list. System safety is a specialized and formalized extension of our in- herent drive for...factors, hazards, mishaps, and ef- fects. The following is an example of each element within the hierarchy : An exposed sharp edge in a relay cabi- net

A combined deterministic and probabilistic procedure for safety assessment of components with cracks - Handbook.

Energy Technology Data Exchange (ETDEWEB)

Dillstroem, Peter; Bergman, Mats; Brickstad, Bjoern; Weilin Zang; Sattari-Far, Iradj; Andersson, Peder; Sund, Goeran; Dahlberg, Lars; Nilsson, Fred (Inspecta Technology AB, Stockholm (Sweden))

2008-07-01

SSM has supported research work for the further development of a previously developed procedure/handbook (SKI Report 99:49) for assessment of detected cracks and tolerance for defect analysis. During the operative use of the handbook it was identified needs to update the deterministic part of the procedure and to introduce a new probabilistic flaw evaluation procedure. Another identified need was a better description of the theoretical basis to the computer program. The principal aim of the project has been to update the deterministic part of the recently developed procedure and to introduce a new probabilistic flaw evaluation procedure. Other objectives of the project have been to validate the conservatism of the procedure, make the procedure well defined and easy to use and make the handbook that documents the procedure as complete as possible. The procedure/handbook and computer program ProSACC, Probabilistic Safety Assessment of Components with Cracks, has been extensively revised within this project. The major differences compared to the last revision are within the following areas: It is now possible to deal with a combination of deterministic and probabilistic data. It is possible to include J-controlled stable crack growth. The appendices on material data to be used for nuclear applications and on residual stresses are revised. A new deterministic safety evaluation system is included. The conservatism in the method for evaluation of the secondary stresses for ductile materials is reduced. A new geometry, a circular bar with a circumferential surface crack has been introduced. The results of this project will be of use to SSM in safety assessments of components with cracks and in assessments of the interval between the inspections of components in nuclear power plants

A procedure for safety assessment of components with cracks - Handbook. 3rd revised edition

Energy Technology Data Exchange (ETDEWEB)

Andersson, P.; Bergman, M.; Brickstad, B.; Dahlberg, L.; Nilsson, F.; Sattari-Far, I. [SAQ Kontroll AB, Stockholm (Sweden)

1999-12-01

given objectives, the handbook contains solutions for the stress intensity factor and the limit load for a number of crack geometries of importance for applications. It also contains rules for defect characterization, recommendations for estimation of residual stresses, material data for nuclear applications and a safety evaluation system. To ensure conservatism, the procedure with the given solutions of the stress intensity factor and the limit load has been validated. Predictions of the procedure were compared with the actual outcome of full scale experiments reported in the literature. The first edition of the handbook was released in 1990 and the second in 1991. This third edition has been extensively revised. A new safety evaluation system has been introduced. The conservatism in the method for assessment of secondary stresses has been reduced. The solutions for the stress intensity factor and the limit load, the recommendations for estimation of residual stresses and the given material data for nuclear applications have been updated. A modern Windows based PC-program SACC has been developed which can perform the assessments described in this handbook including calculation of crack growth due to stress corrosion and fatigue. The program also has an option which enables assessment of cracks according to the 1995 edition of the ASME Boiler and Pressure Vessel Code, Section XI. Appendices A, C and H for assessment of cracks in ferritic pressure vessels, austenitic piping and ferritic piping, respectively.

A procedure for safety assessment of components with cracks - Handbook. 3rd revised edition

International Nuclear Information System (INIS)

Andersson, P.; Bergman, M.; Brickstad, B.; Dahlberg, L.; Nilsson, F.; Sattari-Far, I.

1999-12-01

, the handbook contains solutions for the stress intensity factor and the limit load for a number of crack geometries of importance for applications. It also contains rules for defect characterization, recommendations for estimation of residual stresses, material data for nuclear applications and a safety evaluation system. To ensure conservatism, the procedure with the given solutions of the stress intensity factor and the limit load has been validated. Predictions of the procedure were compared with the actual outcome of full scale experiments reported in the literature. The first edition of the handbook was released in 1990 and the second in 1991. This third edition has been extensively revised. A new safety evaluation system has been introduced. The conservatism in the method for assessment of secondary stresses has been reduced. The solutions for the stress intensity factor and the limit load, the recommendations for estimation of residual stresses and the given material data for nuclear applications have been updated. A modern Windows based PC-program SACC has been developed which can perform the assessments described in this handbook including calculation of crack growth due to stress corrosion and fatigue. The program also has an option which enables assessment of cracks according to the 1995 edition of the ASME Boiler and Pressure Vessel Code, Section XI. Appendices A, C and H for assessment of cracks in ferritic pressure vessels, austenitic piping and ferritic piping, respectively

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.

Safety and application of procedures or: how do ''they'' have to use operating procedures in nuclear power plants

International Nuclear Information System (INIS)

Dien, Y.

1993-03-01

Emergency procedures are inescapable aspects of safety. They can be seen as the laws to be respected in an accident situation. But as for all laws, there remains the problem of their application: should strict adherence to the procedure be imposed under all circumstances. Is this possible. Are there any potential risks with such a requirement. Or, on the contrary, should application be more ''open'', more flexible, allowing for adaptation to the actual situation. But what are the potential risks involved in this approach. Are these two approaches to the application of procedures mutually exclusive, or are they complementary. This paper analyzes the nature of the problem of application of procedures and proposes orientations for further thought on the matter. (author). 11 refs

Convention on nuclear safety. Rules of procedure and financial rules

International Nuclear Information System (INIS)

1998-01-01

The document presents the Rules of Procedure and Financial Rules that apply mutatis mutandis to any meeting of the Contracting Parties to the Convention on Nuclear Safety (INFCIRC/449) convened in accordance with Chapter 3 of the Convention. It includes four parts: General provisions, Preparatory process for review meetings, Review meetings, and Amendment and interpretation of rules

49 CFR 214.337 - On-track safety procedures for lone workers.

Science.gov (United States)

2010-10-01

...-track equipment is not impaired by background noise, lights, precipitation, fog, passing trains, or any... performing routine inspection or minor correction may use individual train detection to establish on-track... worker retains an absolute right to use on-track safety procedures other than individual train detection...

Efficacy, safety, and patient acceptability of the Essure™ procedure

Directory of Open Access Journals (Sweden)

Hopkins MR

2011-04-01

Full Text Available Collette R Lessard, Matthew R HopkinsDepartment of Obstetrics and Gynecology, Mayo Clinic, Rochester, Minnesota, USAAbstract: The Essure™ system for permanent contraception was developed as a less invasive method of female sterilization. Placement of the Essure™ coil involves a hysteroscopic transcervical technique. This procedure can be done in a variety of settings and with a range of anesthetic options. More than eight years have passed since the US Food and Drug Administration approval of Essure™. Much research has been done to evaluate placement success, adverse outcomes, satisfaction, pain, and the contraceptive efficacy of the Essure™. The purpose of this review is to summarize the available literature regarding the efficacy, safety, and patient satisfaction with this new sterilization technique.Keywords: hysteroscopic sterilization, Essure™, safety, efficacy, acceptability

78 FR 4985 - Uniform Procedures for State Highway Safety Grant Programs

Science.gov (United States)

2013-01-23

...) that were tied to the agency's child restraint performance standards (FMVSS 213). Thus, under today's... consolidates into one rule a number of old regulations (State Highway Safety Agency, Political Subdivision... Belt Performance Grants (formerly codified at 23 U.S.C. 406) and Child Safety and Child Booster Seat...

Radiation safety procedures in radioiodine therapy for thyroid cancer

International Nuclear Information System (INIS)

Rajashekharrao, B.; Samuel, A.M.

1999-01-01

During any administration of radioactive materials, it is imperative to always be conversant with any forbidden radiation health safety practices. This need is amplified when dealing with therapeutic amount of radionuclides. Among all the procedures dealing with the use of radiopharmaceuticals, it is easiest to think of 131 I, since this is the most widely used unsealed source of a radiopharmaceutical for treatment of thyroid cancer and hyperthyroidism and carries with it most of the problems associated with therapy applications

Risk and safety of pediatric sedation/anesthesia for procedures outside the operating room.

Science.gov (United States)

Cravero, Joseph P

2009-08-01

Sedation and anesthesia outside the operating room represents a rapidly growing field of practice that involves a number of different specialty providers including anesthesiology. The literature surrounding this work is found in a variety of journals - many outside anesthesiology. This review is intended to inform readers about the current status of risk and safety involving sedation/anesthesia for tests and minor procedures utilizing a wide range of sources. Two large database studies have helped to define the frequency and nature of adverse events in pediatric sedation/anesthesia practice from a multispecialty perspective. A number of papers describing respiratory and hemodynamic aspects of dexmedetomidine sedation have also been published. Finally, a number of studies relating to training sedation providers, reporting of sedation adverse events, sedation for vulnerable populations, and (in particular) ketamine sedation adverse respiratory events have also come to light. The latest publications continue to document a relatively low risk to pediatric sedation yet also warn us about the potential adverse events in this field. The results help to define competencies required to deliver pediatric sedation and make this practice even safer. Particularly interesting are new jargon and methodologies for defining adverse events and the use of new methods for training sedation providers.

Exploring the safety in numbers effect for vulnerable road users on a macroscopic scale.

Science.gov (United States)

Tasic, Ivana; Elvik, Rune; Brewer, Simon

2017-12-01

A "Safety in Numbers" effect for a certain group of road users is present if the number of crashes increases at a lower rate than the number of road users. The existence of this effect has been invoked to justify investments in multimodal transportation improvements in order to create more sustainable urban transportation systems by encouraging walking, biking, and transit ridership. The goal of this paper is to explore safety in numbers effect for cyclists and pedestrians in areas with different levels of access to multimodal infrastructure. Data from Chicago served to estimate the expected number of crashes on the census tract level by applying Generalized Additive Models (GAM) to capture spatial dependence in crash data. Measures of trip generation, multimodal infrastructure, network connectivity and completeness, and accessibility were used to model travel exposure in terms of activity, number of trips, trip length, travel opportunities, and conflicts. The results show that a safety in numbers effect exists on a macroscopic level for motor vehicles, pedestrians, and bicyclists. Copyright © 2017 Elsevier Ltd. All rights reserved.

United States Nuclear Regulatory Commission Staff practice and procedure digest

International Nuclear Information System (INIS)

1990-08-01

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

A procedure for safety assessment of components with cracks - Handbook

International Nuclear Information System (INIS)

Andersson, P.; Bergman, M.; Brickstad, B.; Dahlberg, L.; Nilsson, F.; Sattari-Far, I.

1996-01-01

In this handbook a procedure is described which can be used both for assessment of detected cracks or crack like defects or for defect tolerance analysis. The procedure can be used to calculate possible crack growth due to fatigue or stress corrosion and to calculate the reserve margin for failure due to fracture and plastic collapse. For ductile materials, the procedure gives the reserve margin for initiation of stable crack growth. Thus, an extra reserve margin, unknown to size, exists for failure in components made of ductile materials. The procedure was developed for operative use with the following objectives in mind: The procedure should be able to handle both linear and non-linear problems without any a priori division; The procedure shall ensure uniqueness of the safety assessment; The procedure should be well defined and easy to use; The conservatism of the procedure should be well validated; The handbook that documents the procedure should be so complete that for most assessments access to any other fracture mechanics literature should not be necessary. The method utilized is based on the R6-method developed at Nuclear Electric plc. This method can in principle be used for all metallic materials. It is, however, more extensively verified for steel alloys only. The method is not intended for use in temperatures where creep deformation is of importance. The first edition of the handbook was released in 1990 and the second in 1991. This third edition has been extensively revised. A Windows-based program (SACC) has been developed which can perform the assessments described in the book including calculation of crack growth due to stress corrosion and fatigue. 52 refs., 27 figs., 35 tabs

Safety code 19: recommended safety procedures for the selection, installation and use of x-ray diffraction equipment

International Nuclear Information System (INIS)

1984-01-01

This document is one of a series of Safety Codes prepared by the Radiation Protection Bureau to set out requirements for the safe use of radiation emitting devices. The equipment and installation guidelines and safety procedures detailed in this Code are primarily for the instruction and guidance of persons employed in Federal Public Service Departments and Agencies, as well as those coming under the jurisdiction of the Canada Labour Code. This Safety Code is also intended to assist other users of X-ray diffraction equipment to select safe equipment and to install and use it so that the radiation hazard to the operator and other persons in its vicinity is negligible. It should be noted that facilities under provincial jurisdiction may be subject to requirements specified under provincial statutes. This Code supersedes Safety Code RPD-SC-7, entitled 'Requirements For Non-Medical X-Ray Equipment, Use and Installation', insofar as X-ray diffraction equipment is concerned, and it is intended to complement X-ray equipment design, construction and performance standards promulgated under the Radiation Emitting Devices Act

Development of a draft of human factors safety review procedures for the Korean Next Generation Reactor

International Nuclear Information System (INIS)

Lee, Jung Woon; Moon, B. S.; Park, J. C.; Lee, Y. H.; Oh, I. S.; Lee, H. C.

2000-02-01

In this study, a draft of Human Factors Engineering (HFE) Safety Review Procedures (SRP) was developed for the safety review of KNGR based on HFE Safety and Regulatory Requirements and Guidelines (SRRG). This draft includes acceptance criteria, review procedure, and evaluation findings for the areas of review including HFE program management, human factors analyses, human factors design, and HFE verification and validation, based on section 15.1 'human factors engineering design process' and 15.2 'control room human factors engineering' of KNGR specific safety requirements and chapter 15 'human factors engineering' of KNGR safety regulatory guides. For the effective review, human factors concerns or issues related to advanced HSI design that have been reported so far should be extensively examined. In this study, a total of 384 human factors issues related to the advanced HSI design were collected through our review of a total of 145 documents. A summary of each issue was described and the issues were identified by specific features of HSI design. These results were implemented into a database system

Safety in numbers? Tackling domestic abuse in couples and network therapies.

Science.gov (United States)

Galvani, Sarah A

2007-03-01

Family, network or couples-based therapies have been helping to support people with substance problems for decades. Their value in supporting a person to change their alcohol or drug use is clear. However, as links between substance use and domestic abuse are increasingly recognised, these approaches need to reflect on the potential safety risks they present to people taking part. The prevalence of domestic abuse among people receiving drug and alcohol services is considerably higher than general population estimates, yet this does not appear to have been adequately addressed in network therapies. This article suggests that this needs to change and that safety of service users needs to be at least as important as the intervention itself. It offers for debate a number of potential safety issues raised by network therapies where there is evidence of domestic abuse; it provides examples of three approaches used to marshal social and network support in substance interventions; and offers a number of suggestions for how network therapies can ensure their use remains safe and supportive where there is domestic abuse.

Licensing procedures and safety criteria for core conversion in Japan

International Nuclear Information System (INIS)

Kanda, K.; Nakagome, Y.; Hayashi, M.

1983-01-01

Procedures relating to the construction and operation of reactor facilities are discussed. Specifically, the Safety Analysis Report on the Kyoto University Critical Assembly (KUCA) core conversion (93% to 45% enrichment) is noted. The results of critical experiments in the KUCA and of burnup tests in the Oak Ridge Research (ORR) Reactor will be used in the final determination of the feasibility of the conversion of the Kyoto University High Flux Reactor (KUHFR) to the use of 45% enrichment

Licensing procedures and safety criteria for core conversion in Japan

International Nuclear Information System (INIS)

Kanda, K.; Nakagome, Y.; Hayashi, M.

1983-01-01

In Japan, the establishment and operation of nuclear installations are governed mainly by the Law for Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors. This law lays down the regulations and conditions for licensing of the various installations involved in the nuclear fuel cycle, namely licensing of installations for refining, fabricating and reprocessing; and reactors, as well as licensing of the use of nuclear fuels in research facilities. Although procedures for the installations listed above vary depending on the installation concerned, only those relating to construction and operation of reactor facilities will be analysed in this study, as the conditions and principles applying to licensing and control of other installations are, to a large extent, similar to those concerning reactor facilities. The second part of this presentation describes the safety review of the KUCA reactor core conversion form HEU to MEU. For the safety review of the core conversion, the Committee on Examination of Reactor Safety of Japanese Government examined mainly the the nuclear characteristics and the integrity of aluminide fuel plates, which was very severe because we had no experience to use aluminide fuel plates in Japan. The integrity of fuel plates and the results of the worst accident analysis for the MEU core are shown with the comparison between the HEU and MEU cores. The significant difference was not observed between them. All the regulatory procedures were completed in September 1980. Fabrication of MEU fuel elements for the KUCA experiments by CERCA in France was started in September 1980, and will be completed in March 1981. The critical experiments in the KUCA with MEU fuel will be started on a single-core in May 1981 as a first step. Those on a coupled-core will follow

Recommendations to improve radiation safety during invasive cardiovascular procedures

International Nuclear Information System (INIS)

Miranda, Patricia; Ubeda, Carlos; Vano, Eliseo; Nocetti, Diego

2014-01-01

In this paper we present guidelines aimed to improve radiation safety during invasive cardiovascular procedures. Unwanted effects upon patients and medical personnel are conventionally classified. A program of Quality Assurance is proposed, an aspect of which is a program for radiologic protection, including operator protection, radiation monitoring, shielding and personnel training. Permanent and specific actions should be taken at every cardiovascular lab, before, during and after interventions. In order to implement these guidelines and actions, a fundamental step is a review of current legislation. Specific programs for quality control and radiologic protection along with a definition of acceptable radiation exposure doses are required

Improving the safety and quality of nursing care through standardized operating procedures in Bosnia and Herzegovina.

Science.gov (United States)

Ausserhofer, Dietmar; Rakic, Severin; Novo, Ahmed; Dropic, Emira; Fisekovic, Eldin; Sredic, Ana; Van Malderen, Greet

2016-06-01

We explored how selected 'positive deviant' healthcare facilities in Bosnia and Herzegovina approach the continuous development, adaptation, implementation, monitoring and evaluation of nursing-related standard operating procedures. Standardized nursing care is internationally recognized as a critical element of safe, high-quality health care; yet very little research has examined one of its key instruments: nursing-related standard operating procedures. Despite variability in Bosnia and Herzegovina's healthcare and nursing care quality, we assumed that some healthcare facilities would have developed effective strategies to elevate nursing quality and safety through the use of standard operating procedures. Guided by the 'positive deviance' approach, we used a multiple-case study design to examine a criterion sample of four facilities (two primary healthcare centres and two hospitals), collecting data via focus groups and individual interviews. In each studied facility, certification/accreditation processes were crucial to the initiation of continuous development, adaptation, implementation, monitoring and evaluation of nursing-related SOPs. In one hospital and one primary healthcare centre, nurses working in advanced roles (i.e. quality coordinators) were responsible for developing and implementing nursing-related standard operating procedures. Across the four studied institutions, we identified a consistent approach to standard operating procedures-related processes. The certification/accreditation process is enabling necessary changes in institutions' organizational cultures, empowering nurses to take on advanced roles in improving the safety and quality of nursing care. Standardizing nursing procedures is key to improve the safety and quality of nursing care. Nursing and Health Policy are needed in Bosnia and Herzegovina to establish a functioning institutional framework, including regulatory bodies, educational systems for developing nurses' capacities or the

Development of a draft of human factors safety review procedures for the Korean next generation reactor

Energy Technology Data Exchange (ETDEWEB)

Lee, Jung Woon; Moon, B. S.; Park, J. C.; Lee, Y. H.; Oh, I. S.; Lee, H. C. [Korea Atomic Energy Research Institute, Taejeon (Korea)

2000-02-01

In this study, a draft of human factors engineering (HFE) safety review procedures (SRP) was developed for the safety review of KNGR based on HFE Safety and Regulatory Requirements and Guidelines (SRRG). This draft includes acceptance criteria, review procedure, and evaluation findings for the areas of review including HFE Program Management, Human Factors Analyses, Human Factors Design, and HFE Verification and Validation, based on Section 15.1 'Human Factors Engineering Design Process' and 15.2 'Control Room Human Factors Engineering' of KNGR Specific Safety Requirements and Chapter 15 'Human Factors Engineering' of KNGR Safety Regulatory Guides. For the effective review, human factors concerns or issues related to advanced HSI design that have been reported so far should be extensively examined. In this study, a total of 384 human factors issues related to the advanced HSI design were collected through our review of a total of 145 documents. A summary of each issue was described and the issues were identified by specific features of HSI design. These results were implemented into a database system. 8 refs., 2 figs. (Author)

The significance of the probabilistic safety analysis (PSA) in administrative procedures under nuclear law

International Nuclear Information System (INIS)

Berg, H.P.

1994-01-01

The probabilistic safety analysis (PSA) is a useful tool for safety relevant evaluation of nuclear power plant designed on the basis of deterministic specifications. The PSA yields data identifying reliable or less reliable systems, or frequent or less frequent failure modes to be taken into account for safety engineering. Performance of a PSA in administrative procedures under nuclear law, e.g. licensing, is an obligation laid down in a footnote to criterion 1.1 of the BMI safety criteria catalogue, which has been in force unaltered since 1977. The paper explains the application and achievements of PSA in the phase of reactor development concerned with the conceptual design basis and design features, using as an example the novel PWR. (orig./HP) [de

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

Energy Technology Data Exchange (ETDEWEB)

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

1986-12-01

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

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

International Nuclear Information System (INIS)

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

1986-12-01

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

Abdominoplasty: Risk Factors, Complication Rates, and Safety of Combined Procedures.

Science.gov (United States)

Winocour, Julian; Gupta, Varun; Ramirez, J Roberto; Shack, R Bruce; Grotting, James C; Higdon, K Kye

2015-11-01

Among aesthetic surgery procedures, abdominoplasty is associated with a higher complication rate, but previous studies are limited by small sample sizes or single-institution experience. A cohort of patients who underwent abdominoplasty between 2008 and 2013 was identified from the CosmetAssure database. Major complications were recorded. Univariate and multivariate analysis was performed evaluating risk factors, including age, smoking, body mass index, sex, diabetes, type of surgical facility, and combined procedures. The authors identified 25,478 abdominoplasties from 183,914 procedures in the database. Of these, 8,975 patients had abdominoplasty alone and 16,503 underwent additional procedures. The number of complications recorded was 1,012 (4.0 percent overall rate versus 1.4 percent in other aesthetic surgery procedures). Of these, 31.5 percent were hematomas, 27.2 percent were infections and 20.2 percent were suspected or confirmed venous thromboembolism. On multivariate analysis, significant risk factors (p procedures (1.5), and procedure performance in a hospital or surgical center versus office-based surgical suite (1.6). Combined procedures increased the risk of complication (abdominoplasty alone, 3.1 percent; with liposuction, 3.8 percent; breast procedure, 4.3 percent; liposuction and breast procedure, 4.6 percent; body-contouring procedure, 6.8 percent; liposuction and body-contouring procedure, 10.4 percent). Abdominoplasty is associated with a higher complication rate compared with other aesthetic procedures. Combined procedures can significantly increase complication rates and should be considered carefully in higher risk patients. Risk, II.

The Safety Assessment of OPR-1000 for Station Blackout Applying Combined Deterministic and Probabilistic Procedure

Energy Technology Data Exchange (ETDEWEB)

Kang, Dong Gu; Ahn, Seung-Hoon; Cho, Dae-Hyung [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2015-05-15

This is termed station blackout (SBO). However, it does not generally include the loss of available AC power to safety buses fed by station batteries through inverters or by alternate AC sources. Historically, risk analysis results have indicated that SBO was a significant contributor to overall core damage frequency. In this study, the safety assessment of OPR-1000 nuclear power plant for SBO accident, which is a typical beyond design basis accident and important contributor to overall plant risk, is performed by applying the combined deterministic and probabilistic procedure (CDPP). In addition, discussions are made for reevaluation of SBO risk at OPR-1000 by eliminating excessive conservatism in existing PSA. The safety assessment of OPR-1000 for SBO accident, which is a typical BDBA and significant contributor to overall plant risk, was performed by applying the combined deterministic and probabilistic procedure. However, the reference analysis showed that the CDF and CCDP did not meet the acceptable risk, and it was confirmed that the SBO risk should be reevaluated. By estimating the offsite power restoration time appropriately, the SBO risk was reevaluated, and it was finally confirmed that current OPR-1000 system lies in the acceptable risk against the SBO. In addition, it was demonstrated that the proposed CDPP is applicable to safety assessment of BDBAs in nuclear power plants without significant erosion of the safety margin.

Evaluation procedure of software safety plan for digital I and C of KNGR

International Nuclear Information System (INIS)

Lee, Jang Soo; Park, Jong Kyun; Lee, Ki Young; Kwon, Ki Choon; Kim, Jang Yeol; Cheon, Se Woo

2000-05-01

The development, use, and regulation of computer systems in nuclear reactor instrumentation and control (I and C) systems to enhance reliability and safety is a complex issue. This report is one of a series of reports from the Korean next generation reactor (KNGR) software safety verification and validation (SSVV) task, Korea Atomic Energy Research Institute, which investigates different aspects of computer software in reactor I and C systems, and describes the engineering procedures for developing such a software. The purpose of this guideline is to give the software safety evaluator the trail map between the code and standards layer and the design methodology and documents layer for the software important to safety in nuclear power plants. Recently, the safety planning for safety-critical software systems is being recognized as the most important phase in the software life cycle, and being developed new regulatory positions and standards by the regulatory and the standardization organizations. The requirements for software important to safety of nuclear reactor are described in such positions and standards, for example, the new standard review plan (SRP), IEC 880 supplements, IEEE standard 1228-1994, IEEE standard 7-4.3.2-1993, and IAEA safety series No. 50-SG-D3 and D8. We presented the guidance for evaluating the safety plan of the software in the KNGR protection systems. The guideline consists of the regulatory requirements for software safety in chapter 2, the evaluation checklist of software safety plan in chapter3, and the evaluation results of KNGR software safety plan in chapter 4

Evaluation procedure of software safety plan for digital I and C of KNGR

Energy Technology Data Exchange (ETDEWEB)

Lee, Jang Soo; Park, Jong Kyun; Lee, Ki Young; Kwon, Ki Choon; Kim, Jang Yeol; Cheon, Se Woo

2000-05-01

The development, use, and regulation of computer systems in nuclear reactor instrumentation and control (I and C) systems to enhance reliability and safety is a complex issue. This report is one of a series of reports from the Korean next generation reactor (KNGR) software safety verification and validation (SSVV) task, Korea Atomic Energy Research Institute, which investigates different aspects of computer software in reactor I and C systems, and describes the engineering procedures for developing such a software. The purpose of this guideline is to give the software safety evaluator the trail map between the code and standards layer and the design methodology and documents layer for the software important to safety in nuclear power plants. Recently, the safety planning for safety-critical software systems is being recognized as the most important phase in the software life cycle, and being developed new regulatory positions and standards by the regulatory and the standardization organizations. The requirements for software important to safety of nuclear reactor are described in such positions and standards, for example, the new standard review plan (SRP), IEC 880 supplements, IEEE standard 1228-1994, IEEE standard 7-4.3.2-1993, and IAEA safety series No. 50-SG-D3 and D8. We presented the guidance for evaluating the safety plan of the software in the KNGR protection systems. The guideline consists of the regulatory requirements for software safety in chapter 2, the evaluation checklist of software safety plan in chapter3, and the evaluation results of KNGR software safety plan in chapter 4.

Road safety audit tools, procedures, and experiences : a literature review and recommendations : research in the framework of the European research project Safety Standards for Road Design and Redesign SAFESTAR, Workpackage 8.

NARCIS (Netherlands)

Kooi, R.M. van der

1999-01-01

This report describes tools and procedures established in different countries which apply Road Safety Audits (RSA). These RSAs are utilized to identify potential safety problems and they concentrate on safety measures to overcome these problems. This technique is used to detect possible safety

Transition to Office-based Obstetric and Gynecologic Procedures: Safety, Technical, and Financial Considerations.

Science.gov (United States)

Peacock, Lisa M; Thomassee, May E; Williams, Valerie L; Young, Amy E

2015-06-01

Office-based surgery is increasingly desired by patients and providers due to ease of access, overall efficiency, reimbursement, and satisfaction. The adoption of office-based surgery requires careful consideration of safety, efficacy, cost, and feasibility within a providers practice. This article reviews the currently available data regarding patient and provider satisfaction as well as practical considerations of staffing, equipment, and supplies. To aid the practitioner, issues of office-based anesthesia and safety with references to currently available national guidelines and protocols are provided. Included is a brief review of billing, coding, and reimbursement. Technical procedural aspects with information and recommendations are summarized.

Employers' Occupational Health and Safety Training Obligations in Framework Directive and Training Procedure and Rules in Turkey

OpenAIRE

Nuray Gökçek Karaca; Berrin Gökçek

2015-01-01

Employers occupational safety and health training obligations are regulated in 89/391/EEC Framework Directive and also in 6331 numbered Occupational Health and Safety Law in Turkey. The main objective of this research is to determine and evaluate the employers’ occupational health and safety training obligations in Framework Directive in comparison with the 6331 numbered Occupational Health and Safety Law and to examine training principles in Turkey. For this purpose, ...

Nuclear power safety economics

International Nuclear Information System (INIS)

Legasov, V.A.; Demin, V.F.; Shevelev, Ya.V.

1984-01-01

The existing conceptual and methodical basis for the decision-making process insuring safety of the nuclear power and other (industrial and non-industrial) human activities is critically analyzed. Necessity of development a generalized economic safety analysis method (GESAM) is shown. Its purpose is justifying safety measures. Problems of GESAM development are considered including the problem of costing human risk. A number of suggestions on solving them are given. Using the discounting procedure in the assessment of risk or detriment caused by harmful impact on human health is substantiated. Examples of analyzing some safety systems in the nuclear power and other spheres of human activity are given

Use of safety analysis to site comfirmation procedure in case of hard rock repository

International Nuclear Information System (INIS)

Peltonen, E.K.

1984-02-01

The role of safety analysis in a confirmation procedure of a candidate disposal site of radioactive wastes is discussed. Items dealt with include principle reasons and practical goals of the use of safety analysis, methodology of safety analysis and assessment, as well as usefulness and adequacy of the present safety analysis. Safety analysis is a tool, which enables one to estimate quantitatively the possible radiological impacts from the disposal. The results can be compared with the criteria and the suitability conclusions drawn. Because of its systems analytical nature safety analysis is an effective method to reveal, what are the most important factors of the disposal system and the most critical site characteristics inside the lumped parameters often provided by the experimental site investigation methods. Furthermore it gives information on the accuracy needs of different site properties. This can be utilized to judge whether the quality and quantity of the measurements for the characterization are sufficient as well as to guide the further site investigations. A more practical discussion regarding the applicability of the use of safety analysis is presented by an example concerning the assessment of a Finnish candidate site for low- and intermediate-level radioactive waste repository. (author)

A simple intervention to improve patient safety, save time and improve staff experience in the AMU procedure room.

Science.gov (United States)

Misselbrook, Gary Peter; Kause, Juliane; Yeoh, Su-Ann

2016-01-01

Over the last decade, operating theatres and Intensive Care Units (ICUs) have established systematic methods for performing procedures on patients that have been shown to reduce complications and improve patient safety. Whilst the use of procedure rooms on Acute Medicine Units (AMUs) is highly recommended by patient safety groups and Royal College publications, they are not universally available or appropriately utilised. In this article we discuss a quality improvement project that was undertaken on an AMU at a large university teaching hospital in the United Kingdom, highlighting its successes and challenges.

NASA Spinoff Article: Automated Procedures To Improve Safety on Oil Rigs

Science.gov (United States)

Garud, Sumedha

2013-01-01

On May 11th, 2013, two astronauts emerged from the interior of the International Space Station (ISS) and worked their way toward the far end of spacecraft. Over the next 51/2 hours, the two replaced an ammonia pump that had developed a significant leak a few days before. On the ISS, ammonia serves the vital role of cooling components-in this case, one of the station's eight solar arrays. Throughout the extravehicular activity (EVA), the astronauts stayed in constant contact with mission control: every movement, every action strictly followed a carefully planned set of procedures to maximize crew safety and the chances of success. Though the leak had come as a surprise, NASA was prepared to handle it swiftly thanks in part to the thousands of procedures that have been written to cover every aspect of the ISS's operations. The ISS is not unique in this regard: Every NASA mission requires well-written procedures-or detailed lists of step-by-step instructions-that cover how to operate equipment in any scenario, from normal operations to the challenges created by malfunctioning hardware or software. Astronauts and mission control train and drill extensively in procedures to ensure they know what the proper procedures are and when they should be used. These procedures used to be exclusively written on paper, but over the past decade, NASA has transitioned to digital formats. Electronic-based documentation simplifies storage and use, allowing astronauts and flight controllers to find instructions more quickly and display them through a variety of media. Electronic procedures are also a crucial step toward automation: once instructions are digital, procedure display software can be designed to assist in authoring, reviewing, and even executing them.

Radiation safety in welding and testing

International Nuclear Information System (INIS)

King, B.E.; Malaxos, M.; Hartley, B.M.

1985-01-01

There are a number of ways of achieving radiation safety in the workplace. The first is by engineering radiation safety into the equipment, providing shielded rooms and safety interlocks. The second is by following safe working procedures. The National Health and Medical Research Council's Code of practice for the control and safe handling of sealed radioactive sources used in industrial radiography (1968) sets out the standards which must be met by equipment to be used in industrial radiography

Safety of Cargo Aircraft Handling Procedure

Directory of Open Access Journals (Sweden)

Daniel Hlavatý

2017-07-01

Full Text Available The aim of this paper is to get acquainted with the ways how to improve the safety management system during cargo aircraft handling. The first chapter is dedicated to general information about air cargo transportation. This includes the history or types of cargo aircraft handling, but also the means of handling. The second part is focused on detailed description of cargo aircraft handling, including a description of activities that are performed before and after handling. The following part of this paper covers a theoretical interpretation of safety, safety indicators and legislative provisions related to the safety of cargo aircraft handling. The fourth part of this paper analyzes the fault trees of events which might occur during handling. The factors found by this analysis are compared with safety reports of FedEx. Based on the comparison, there is a proposal on how to improve the safety management in this transportation company.

United States Nuclear Regulatory Commission Staff Practice and Procedure Digest

International Nuclear Information System (INIS)

1992-02-01

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

Safety of Running Two Rooms: A Systematic Review and Meta-Analysis of Overlapping Neurosurgical Procedures.

Science.gov (United States)

Self, D Mitchell; Ilyas, Adeel; Stetler, William R

2018-04-27

Overlapping surgery, a long-standing practice within academic neurosurgery centers nationwide, has recently come under scrutiny from the government and media as potentially harmful to patients. Therefore, the objective of this systematic review and meta-analysis is to determine the safety of overlapping neurosurgical procedures. The authors performed a systematic review and meta-analysis in accordance with PRISMA guidelines. A review of PubMed and Medline databases was undertaken with the search phrase "overlapping surgery AND neurosurgery AND outcomes." Data regarding patient demographics, type of neurosurgical procedure, and outcomes and complications were extracted from each study. The principle summary measure was odds ratio (OR) of the association of overlapping versus non-overlapping surgery with outcomes. The literature search yielded a total of 36 studies, of which 5 studies met inclusion criteria and were included in this study. These studies included a total of 25,764 patients undergoing neurosurgical procedures. Overlapping surgery was associated with an increased likelihood of being discharged home (OR = 1.32; 95% CI 1.20 to 1.44; P < 0.001) and a reduced 30-day unexpected return to the operating room (OR = 0.79; 95% CI 0.72 to 0.87; P < 0.001). Overlapping surgery did not significantly affect OR of length of surgery, 30-day mortality, or 30-day readmission. Overlapping neurosurgical procedures were not associated with worse patient outcomes. Additional, prospective studies are needed to further assess the safety overlapping procedures. Copyright © 2018. Published by Elsevier Inc.

Report on nuclear industry quality assurance procedures for safety analysis computer code development and use

International Nuclear Information System (INIS)

Sheron, B.W.; Rosztoczy, Z.R.

1980-08-01

As a result of a request from Commissioner V. Gilinsky to investigate in detail the causes of an error discovered in a vendor Emergency Core Cooling System (ECCS) computer code in March, 1978, the staff undertook an extensive investigation of the vendor quality assurance practices applied to safety analysis computer code development and use. This investigation included inspections of code development and use practices of the four major Light Water Reactor Nuclear Steam Supply System vendors and a major reload fuel supplier. The conclusion reached by the staff as a result of the investigation is that vendor practices for code development and use are basically sound. A number of areas were identified, however, where improvements to existing vendor procedures should be made. In addition, the investigation also addressed the quality assurance (QA) review and inspection process for computer codes and identified areas for improvement

United States Nuclear Regulatory Commission Staff Practice and Procedure Digest

International Nuclear Information System (INIS)

1992-08-01

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

United States Nuclear Regulatory Commission Staff Practice and Procedure Digest

International Nuclear Information System (INIS)

1992-05-01

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

United States Nuclear Regulatory Commission Staff Practice and Procedure Digest

International Nuclear Information System (INIS)

1993-08-01

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

United States Nuclear Regulatory Commission Staff practice and procedure digest

International Nuclear Information System (INIS)

1993-05-01

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

The increasing number of surgical procedures for female genital fistula in England: analysis of Hospital Episode Statistics (HES) data.

Science.gov (United States)

Ismail, S I M F

2015-01-01

The aim of this study was to describe the number and trend of surgical procedures for female genital fistula in England. An online search of Hospital Episode Statistics (HES) data was carried out. Data were available for the 4-year period from 2002-03 until 2005-06. The total number of surgical procedures carried out for female genital fistula steadily increased by 28.7% from 616 in 2002-03 to 793 in 2005-06. The number of surgical procedures performed for rectovaginal fistula exceeded the total number of surgical procedures carried out for vesicovaginal and urethrovaginal fistula in each year of the study period. This pattern needs to be monitored and investigated further.

75 FR 34064 - Manufactured Home Construction and Safety Standards, Test Procedures for Roof Trusses

Science.gov (United States)

2010-06-16

... failure. Failure is rupture, fracture, or excessive yielding. (v) Final recovery phase. Remove 2.0 times... members of the public. Commenters should follow the instructions provided on that site to submit comments... nondestructive testing procedure for roof trusses that permits a lower overall factor of safety to be used in...

Procedures for conducting probabilistic safety assessment for non-reactor nuclear facilities

International Nuclear Information System (INIS)

2002-01-01

A well performed and adequately documented safety assessment of a nuclear facility will serve as a basis to determine whether the facility complies with the safety objectives, principles and criteria as stipulated by the national regulatory body of the country where the facility is in operation. International experience shows that the practices and methodologies used to perform safety assessments and periodic safety re-assessment for non-reactor nuclear facilities differ significantly from county to country. Most developing countries do not have methods and guidance for safety assessment that are prescribed by the regulatory body. Typically the safety evaluation for the facility is based on a case by case assessment. Whilst conservative deterministic analyses are predominantly used as a licensing basis in many countries, recently probabilistic safety assessment (PSA) techniques have been applied as a useful complementary tool to support safety decision making. The main benefit of PSA is to provide insights into the safety aspects of facility design and operation. PSA points up the potential environmental impacts of postulated accidents, including the dominant risk contributors, and enables safety analysts to compare options for reducing risk. In order to advise on how to apply PSA methodology for the safety assessment of non-reactor nuclear facilities, the IAEA organized several consultants meetings, which led to the preparation of this TECDOC. This document is intended as guidance for the conduct of PSA in non-nuclear facilities. The main emphasis here is on the general procedural steps of a PSA that is specific for a non-reactor nuclear facility, rather than the details of the specific methods. The report is directed at technical staff managing or performing such probabilistic assessments and to promote a standardized framework, terminology and form of documentation for these PSAs. It is understood that the level of detail implied in the tasks presented in this

Impact of operator experience and training strategy on procedural outcomes with leadless pacing: Insights from the Micra Transcatheter Pacing Study.

Science.gov (United States)

El-Chami, Mikhael; Kowal, Robert C; Soejima, Kyoko; Ritter, Philippe; Duray, Gabor Z; Neuzil, Petr; Mont, Lluis; Kypta, Alexander; Sagi, Venkata; Hudnall, John Harrison; Stromberg, Kurt; Reynolds, Dwight

2017-07-01

Leadless pacemaker systems have been designed to avoid the need for a pocket and transvenous lead. However, delivery of this therapy requires a new catheter-based procedure. This study evaluates the role of operator experience and different training strategies on procedural outcomes. A total of 726 patients underwent implant attempt with the Micra transcatheter pacing system (TPS; Medtronic, Minneapolis, MN, USA) by 94 operators trained in a teaching laboratory using a simulator, cadaver, and large animal models (lab training) or locally at the hospital with simulator/demo model and proctorship (hospital training). Procedure success, procedure duration, fluoroscopy time, and safety outcomes were compared between training methods and experience (implant case number). The Micra TPS procedure was successful in 99.2% of attempts and did not differ between the 55 operators trained in the lab setting and the 39 operators trained locally at the hospital (P = 0.189). Implant case number was also not a determinant of procedural success (P = 0.456). Each operator performed between one and 55 procedures. Procedure time and fluoroscopy duration decreased by 2.0% (P = 0.002) and 3.2% (P safety outcomes by training method. Among a large group of operators, implantation success was high regardless of experience. While procedure duration and fluoroscopy times decreased with implant number, complications were low and not associated with case number. Procedure and safety outcomes were similar between distinct training methodologies. © 2017 Wiley Periodicals, Inc.

Soil Conservation Service Curve Number method: How to mend a wrong soil moisture accounting procedure?

Science.gov (United States)

Michel, Claude; Andréassian, Vazken; Perrin, Charles

2005-02-01

This paper unveils major inconsistencies in the age-old and yet efficient Soil Conservation Service Curve Number (SCS-CN) procedure. Our findings are based on an analysis of the continuous soil moisture accounting procedure implied by the SCS-CN equation. It is shown that several flaws plague the original SCS-CN procedure, the most important one being a confusion between intrinsic parameter and initial condition. A change of parameterization and a more complete assessment of the initial condition lead to a renewed SCS-CN procedure, while keeping the acknowledged efficiency of the original method.

Safety of type and screen method compared to conventional antiglobulin crossmatch procedures for compatibility testing in Indian setting

Directory of Open Access Journals (Sweden)

Chaudhary Rajendra

2011-01-01

Full Text Available Background: Over the past 30 years, pretransfusion tests have undergone considerable modification. In 1984, AABB recommended that the full cross match could be replaced by an abbreviated cross match in patients with negative antibody screen. However, before implementation of such a policy, issue regarding safety of T & S needs to be evaluated. Objectives: The aim of pretransfusion testing (PTT is to ensure that enough red blood cells (RBCs in the selected red cell components will survive when transfused. Results and Conclusion: We have, therefore in this study; evaluated safety of T & S procedure for PTT in comparison with conventional test tube cross match. The T & S procedure gave a safety of 91.6%. Also, the usefulness of the T & S was shown through the detection of unexpected antibodies in 0.75% (15 out of 2026 of cases.

Required number of records for ASCE/SEI 7 ground-motion scaling procedure

Science.gov (United States)

Reyes, Juan C.; Kalkan, Erol

2011-01-01

The procedures and criteria in 2006 IBC (International Council of Building Officials, 2006) and 2007 CBC (International Council of Building Officials, 2007) for the selection and scaling ground-motions for use in nonlinear response history analysis (RHA) of structures are based on ASCE/SEI 7 provisions (ASCE, 2005, 2010). According to ASCE/SEI 7, earthquake records should be selected from events of magnitudes, fault distance, and source mechanisms that comply with the maximum considered earthquake, and then scaled so that the average value of the 5-percent-damped response spectra for the set of scaled records is not less than the design response spectrum over the period range from 0.2Tn to 1.5Tn sec (where Tn is the fundamental vibration period of the structure). If at least seven ground-motions are analyzed, the design values of engineering demand parameters (EDPs) are taken as the average of the EDPs determined from the analyses. If fewer than seven ground-motions are analyzed, the design values of EDPs are taken as the maximum values of the EDPs. ASCE/SEI 7 requires a minimum of three ground-motions. These limits on the number of records in the ASCE/SEI 7 procedure are based on engineering experience, rather than on a comprehensive evaluation. This study statistically examines the required number of records for the ASCE/SEI 7 procedure, such that the scaled records provide accurate, efficient, and consistent estimates of" true" structural responses. Based on elastic-perfectly-plastic and bilinear single-degree-of-freedom systems, the ASCE/SEI 7 scaling procedure is applied to 480 sets of ground-motions. The number of records in these sets varies from three to ten. The records in each set were selected either (i) randomly, (ii) considering their spectral shapes, or (iii) considering their spectral shapes and design spectral-acceleration value, A(Tn). As compared to benchmark (that is, "true") responses from unscaled records using a larger catalog of ground

Application of a statistical thermal design procedure to evaluate the PWR DNBR safety analysis limits

International Nuclear Information System (INIS)

Robeyns, J.; Parmentier, F.; Peeters, G.

2001-01-01

In the framework of safety analysis for the Belgian nuclear power plants and for the reload compatibility studies, Tractebel Energy Engineering (TEE) has developed, to define a 95/95 DNBR criterion, a statistical thermal design method based on the analytical full statistical approach: the Statistical Thermal Design Procedure (STDP). In that methodology, each DNBR value in the core assemblies is calculated with an adapted CHF (Critical Heat Flux) correlation implemented in the sub-channel code Cobra for core thermal hydraulic analysis. The uncertainties of the correlation are represented by the statistical parameters calculated from an experimental database. The main objective of a sub-channel analysis is to prove that in all class 1 and class 2 situations, the minimum DNBR (Departure from Nucleate Boiling Ratio) remains higher than the Safety Analysis Limit (SAL). The SAL value is calculated from the Statistical Design Limit (SDL) value adjusted with some penalties and deterministic factors. The search of a realistic value for the SDL is the objective of the statistical thermal design methods. In this report, we apply a full statistical approach to define the DNBR criterion or SDL (Statistical Design Limit) with the strict observance of the design criteria defined in the Standard Review Plan. The same statistical approach is used to define the expected number of rods experiencing DNB. (author)

Safety barriers and safety functions a comparison of different applications

International Nuclear Information System (INIS)

Harms-Ringdahl, L.

1998-01-01

A study is being made with the focus on different theories and applications concerning 'safety barriers' and 'safety functions'. One aim is to compare the characteristics of different kinds of safely functions, which can be purpose, efficiency, reliability, weak points etc. A further aim is to summarize how the combination of different barriers are described and evaluated. Of special interest are applications from nuclear and chemical process safety. The study is based on a literature review, interviews and discussions. Some preliminary conclusions are made. For example, it appears to exist a need for better tools to support the design and evaluation of procedures. There are a great number of theoretical models describing safety functions. However, it still appears to be an interest in further development of models, which might give the basis for improved practical tools. (author)

Number of radiological examinations in Finland in 2000

CERN Document Server

Hakanen, A

2002-01-01

STUK (Radiation and Nuclear Safety Authority) collected the number of radiological examinations in Finland in 2000. The work was based on a decree of the ministry of social affairs and health on the medical use of radiation. The work was done in cooperation with the Finnish work group of nomenclature of radiological examinations and procedures and professor Seppo Soimakallio. In 2000, ca. 4.1 million x-ray examinations were made in Finland. In 1984 and in 1995, the numbers were ca. 4.6 million and 4.2 million, respectively, indicating that the total number of x-ray examinations has remained nearly unaltered. The proportions of conventional x-ray examinations, computed tomography examinations, angiographic and interventional procedures were ca. 93.5 %, 5.0 %, 0.9 % and 0.6 %, respectively. The reported number of ultrasound examinations was ca. 0.5 million. The reported number of MRI examinations was ca. 0.1 million.

Updated procedure for the safety evaluation of natural flavor complexes used as ingredients in food

NARCIS (Netherlands)

Cohen, Samuel M.; Eisenbrand, Gerhard; Fukushima, Shoji; Gooderham, Nigel J.; Guengerich, F.P.; Hecht, Stephen S.; Rietjens, Ivonne M.C.M.; Davidsen, Jeanne M.; Harman, Christie L.; Taylor, Sean V.

2018-01-01

An effective and thorough approach for the safety evaluation of natural flavor complexes (NFCs) was published in 2005 by the Expert Panel of the Flavor and Extract Manufacturers Association (FEMA). An updated procedure is provided here, which maintains the essential concepts of the use of the

CENRTC Project number-sign 2F3EOA, OCB A-376, acceptance test procedure

International Nuclear Information System (INIS)

Akerson, A.W.

1995-01-01

This test procedure provides the steps necessary to verify correct functional operation of controls, annunciators, alarms, protective relays and related systems impacted by CENRTC number-sign 2F3E0A, Microwave Transfer Trip Project, modification work performed under work package 6B-93-00041/M. This procedure separates three tests into separate sections: energization of A-376 duplex panel and circuits; SCADA tests; and A-376 local trip tests

An innovative 3-D numerical modelling procedure for simulating repository-scale excavations in rock - SAFETI

Energy Technology Data Exchange (ETDEWEB)

Young, R. P.; Collins, D.; Hazzard, J.; Heath, A. [Department of Earth Sciences, Liverpool University, 4 Brownlow street, UK-0 L69 3GP Liverpool (United Kingdom); Pettitt, W.; Baker, C. [Applied Seismology Consultants LTD, 10 Belmont, Shropshire, UK-S41 ITE Shrewsbury (United Kingdom); Billaux, D.; Cundall, P.; Potyondy, D.; Dedecker, F. [Itasca Consultants S.A., Centre Scientifique A. Moiroux, 64, chemin des Mouilles, F69130 Ecully (France); Svemar, C. [Svensk Karnbranslemantering AB, SKB, Aspo Hard Rock Laboratory, PL 300, S-57295 Figeholm (Sweden); Lebon, P. [ANDRA, Parc de la Croix Blanche, 7, rue Jean Monnet, F-92298 Chatenay-Malabry (France)

2004-07-01

This paper presents current results from work performed within the European Commission project SAFETI. The main objective of SAFETI is to develop and test an innovative 3D numerical modelling procedure that will enable the 3-D simulation of nuclear waste repositories in rock. The modelling code is called AC/DC (Adaptive Continuum/ Dis-Continuum) and is partially based on Itasca Consulting Group's Particle Flow Code (PFC). Results are presented from the laboratory validation study where algorithms and procedures have been developed and tested to allow accurate 'Models for Rock' to be produced. Preliminary results are also presented on the use of AC/DC with parallel processors and adaptive logic. During the final year of the project a detailed model of the Prototype Repository Experiment at SKB's Hard Rock Laboratory will be produced using up to 128 processors on the parallel super computing facility at Liverpool University. (authors)

PGDP [Paducah Gaseous Diffusion Plant]-UF6 handling, sampling, analysis and associated QC/QA and safety related procedures

International Nuclear Information System (INIS)

Harris, R.L.

1987-01-01

This document is a compilation of Paducah Gaseous Diffusion Plant procedures on UF 6 handling, sampling, and analysis, along with associated QC/QA and safety related procedures. It was assembled for transmission by the US Department of Energy to the Korean Advanced Energy Institute as a part of the US-Korea technical exchange program

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

International Nuclear Information System (INIS)

Aldorf, R.

1997-01-01

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

Approaches to document the efficacy and safety of microdermabrasion procedure.

Science.gov (United States)

Spencer, James M; Kurtz, Ellen S

2006-11-01

Microdermabrasion is a popular cosmetic procedure for skin rejuvenation, which is achieved by mechanical abrasion of the skin at a superficial level. The objective was to study the efficacy of microdermabrasion in photoaging and to investigate the compatibility of a cleanser and a lotion with microdermabrasion. Sixteen women underwent microdermabrasion to the face once a week for a total of six treatments. Subjects were also given a personal skin care regimen (cleanser and lotion). Colorimetry values as well as investigator and patients ratings for safety and efficacy were analyzed at various time points and compared to baseline. There were no significant changes in safety and tolerance variables throughout the study. Clinical efficacy variables (fine wrinkles, dullness, pigmentation, and large pores) significantly improved by the third treatment, with further improvement by the end of the study (six treatments). Subjects perceived improvement in facial photoaging variables. Colorimetry showed increased brightness and decreased yellowness of target skin sites on the face throughout the study. Multiple microdermabrasions were effective in significantly improving various facial photoaging variables. The personal skin care regimen used was well tolerated by the subjects.

Management of safety culture

International Nuclear Information System (INIS)

Kavsek, D.

2004-01-01

The strengthening of safety culture in an organization has become an increasingly important issue for nuclear industry. A high level of safety performance is essential for business success in intensely competitive global environment. This presentation offers a discussion of some principles and activities used in enhancing safety performance and appropriate safety behaviour at the Krsko NPP. Over the years a number of events have occurred in nuclear industry that have involved problems in human performance. A review of these and other significant events has identified recurring weaknesses in plant safety culture and policy. Focusing attention on the strengthening of relevant processes can help plants avoid similar undesirable events. The policy of the Krsko NPP is that all employees concerned shall constantly be alert to opportunities to reduce risks to the lowest practicable level and to achieve excellence in plant safety. The most important objective is to protect individuals, society and the environment by establishing and maintaining an effective defense against radiological hazard in the nuclear power plant. It is achieved through the use of reliable structures, components, systems, and procedures, as well as plant personnel committed to a strong safety culture. The elements of safety culture include both organizational and individual aspects. Elements commonly included at the organizational level are senior management commitment to safety, organizational effectiveness, effective communication, organizational learning, and a culture that encourages identification and resolution of safety issues. Elements identified at the individual level include personal accountability, a questioning attitude, communication, procedural adherence, etc.(author)

An approach toward estimating the safety significance of normal and abnormal operating procedures in nuclear power plants

International Nuclear Information System (INIS)

Grant, T.F.; Harris, M.S.

1989-01-01

The Nuclear Regulatory Commission's TMI Action Plan calls for a long-term plan to upgrade operating procedures in nuclear power plants. The scope of Generic Issue Human Factors 4.4, which stems from this requirement, includes the recommendation of improvements in nuclear power plant normal and abnormal operating procedures (NOPs and AOPs) and the implementation of appropriate regulatory action. This paper will describe the objectives, methodologies, and results of a Battelle-conducted value impact assessment to determine the costs and benefits of having the NRC implement regulatory action that would specify requirements for the preparation of acceptable NOPs and AOPs by the Commission's nuclear power plant licensees. The results of this value impact assessment are expressed in terms of ten cost/benefit attributes that can be affected by the NRC regulatory action. Five of these attributes require the calculation of change in public risk that could be expected to result from the action which, in this case, required determining the safety significance of NOPs and AOPs. In order to estimate this safety significance, a multi-step methodology was created that relies on an existing Probabilistic Risk Assessment (PRA) to provide a quantitative framework for modeling the role of operating procedures. The purpose of this methodology is to determine what impact the improvement of NOPs and AOPs would have on public health and safety

Goldmann applanation tonometry over daily disposable contact lens: accuracy and safety of procedure.

Science.gov (United States)

Zeri, Fabrizio; Lupelli, Luigi; Formichella, Paolo; Masci, Carlo; Fletcher, Robert

2007-09-01

To study accuracy and safety, related to sensation (discomfort) and trauma, when using Goldmann applanation tonometry (GAT) on eyes wearing daily disposable soft contact lenses. The intra-ocular pressure (IOP) of 136 normal eyes of 68 subjects was measured by Goldmann tonometer. Measurements were made in one eye with a contact lens (hilafilcon A) without anaesthetic drops and then without the contact lens using one drop of 0.4% oxybuprocaine hydrochloride. Each contact lens used was identical as to back optic zone, back vertex power. Standard Goldmann procedure only was used for the fellow eye of each subject. Subjective sensation (discomfort) responses to both procedures were studied in a subgroup (66 eyes) using a scale of discomfort, from 1 (no sensation) to 5 (highest sensation). Epithelial staining after tonometry was evaluated for this subgroup. No significant differences were found for the IOP with and without contact lens (tcontact lens insertion, tonometry on contact lens and application of topical anaesthetic). Corneal epithelial staining following the standard tonometry procedure was significantly higher than following the procedure with a contact lens (pcontact lens is accurate, compared to the standard procedure and within the IOP's normal range studied here. Also using a contact lens results in less trauma whilst discomfort is similar.

Safety of liver biopsy as a day procedure in Abuth Zaria, Nigeria

International Nuclear Information System (INIS)

Samuel, D.O.; Okuleke, I.P.

2012-01-01

Chronic liver disease (CLD) is an important condition, diagnosed mainly by liver biopsy and is a leading cause of death among the working class group. It is a major burden in sub-Saharan Africa where it leads to hepatocellular carcinoma with a high mortality. This study was a retrospective one undertaken to determine the safety of performing liver biopsy procedure between January 2000 to January 2009 in terms of the frequency of indications and side effects. A total of 279 entries were found out of which 270 (96.77%) had a definitive liver biopsy histology result. The main indication for liver biopsy was chronic viral hepatitis in 150 patients (53.76%) while the commonest complication was the post-procedure pain that was seen in 16 patients (5.7%). The average duration of hospital stay after biopsy was 6.08 +- 0.52 hours. (author)

Revised radiation emergency procedures at Pakistan research reactor PINSTECH

International Nuclear Information System (INIS)

Orfi, S.D.; Javed, M.; Ahmad, S.; Akhtar, K.M.; Mubarak, M.A.

1984-12-01

Necessary procedures have been laid down in this report to meet the radiation emergency at Pakistan Research Reactor PINSTECH. The Nuclear Safety Committee PINSTECH (NSCP) had also recommended a number of improvements in the existing procedures. Revision of the procedures was also considered necessary to incorporate into it new radiation units/limits and new emergency equipment available. Radiation emergency preparedness programme is of continuous nature. Latest developments else-where and local experience contribute to the improvement of the existing arrangements under this programme. (A.B.)

Safety evaluation by living probabilistic safety assessment. Procedures and applications for planning of operational activities and analysis of operating experience

International Nuclear Information System (INIS)

Johanson, Gunnar; Holmberg, J.

1994-01-01

Living Probabilistic Safety Assessment (PSA) is a daily safety management system and it is based on a plant-specific PSA and supporting information systems. In the living use of PSA, plant status knowledge is used to represent actual plant safety status in monitoring or follow-up perspective. The PSA model must be able to express the risk at a given time and plant configuration. The process, to update the PSA model to represent the current or planned configuration and to use the model to evaluate and direct the changes in the configuration, is called living PSA programme. The main purposes to develop and increase the usefulness of living PSA are: Long term safety planning: To continue the risk assessment process started with the basic PSA by extending and improving the basic models and data to provide a general risk evaluation tool for analyzing the safety effects of changes in plant design and procedures. Risk planning of operational activities: To support the operational management by providing means for searching optimal operational maintenance and testing strategies from the safety point of view. The results provide support for risk decision making in the short term or in a planning mode. The operational limits and conditions given by technical specifications can be analyzed by evaluating the risk effects of alternative requirements in order to balance the requirements with respect to operational flexibility and plant economy. Risk analysis of operating experience: To provide a general risk evaluation tool for analyzing the safety effects of incidents and plant status changes. The analyses are used to: identify possible high risk situations, rank the occurred events from safety point of view, and get feedback from operational events for the identification of risk contributors. This report describes the methods, models and applications required to continue the process towards a living use of PSA. 19 tabs, 20 figs

Use of performance curves in estimating number of procedures required to achieve proficiency in coronary angiography

DEFF Research Database (Denmark)

Räder, Sune B E W; Jørgensen, Erik; Bech, Bo

2011-01-01

.001 for all parameters. To approach the experts' level of DAP and contrast media use, trainees need 394 and 588 procedures, respectively. Performance curves showed large individual differences in the development of competence. Conclusion: On average, trainees needed 300 procedures to reach sufficient level...... needed for trainees to reach recommended reference levels was estimated as 226 and 353, for DAP and use of contrast media, respectively. After 300 procedures, trainees' procedure time, fluoroscopy time, DAP, and contrast media volume were significantly higher compared with experts' performance, P ...Background: Current guidelines in cardiology training programs recommend 100-300 coronary angiography procedures for certification. We aimed to assess the number of procedures needed to reach sufficient proficiency. Methods: Procedure time, fluoroscopy time, dose area product (DAP), and contrast...

Procedure for the determination of gap and base ground surface configurations beneath the bottom plate of storage tanks using neutron gauging inspection techniques : including radiation safety procedure and emergency procedure

International Nuclear Information System (INIS)

Jaafar Abdullah

1993-01-01

The procedure is intended for the neutron gauging inspection of gap between the bottom plate and the foundation of bulk storage tanks, which potentially exhibit uneven sinking of the bottom plate and the foundation. Its describes the requirements for the performance of neutron back scattered inspection techniques (or radiometric non-destructive evaluation techniques), using an isotopic neutron source associated with neutron detecting systems, to detect and size the gap between the bottom plate and the foundations as well as to quantify the presence of hydrogenous materials (e.g. oil or water) underneath the bottom plate. This procedure is not only outline the requirements for the neutron gauging inspection, but also describes the requirements which shall be taken into account in formulating the radiation safety and emergency procedures for the neutron gauging inspection works

Safety climate practice in Korean manufacturing industry

International Nuclear Information System (INIS)

Baek, Jong-Bae; Bae, Sejong; Ham, Byung-Ho; Singh, Karan P.

2008-01-01

Safety climate survey was sent to 642 plants in 2003 to explore safety climate practices in the Korean manufacturing plants, especially in hazardous chemical treating plants. Out of 642 plants contacted 195 (30.4%) participated in the surveys. Data were collected by e-mail using SQL-server and mail. The main objective of this study was to explore safety climate practices (level of safety climate and the underlying problems). In addition, the variables that may influence the level of safety climate among managers and workers were explored. The questionnaires developed by health and safety executive (HSE) in the UK were modified to incorporate differences in Korean culture. Eleven important factors were summarized. Internal reliability of these factors was validated. Number of employees in the company varied from less than 30 employees (9.2%) to over 1000 employees (37.4%). Both managers and workers showed generally high level of safety climate awareness. The major underlying problems identified were inadequate health and safety procedures/rules, pressure for production, and rule breaking. The length of employment was a significant contributing factor to the level of safety climate. In this study, participants showed generally high level of safety climate, and length of employment affected the differences in the level of safety climate. Managers' commitment to comply safety rules, procedures, and effective safety education and training are recommended

Safety climate practice in Korean manufacturing industry.

Science.gov (United States)

Baek, Jong-Bae; Bae, Sejong; Ham, Byung-Ho; Singh, Karan P

2008-11-15

Safety climate survey was sent to 642 plants in 2003 to explore safety climate practices in the Korean manufacturing plants, especially in hazardous chemical treating plants. Out of 642 plants contacted 195 (30.4%) participated in the surveys. Data were collected by e-mail using SQL-server and mail. The main objective of this study was to explore safety climate practices (level of safety climate and the underlying problems). In addition, the variables that may influence the level of safety climate among managers and workers were explored. The questionnaires developed by health and safety executive (HSE) in the UK were modified to incorporate differences in Korean culture. Eleven important factors were summarized. Internal reliability of these factors was validated. Number of employees in the company varied from less than 30 employees (9.2%) to over 1000 employees (37.4%). Both managers and workers showed generally high level of safety climate awareness. The major underlying problems identified were inadequate health and safety procedures/rules, pressure for production, and rule breaking. The length of employment was a significant contributing factor to the level of safety climate. In this study, participants showed generally high level of safety climate, and length of employment affected the differences in the level of safety climate. Managers' commitment to comply safety rules, procedures, and effective safety education and training are recommended.

Safety climate practice in Korean manufacturing industry

Energy Technology Data Exchange (ETDEWEB)

Baek, Jong-Bae [Department of Safety Engineering, Chungju National University, Chungju 380-702 (Korea, Republic of); Bae, Sejong [Department of Biostatistics, University of North Texas Health Science Center, 3500 Camp Bowie Boulevard, Fort Worth, TX 76107 (United States)], E-mail: sbae@hsc.unt.edu; Ham, Byung-Ho [Department of Industrial Safety, Ministry of Labor (Korea, Republic of); Singh, Karan P. [Department of Biostatistics, University of North Texas Health Science Center, 3500 Camp Bowie Boulevard, Fort Worth, TX 76107 (United States)

2008-11-15

Safety climate survey was sent to 642 plants in 2003 to explore safety climate practices in the Korean manufacturing plants, especially in hazardous chemical treating plants. Out of 642 plants contacted 195 (30.4%) participated in the surveys. Data were collected by e-mail using SQL-server and mail. The main objective of this study was to explore safety climate practices (level of safety climate and the underlying problems). In addition, the variables that may influence the level of safety climate among managers and workers were explored. The questionnaires developed by health and safety executive (HSE) in the UK were modified to incorporate differences in Korean culture. Eleven important factors were summarized. Internal reliability of these factors was validated. Number of employees in the company varied from less than 30 employees (9.2%) to over 1000 employees (37.4%). Both managers and workers showed generally high level of safety climate awareness. The major underlying problems identified were inadequate health and safety procedures/rules, pressure for production, and rule breaking. The length of employment was a significant contributing factor to the level of safety climate. In this study, participants showed generally high level of safety climate, and length of employment affected the differences in the level of safety climate. Managers' commitment to comply safety rules, procedures, and effective safety education and training are recommended.

Descriptions and models of safety functions - a prestudy

International Nuclear Information System (INIS)

Harms-Ringdahl, L.

1999-09-01

A study has been made with the focus on different theories and applications concerning 'safety functions' and 'barriers'. In this report, a safety function is defined as a technical or organisational function with the aim to reduce probability and/or consequences associated with a hazard. The study contains a limited review of practice and theories related to safety, with a focus on applications from nuclear and industrial safety. The study is based on a literature review and interviews. A summary has been made of definitions and terminology, which shows a large variation. E.g. 'barrier' can have a precise physical and technical meaning, or it can include human, technical and organisational elements. Only a few theoretical models describing safety functions have been found. One section of the report summarises problems related to safety issues and procedures. They concern errors in procedure design and user compliance. A proposal for describing and structuring safety functions has been made. Dimensions in a description could be degree of abstraction, systems level, the different parts of the function, etc. A model for safety functions has been proposed, which includes the division of a safety function in a number connected 'safety function elements'. One conclusion is that there is a potential for improving theories and tools for safety work and procedures. Safety function could be a useful concept in such a development, and advantages and disadvantages with this is discussed. If further work should be done, it is recommended that this is made as a combination of theoretical analysis and case studies

Patient safety improvement programmes for primary care. Review of a Delphi procedure and pilot studies by the LINNEAUS collaboration on patient safety in primary care

Science.gov (United States)

Verstappen, Wim; Gaal, Sander; Esmail, Aneez; Wensing, Michel

2015-01-01

ABSTRACT Background: To improve patient safety it is necessary to identify the causes of patient safety incidents, devise solutions and measure the (cost-) effectiveness of improvement efforts. Objective: This paper provides a broad overview with practical guidance on how to improve patient safety. Methods: We used modified online Delphi procedures to reach consensus on methods to improve patient safety and to identify important features of patient safety management in primary care. Two pilot studies were carried out to assess the value of prospective risk analysis (PRA), as a means of identifying the causes of a patient safety incident. Results: A range of different methods can be used to improve patient safety but they have to be contextually specific. Practice organization, culture, diagnostic errors and medication safety were found to be important domains for further improvement. Improvement strategies for patient safety could benefit from insights gained from research on implementation of evidence-based practice. Patient involvement and prospective risk analysis are two promising and innovative strategies for improving patient safety in primary care. Conclusion: A range of methods is available to improve patient safety, but there is no ‘magic bullet.’ Besides better use of the available methods, it is important to use new and potentially more effective strategies, such as prospective risk analysis. PMID:26339837

Safety procedures in operation of inspection and maintenance of pressure reduction and metering stations

International Nuclear Information System (INIS)

Villas Boas, Ademar Jose; Biesemeyer, Marco Aurelio R.

2000-01-01

Each local Natural Gas Distribution Company in Brazil has its own working procedures for operations of inspection and maintenance on equipment and accessories connected to the gas network. Some of these Companies developed a better elaborated and documented way of working routines, while others only work based on their operators experience. The objective of this work is to create a standard procedure for operations of inspection and maintenance of Pressure Reducing Stations and Metering Stations, mainly the ones concerned to safety aspects. This work has no intention of exhausting all aspects related to this subject but to become the first step to standardize these types of operations among Natural Gas Distribution Companies. (author)

Procedures for initiation, cost-sharing and management of OECD projects in nuclear safety

International Nuclear Information System (INIS)

2002-01-01

The OECD (CSNI) projects aim to produce results relevant for the safe operation of nuclear power plants through international collaborative projects. In general, the projects consist of advanced experimental programmes that are conducted at specialized facilities. At present, the following OECD (CSNI) projects are in operation: - The Halden Project, covering fuel/materials and I and C/Human Factors issues; - The Cabri Project, addressing reactivity transients on high burnup fuels; - The MASCA Project, which deals with in-vessel corium phenomena; - The OLHF Project, dealing with lower head failure mechanisms; - The SETH Project addressing thermal-hydraulics issues, started in 2001; - The MCCI Project on ex-vessel coolability and melt-concrete interaction. There are significant differences among these projects in terms of their motivation, size and scope. The Halden Project and the Cabri Water Loop Project are large undertakings where the host organisations assume full and direct responsibility for the project establishment and administration - as well as for the negotiation with relevant parties on the terms of participation. In the other cases, instead, the NEA secretariat has a more direct responsibility, conferred by the CSNI, in establishing the project technical and financial basis, as well as for its implementation and administration. The objective of this procedure is to provide a common basis for the establishment and management of the OECD projects in the area of nuclear safety. It is a follow-up of a recommendation expressed by the CSNI Bureau during its meeting in October 2001, where the procedures for the establishment and management of the OECD (CSNI) projects in nuclear safety were addressed. While this procedure attempts at defining general guidelines for project initiation, financing and management, one should bear in mind that each project has its own motivation, background and framework. Thus, some degree of flexibility in project structure

CENRTC Project number-sign 2F3EOA, OCB A-386, acceptance test procedure

International Nuclear Information System (INIS)

Akerson, A.W.

1995-01-01

This test procedure provides the steps necessary to verify correct functional operation of controls, annunciators, alarms, protective relays and related systems impacted by CENRTC number-sign 2F3EOA, Microwave Transfer Trip Project, modification work performed under work package 6B-93-00043/M (CENRTC 2F3EOA MWTT OCB A-386 PACKAGE). This procedure separates four tests into separate sections: Energization of A-386 Duplex Panel and Circuits; Local RFL 6750 function tests and start-up; SCADA tests; and A-386 local trip tests

An automatic optimum number of well-distributed ground control lines selection procedure based on genetic algorithm

Science.gov (United States)

Yavari, Somayeh; Valadan Zoej, Mohammad Javad; Salehi, Bahram

2018-05-01

The procedure of selecting an optimum number and best distribution of ground control information is important in order to reach accurate and robust registration results. This paper proposes a new general procedure based on Genetic Algorithm (GA) which is applicable for all kinds of features (point, line, and areal features). However, linear features due to their unique characteristics are of interest in this investigation. This method is called Optimum number of Well-Distributed ground control Information Selection (OWDIS) procedure. Using this method, a population of binary chromosomes is randomly initialized. The ones indicate the presence of a pair of conjugate lines as a GCL and zeros specify the absence. The chromosome length is considered equal to the number of all conjugate lines. For each chromosome, the unknown parameters of a proper mathematical model can be calculated using the selected GCLs (ones in each chromosome). Then, a limited number of Check Points (CPs) are used to evaluate the Root Mean Square Error (RMSE) of each chromosome as its fitness value. The procedure continues until reaching a stopping criterion. The number and position of ones in the best chromosome indicate the selected GCLs among all conjugate lines. To evaluate the proposed method, a GeoEye and an Ikonos Images are used over different areas of Iran. Comparing the obtained results by the proposed method in a traditional RFM with conventional methods that use all conjugate lines as GCLs shows five times the accuracy improvement (pixel level accuracy) as well as the strength of the proposed method. To prevent an over-parametrization error in a traditional RFM due to the selection of a high number of improper correlated terms, an optimized line-based RFM is also proposed. The results show the superiority of the combination of the proposed OWDIS method with an optimized line-based RFM in terms of increasing the accuracy to better than 0.7 pixel, reliability, and reducing systematic

Processes and Procedures for Application of CFD to Nuclear Reactor Safety Analysis

International Nuclear Information System (INIS)

Richard W. Johnson; Richard R. Schultz; Patrick J. Roache; Ismail B. Celik; William D. Pointer; Yassin A. Hassan

2006-01-01

Traditionally, nuclear reactor safety analysis has been performed using systems analysis codes such as RELAP5, which was developed at the INL. However, goals established by the Generation IV program, especially the desire to increase efficiency, has lead to an increase in operating temperatures for the reactors. This increase pushes reactor materials to operate towards their upper temperature limits relative to structural integrity. Because there will be some finite variation of the power density in the reactor core, there will be a potential for local hot spots to occur in the reactor vessel. Hence, it has become apparent that detailed analysis will be required to ensure that local ''hot spots'' do not exceed safety limits. It is generally accepted that computational fluid dynamics (CFD) codes are intrinsically capable of simulating fluid dynamics and heat transport locally because they are based on ''first principles''. Indeed, CFD analysis has reached a fairly mature level of development, including the commercial level. However, CFD experts are aware that even though commercial codes are capable of simulating local fluid and thermal physics, great care must be taken in their application to avoid errors caused by such things as inappropriate grid meshing, low-order discretization schemes, lack of iterative convergence and inaccurate time-stepping. Just as important is the choice of a turbulence model for turbulent flow simulation. Turbulence models model the effects of turbulent transport of mass, momentum and energy, but are not necessarily applicable for wide ranges of flow types. Therefore, there is a well-recognized need to establish practices and procedures for the proper application of CFD to simulate flow physics accurately and establish the level of uncertainty of such computations. The present document represents contributions of CFD experts on what the basic practices, procedures and guidelines should be to aid CFD analysts to obtain accurate estimates

A working procedure for identifying emerging food safety issues at an early stage: Implications for European and international risk management practices

NARCIS (Netherlands)

Marvin, H.J.P.; Kleter, G.A.; Frewer, L.J.; Cope, S.F.; Wentholt, M.T.A.; Rowe, G.

2009-01-01

There is a need for early identification of emerging food safety issues in order to prevent them from developing into health risks. In this paper, various existing methods and procedures which can be used for early identification of safety issues are reviewed, including the monitoring of the

Probabilistic safety analysis procedures guide, Sections 8-12. Volume 2, Rev. 1

International Nuclear Information System (INIS)

McCann, M.; Reed, J.; Ruger, C.; Shiu, K.; Teichmann, T.; Unione, A.; Youngblood, R.

1985-08-01

A procedures guide for the performance of probabilistic safety assessment has been prepared for interim use in the Nuclear Regulatory Commission programs. It will be revised as comments are received, and as experience is gained from its use. The probabilistic safety assessment studies performed are intended to produce probabilistic predictive models that can be used and extended by the utilities and by NRC to sharpen the focus of inquiries into a range of issues affecting reactor safety. The first volume of the guide describes the determination of the probability (per year) of core damage resulting from accident initiators internal to the plant (i.e., intrinsic to plant operation) and from loss of off-site electric power. The scope includes human reliability analysis, a determination of the importance of various core damage accident sequences, and an explicit treatment and display of uncertainties for key accident sequences. This second volume deals with the treatment of the so-called external events including seismic disturbances, fires, floods, etc. Ultimately, the guide will be augmented to include the plant-specific analysis of in-plant processes (i.e., containment performance). This guide provides the structure of a probabilistic safety study to be performed, and indicates what products of the study are valuable for regulatory decision making. For internal events, methodology is treated in the guide only to the extent necessary to indicate the range of methods which is acceptable; ample reference is given to alternative methodologies which may be utilized in the performance of the study. For external events, more explicit guidance is given

The safety assessment of OPR-1000 nuclear power plant for station blackout accident applying the combined deterministic and probabilistic procedure

Energy Technology Data Exchange (ETDEWEB)

Kang, Dong Gu, E-mail: littlewing@kins.re.kr [Korea Institute of Nuclear Safety, 62 Gwahak-ro, Yuseong-gu, Daejeon 305-338 (Korea, Republic of); Korea Advanced Institute of Science and Technology, 291 Daehak-ro, Yuseong-gu, Daejeon 305-701 (Korea, Republic of); Chang, Soon Heung [Korea Advanced Institute of Science and Technology, 291 Daehak-ro, Yuseong-gu, Daejeon 305-701 (Korea, Republic of)

2014-08-15

Highlights: • The combined deterministic and probabilistic procedure (CDPP) was proposed for safety assessment of the BDBAs. • The safety assessment of OPR-1000 nuclear power plant for SBO accident is performed by applying the CDPP. • By estimating the offsite power restoration time appropriately, the SBO risk is reevaluated. • It is concluded that the CDPP is applicable to safety assessment of BDBAs without significant erosion of the safety margin. - Abstract: Station blackout (SBO) is a typical beyond design basis accident (BDBA) and significant contributor to overall plant risk. The risk analysis of SBO could be important basis of rulemaking, accident mitigation strategy, etc. Recently, studies on the integrated approach of deterministic and probabilistic method for nuclear safety in nuclear power plants have been done, and among them, the combined deterministic and probabilistic procedure (CDPP) was proposed for safety assessment of the BDBAs. In the CDPP, the conditional exceedance probability obtained by the best estimate plus uncertainty method acts as go-between deterministic and probabilistic safety assessments, resulting in more reliable values of core damage frequency and conditional core damage probability. In this study, the safety assessment of OPR-1000 nuclear power plant for SBO accident was performed by applying the CDPP. It was confirmed that the SBO risk should be reevaluated by eliminating excessive conservatism in existing probabilistic safety assessment to meet the targeted core damage frequency and conditional core damage probability. By estimating the offsite power restoration time appropriately, the SBO risk was reevaluated, and it was finally confirmed that current OPR-1000 system lies in the acceptable risk against the SBO. In addition, it is concluded that the CDPP is applicable to safety assessment of BDBAs in nuclear power plants without significant erosion of the safety margin.

Safety and efficacy of rivaroxaban compared with warfarin in patients undergoing peripheral arterial procedures.

Science.gov (United States)

Talukdar, Anjan; Wang, S Keisin; Czosnowski, Lauren; Mokraoui, Nassim; Gupta, Alok; Fajardo, Andres; Dalsing, Michael; Motaganahalli, Raghu

2017-10-01

Rivaroxaban is a United States Food and Drug Administration-approved oral anticoagulant for venous thromboembolic disease; however, there is no information regarding the safety and its efficacy to support its use in patients after open or endovascular arterial interventions. We report the safety and efficacy of rivaroxaban vs warfarin in patients undergoing peripheral arterial interventions. This single-institution retrospective study analyzed all sequential patients from December 2012 to August 2014 (21 months) who were prescribed rivaroxaban or warfarin after a peripheral arterial procedure. Our study population was then compared using American College of Chest Physicians guidelines with patients then stratified as low, medium, or high risk for bleeding complications. Statistical analyses were performed using the Student t-test and χ 2 test to compare demographics, readmissions because of bleeding, and the need for secondary interventions. Logistic regression models were used for analysis of variables associated with bleeding complications and secondary interventions. The Fisher exact test was used for power analysis. There were 44 patients in the rivaroxaban group and 50 patients in the warfarin group. Differences between demographics and risk factors for bleeding between groups or reintervention rate were not statistically significant (P = .297). However, subgroup evaluation of the safety profile suggests that patients who were aged ≤65 years and on warfarin had an overall higher incidence of major bleeding (P = .020). Patients who were aged >65 years, undergoing open operation, had a significant risk for reintervention (P = .047) when they received rivaroxaban. Real-world experience using rivaroxaban and warfarin in patients after peripheral arterial procedures suggests a comparable safety and efficacy profile. Subgroup analysis of those requiring an open operation demonstrated a decreased bleeding risk when rivaroxaban was used (in those aged <65�

Laser Safety Inspection Criteria

International Nuclear Information System (INIS)

Barat, K

2005-01-01

A responsibility of the Laser Safety Officer (LSO) is to perform laser safety audits. The American National Standard Z136.1 Safe use of Lasers references this requirement in several sections: (1) Section 1.3.2 LSO Specific Responsibilities states under Hazard Evaluation, ''The LSO shall be responsible for hazards evaluation of laser work areas''; (2) Section 1.3.2.8, Safety Features Audits, ''The LSO shall ensure that the safety features of the laser installation facilities and laser equipment are audited periodically to assure proper operation''; and (3) Appendix D, under Survey and Inspections, it states, ''the LSO will survey by inspection, as considered necessary, all areas where laser equipment is used''. Therefore, for facilities using Class 3B and or Class 4 lasers, audits for laser safety compliance are expected to be conducted. The composition, frequency and rigueur of that inspection/audit rests in the hands of the LSO. A common practice for institutions is to develop laser audit checklists or survey forms. In many institutions, a sole Laser Safety Officer (LSO) or a number of Deputy LSO's perform these audits. For that matter, there are institutions that request users to perform a self-assessment audit. Many items on the common audit list and the associated findings are subjective because they are based on the experience and interest of the LSO or auditor in particular items on the checklist. Beam block usage is an example; to one set of eyes a particular arrangement might be completely adequate, while to another the installation may be inadequate. In order to provide more consistency, the National Ignition Facility Directorate at Lawrence Livermore National Laboratory (NIF-LLNL) has established criteria for a number of items found on the typical laser safety audit form. These criteria are distributed to laser users, and they serve two broad purposes: first, it gives the user an expectation of what will be reviewed by an auditor, and second, it is an

Flaws found in Los Alamos safety procedures

Science.gov (United States)

Gwynne, Peter

2017-12-01

A US government panel on nuclear safety has discovered a series of safety issues at the Los Alamos National Laboratory, concluding that government oversight of the lab's emergency preparation has been ineffective.

Efficiency and Safety of One-Step Procedure Combined Laparoscopic Cholecystectomy and Eretrograde Cholangiopancreatography for Treatment of Cholecysto-Choledocholithiasis: A Randomized Controlled Trial.

Science.gov (United States)

Liu, Zhiyi; Zhang, Luyao; Liu, Yanling; Gu, Yang; Sun, Tieliang

2017-11-01

We aimed to evaluate the efficiency and safety of one-step procedure combined endoscopic retrograde cholangiopancreatography (ERCP) and laparoscopic cholecystectomy (LC) for treatment of patients with cholecysto-choledocholithiasis. A prospective randomized study was performed on 63 consecutive cholecysto-choledocholithiasis patients during 2008 and 2011. The efficiency and safety of one-step procedure was assessed by comparing the two-step LC with ERCP + endoscopic sphincterotomy (EST). Outcomes including intraoperative features, postoperative features (length of stay and postoperative complications) were evaluated. One- or two-step procedure of LC with ERCP + EST was successfully performed in all patients, and common bile duct stones were completely removed. Statistical analyses showed that length of stay and pulmonary infection rate were significantly lower in the test group compared with that in the control group (P 0.05). The one-step procedure of LC with ERCP + EST is superior to the two-step procedure for treatment of patients with cholecysto-choledocholithiasis regarding to the reduced hospital stay and inhibited occurrence of pulmonary infections. Compared with two-step procedure, one-step procedure of LC with ERCP + EST may be a superior option for cholecysto-choledocholithiasis patients treatment regarding to hospital stay and pulmonary infections.

Procedures for self-assessment of operational safety

International Nuclear Information System (INIS)

1997-08-01

Self-assessment processes have been continuously developed by nuclear organizations, including nuclear power plants. Currently, the nuclear industry and governmental organizations are showing an increasing interest in the implementation of this process as an effective way for improving safety performance. Self-assessment involves the use of different types of tools and mechanisms to assist the organizations in assessing their own safety performance against given standards. This helps to enhance the understanding of the need for improvements, the feeling of ownership in achieving them and and the safety culture as a whole. The concepts developed in this report present the basic approach to self-assessment taking into consideration experience gained during Operational Safety Review Team (OSART) missions, from organizations and utilities which have successfully implemented parts of a self-assessment programme and from meetings organized to discuss the subject

Safety handbook

International Nuclear Information System (INIS)

1990-01-01

The purpose of the Australian Nuclear Science and Technology Organization's Safety Handbook is to outline simply the fundamental procedures and safety precautions which provide an appropriate framework for safe working with any potential hazards, such as fire and explosion, welding, cutting, brazing and soldering, compressed gases, cryogenic liquids, chemicals, ionizing radiations, non-ionising radiations, sound and vibration, as well as safety in the office. It also specifies the organisation for safety at the Lucas Heights Research Laboratories and the responsibilities of individuals and committees. It also defines the procedures for the scrutiny and review of all operations and the resultant setting of safety rules for them. ills

Procedures for controlling the risks of reliability, safety, and availability of technical systems

International Nuclear Information System (INIS)

1987-01-01

The reference book covers four sections. Apart from the fundamental aspects of the reliability problem, of risk and safety and the relevant criteria with regard to reliability, the material presented explains reliability in terms of maintenance, logistics and availability, and presents procedures for reliability assessment and determination of factors influencing the reliability, together with suggestions for systems technical integration. The reliability assessment consists of diagnostic and prognostic analyses. The section on factors influencing reliability discusses aspects of organisational structures, programme planning and control, and critical activities. (DG) [de

Development of ISA procedure for uranium fuel fabrication and enrichment facilities: overview of ISA procedure and its application

International Nuclear Information System (INIS)

Yamate, Kazuki; Yamada, Takashi; Takanashi, Mitsuhiro; Sasaki, Noriaki

2013-01-01

Integrated Safety Analysis (ISA) procedure for uranium fuel fabrication and enrichment facilities has been developed for aiming at applying risk-informed regulation to these uranium facilities. The development has carried out referring to the ISA (NUREG-1520) by the Nuclear Regulatory Commission (NRC). The paper presents purpose, principles and activities for the development of the ISA procedure, including Risk Level (RL) matrix and grading evaluation method of IROFS (Items Relied on for Safety), as well as general description and features of the procedure. Also described in the paper is current status in application of risk information from the ISA. Japanese four licensees of the uranium facilities have been conducting ISA for their representative processes using the developed procedure as their voluntary safety activities. They have been accumulating experiences and knowledge on the ISA procedure and risk information through the field activities. NISA (Nuclear and Industrial Safety Agency) and JNES (Japan Nuclear Energy Safety Organization) are studying how to use such risk information for the safety regulation of the uranium facilities, taking into account the licensees' experiences and knowledge. (authors)

Post Chernobyl safety review at Ontario Hydro

International Nuclear Information System (INIS)

Frescura, G.M.; Luxat, J.C.; Jobe, C.

1991-01-01

It is generally recognized that the Chernobyl Unit 4 accident did not reveal any new phenomena which had not been previously identified in safety analyses. However, the accident provided a tragic reminder of the potential consequences of reactivity initiated accidents (RIAs) and stimulated nuclear plant operators to review their safety analyses, operating procedures and various operational and management aspects of nuclear safety. Concerning Ontario Hydro, the review of the accident performed by the corporate body responsible for nuclear safety policy and by the Atomic Energy Control Board (the Regulatory Body) led to a number of specific recommendations for further action by various design, analysis and operation groups. These recommendations are very comprehensive in terms of reactor safety issues considered. The general conclusion of the various studies carried out in response to the recommendations, is that the CANDU safety design and the procedures in place to identify and mitigate the consequences of accidents are adequate. Improvements to the reliability of the Pickering NGSA shutdown system and to some aspects of safety management and staff training, although not essential, are possible and would be pursued. In support of this conclusion, the paper describes some of the studies that were carried out and discusses the findings. The first part of the paper deals with safety design aspects. While the second is concerned with operational aspects

Pleural procedures and patient safety: a national BTS audit of practice.

Science.gov (United States)

Hooper, Clare E; Welham, Sally A; Maskell, Nick A

2015-02-01

The BTS pleural procedures audit collected data over a 2-month period in June and July 2011. In contrast with the 2010 audit, which focussed simply on chest drain insertions, data on all pleural aspirations and local anaesthetic thoracoscopy (LAT) was also collected. Ninety hospitals submitted data, covering a patient population of 33 million. Twenty-one per cent of centres ran a specialist pleural disease clinic, 71% had a nominated chest drain safety lead, and 20% had thoracic surgery on site. Additionally, one-third of centres had a physician-led LAT service. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://group.bmj.com/group/rights-licensing/permissions.

United States Nuclear Regulatory Commission Staff practice and procedure digest

International Nuclear Information System (INIS)

1991-12-01

This sixth edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to December 31, 1990 interpreting the NRC's Rules of Practice in 10 CFR Part 2. This sixth edition replaces in part earlier editions and revisions and includes appropriate changes reflecting the amendments to the Rules of Practice effective through December 31, 1990

An engineer-constructor's view of nuclear power plant safety

International Nuclear Information System (INIS)

Landis, J.W.; Jacobs, S.B.

1984-01-01

At SWEC we have been involved in the development of safety features of nuclear power plants ever since we served as the engineer-constructur for the first commerical nuclear power station at Shippingport, Pennsylvania, in the 1950s. Our personnel have pioneered a number of safety innovations and improvements. Among these innovations is the subatmospheric containment for pressurized water reactor (PWR) power plants. This type of containment is designed so that leakage will terminate within 1 to 2 hours of the worst postulated loss of coolant accident. Other notable contributions include first use of reinforced-concrete atmospheric containments for PWR power plants and of reinforced-concrete, vapor-suppression containments for boiling water reactor (BWR) power plants. Both concepts meet rigorous U.S. safety requirements. SWEC has performed a substantial amount of work on developing standardized plant designs and has developed standardized engineering and construction techniques and procedures. Standardization concepts are being developed in Canada, France, USSR, and Germany, as well as in the United States. The West German convoy concept, which involves developing a number of standardized plants in a common effort, has been quite successful. We believe standardization contributes to safety in a number of ways. Use of standardized designs, procedures, techniques, equipment, and methods increases efficiency and results in higher quality. Standardization also reduces the design variations with which plant operators, emergency teams, and regulatory personnel must be familiar, thus increasing operator capability, and permits specialized talents to be focused on important safety considerations. (orig./RW)

Update on radiation safety and dose reduction in pediatric neuroradiology

International Nuclear Information System (INIS)

Mahesh, Mahadevappa

2015-01-01

The number of medical X-ray imaging procedures is growing exponentially across the globe. Even though the overall benefit from medical X-ray imaging procedures far outweighs any associated risks, it is crucial to take all necessary steps to minimize radiation risks to children without jeopardizing image quality. Among the X-ray imaging studies, except for interventional fluoroscopy procedures, CT studies constitute higher dose and therefore draw considerable scrutiny. A number of technological advances have provided ways for better and safer CT imaging. This article provides an update on the radiation safety of patients and staff and discusses dose optimization in medical X-ray imaging within pediatric neuroradiology. (orig.)

Update on radiation safety and dose reduction in pediatric neuroradiology

Energy Technology Data Exchange (ETDEWEB)

Mahesh, Mahadevappa [Johns Hopkins University School of Medicine, The Russell H. Morgan Department of Radiology and Radiological Science, Baltimore, MD (United States)

2015-09-15

The number of medical X-ray imaging procedures is growing exponentially across the globe. Even though the overall benefit from medical X-ray imaging procedures far outweighs any associated risks, it is crucial to take all necessary steps to minimize radiation risks to children without jeopardizing image quality. Among the X-ray imaging studies, except for interventional fluoroscopy procedures, CT studies constitute higher dose and therefore draw considerable scrutiny. A number of technological advances have provided ways for better and safer CT imaging. This article provides an update on the radiation safety of patients and staff and discusses dose optimization in medical X-ray imaging within pediatric neuroradiology. (orig.)

Writer`s guide for technical procedures

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-12-01

A primary objective of operations conducted in the US Department of Energy (DOE) complex is safety. Procedures are a critical element of maintaining a safety envelope to ensure safe facility operation. This DOE Writer`s Guide for Technical Procedures addresses the content, format, and style of technical procedures that prescribe production, operation of equipment and facilities, and maintenance activities. The DOE Writer`s Guide for Management Control Procedures and DOE Writer`s Guide for Emergency and Alarm Response Procedures are being developed to assist writers in developing nontechnical procedures. DOE is providing this guide to assist writers across the DOE complex in producing accurate, complete, and usable procedures that promote safe and efficient operations that comply with DOE orders, including DOE Order 5480.19, Conduct of Operations for DOE Facilities, and 5480.6, Safety of Department of Energy-Owned Nuclear Reactors.

Comparative efficacy and safety of the left versus right radial approach for percutaneous coronary procedures: a meta-analysis including 6870 patients

Directory of Open Access Journals (Sweden)

S.L. Xia

2015-08-01

Full Text Available The radial approach is widely used in the treatment of patients with coronary artery disease. We conducted a meta-analysis of published results on the efficacy and safety of the left and right radial approaches in patients undergoing percutaneous coronary procedures. A systematic search of reference databases was conducted, and data from 14 randomized controlled trials involving 6870 participants were analyzed. The left radial approach was associated with significant reductions in fluoroscopy time [standardized mean difference (SMD=-0.14, 95% confidence interval (CI=-0.19 to -0.09; P<0.00001] and contrast volume (SMD=-0.07, 95%CI=-0.12 to -0.02; P=0.009. There were no significant differences in rate of procedural failure of the left and the right radial approaches [risk ratios (RR=0.98; 95%CI=0.77-1.25; P=0.88] or procedural time (SMD=-0.05, 95%CI=0.17-0.06; P=0.38. Tortuosity of the subclavian artery (RR=0.27, 95%CI=0.14-0.50; P<0.0001 was reported more frequently with the right radial approach. A greater number of catheters were used with the left than with the right radial approach (SMD=0.25, 95%CI=0.04-0.46; P=0.02. We conclude that the left radial approach is as safe as the right radial approach, and that the left radial approach should be recommended for use in percutaneous coronary procedures, especially in percutaneous coronary angiograms.

Procedures for conducting probabilistic safety assessments of nuclear power plants (level 2). Accident progression, containment analysis and estimation of accident source terms

International Nuclear Information System (INIS)

1995-01-01

The present publication on Level 2 PSA is based on a compilation and review of practices in various Member States. It complements Safety Series No. 50-P-4, issued in 1992, on Procedures for Conducting Probabilistic Safety Assessments of Nuclear Power Plants (Level 1). Refs, figs and tabs

United States Nuclear Regulatory Commission Staff Practice and Procedure Digest

International Nuclear Information System (INIS)

1990-11-01

This Revision 8 of the fifth edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to June 30, 1990 interpreting the NRC's Rules of Practice in 10 CFR Part 2. This Revision 8 replaces in part earlier editions and revisions and includes appropriate changes reflecting the amendments to the Rules of Practice effective through June 30, 1990

Upgraded safety analysis document including operations policies, operational safety limits and policy changes. Revision 2

International Nuclear Information System (INIS)

Batchelor, K.

1996-03-01

The National Synchrotron Light Source Safety Analysis Reports (1), (2), (3), BNL reports number-sign 51584, number-sign 52205 and number-sign 52205 (addendum) describe the basic Environmental Safety and Health issues associated with the department's operations. They include the operating envelope for the Storage Rings and also the rest of the facility. These documents contain the operational limits as perceived prior or during construction of the facility, much of which still are appropriate for current operations. However, as the machine has matured, the experimental program has grown in size, requiring more supervision in that area. Also, machine studies have either verified or modified knowledge of beam loss modes and/or radiation loss patterns around the facility. This document is written to allow for these changes in procedure or standards resulting from their current mode of operation and shall be used in conjunction with the above reports. These changes have been reviewed by NSLS and BNL ES and H committee and approved by BNL management

Pacemaker replacement in nonagenarians: Procedural safety and long-term follow-up.

Science.gov (United States)

Loirat, Aurélie; Fénéon, Damien; Behaghel, Albin; Behar, Nathalie; Le Helloco, Alain; Mabo, Philippe; Daubert, Jean-Claude; Leclercq, Christophe; Martins, Raphaël P

2015-01-01

The rate of pacemaker implantation is rising. Given that the life expectancy of the population is projected to increase, a large number of elderly patients are likely to be implanted in the future. As pacemaker batteries can last for 8-10years, an increasing number of pacemaker recipients will require replacement of their devices when they become nonagenarians. To analyse the short- and long-term outcomes after device replacement in nonagenarians. Patients aged≥90years referred to a tertiary centre for pacemaker replacement from January 2004 to July 2014 were included retrospectively. Clinical follow-up data were obtained from clinical visits or telephone interviews with patients or their families. The primary clinical endpoint was total mortality. Secondary endpoints included early and delayed procedure-related complications and predictive risk factors for total mortality. Sixty-two patients were included (mean age 93.3±2.9years at time of pacemaker replacement). Mean procedure duration was 35.7±17.2minutes. Mean hospital stay was 2.2±1.1days. One patient died from a perioperative complication. Thirty-seven patients (59.7%) died during a median follow-up of 22.1months (interquartile range, 11.8-39.8months). Survival rates were 84.2% (95% confidence interval [CI] 71.8-91.5%) at 1year, 66.9% (95% CI 51.8-78.2%) at 2years and 22.7% (95% CI 10.6-37.7%) at 5years. Atrial fibrillation (hazard ratio 2.47, 95% CI 1.1-5.6) and non-physiological pacing (i.e. VVI pacing in patients in sinus rhythm) (hazard ratio 2.20, 95% CI 1.0-4.9) were predictors of mortality. Pacemaker replacement in nonagenarians is a safe and straightforward procedure. These data suggest that procedures can be performed securely in this old and frail population, with patients living for a median of 30months afterwards. Copyright © 2015 Elsevier Masson SAS. All rights reserved.

Safety culture development in nuclear electric plc

International Nuclear Information System (INIS)

Gibson, G.P.; Low, M.B.J.

1995-01-01

Nuclear Electric plc (NE) has always given the highest priority to safety. However, past emphasis has been directed towards ensuring safety thorough engineering design and hazard control procedures. Whilst the company did achieve high safety standards, particularly with respect to accidents, it was recognized that further improvements could be obtained. Analysis of the safety performance across a wide range of industries showed that the key to improving safety performance lay in developing a strong safety culture within the company. Over the last five years, NE has made great strides to improve its safety culture. This has resulted in a considerable improvement in its measured safety performance indicators, such as the number of incidents at international nuclear event scale (INES) rating 1, the number of lost time accidents and the collective radiation dose. However, despite this success, the company is committed to further improvement and a means by which this process becomes self-sustaining. In this way the company will achieve its prime goal, to ''ensure the safety of people, plant and the environment''. The paper provides an overview of the development of safety culture in NE since its formation in November 1989. It describes the research and international developments that have influenced the company's understanding of safety culture, the key initiatives that the company has undertaken to enhance its safety culture and the future initiatives being considered to ensure continual improvement. (author). 5 refs, 2 figs, 2 tabs

PGSFR Core Thermal Design Procedure to Evaluate the Safety Margin

Energy Technology Data Exchange (ETDEWEB)

Choi, Sun Rock; Kim, Sang-Ji [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2014-10-15

The Korea Atomic Energy Research Institute (KAERI) has performed a SFR design with the final goal of constructing a prototype plant by 2028. The main objective of the SFR prototype plant is to verify the TRU metal fuel performance, reactor operation, and transmutation ability of high-level wastes. The core thermal design is to ensure the safe fuel performance during the whole plant operation. Compared to the critical heat flux in typical light water reactors, nuclear fuel damage in SFR subassemblies arises from a creep induced failure. The creep limit is evaluated based on the maximum cladding temperature, power, neutron flux, and uncertainties in the design parameters, as shown in Fig. 1. In this work, the core thermal design procedures are compared to verify the present PGSFR methodology based on the nuclear plant design criteria/guidelines and previous SFR thermal design methods. The PGSFR core thermal design procedure is verified based on the nuclear plant design criteria/guidelines and previous methods in LWRs and SFRs. The present method aims to directly evaluate the fuel cladding failure and to assure more safety margin. The 2 uncertainty is similar to 95% one-side tolerance limit of 1.96 in LWRs. The HCFs, ITDP, and MCM reveal similar uncertainty propagation for cladding midwall temperature for typical SFR conditions. The present HCFs are mainly employed from the CRBR except the fuel-related uncertainty such as an incorrect fuel distribution. Preliminary PGSFR specific HCFs will be developed by the end of 2015.

Results of a national survey on nuclear medicine procedures

International Nuclear Information System (INIS)

Curti, A.R.; Gatica, N.A.; Melis, H.J.

1998-01-01

Full text: In 1997, the Nuclear Regulatory Authority of Argentina carried out a compilation of data on radiopharmaceuticals administered to patients in nuclear medicine procedures. Its aim was to get information on the radiopharmaceuticals that are used in different procedures and the activity administered to the patient, to assess the radiation exposure of the population and to contribute to a global survey of medical radiation usage and exposures conducted by the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR), by sending information of the country. The data compiled were analysed, and for the most frequent procedures, the mean activity administered, the standard deviation, the distribution of the number of procedures for different age groups, sex and radiopharmaceuticals were assessed. The radiation exposure for children and adults was estimated. For the main diagnostic examinations, the results of the survey were compared with specific values published in the Basic Safety Standards of the International Atomic Energy Agency (Safety Series No. 115, 1996). As a conclusion, it may be point out the importance of continuing with the compilation of this kind of information in order to identify emerging trends on the use of nuclear medicine procedures in Argentina and the activity of radiopharmaceuticals administered to the patients. (author) [es

Hospitals with greater diversities of physiologically complex procedures do not achieve greater surgical growth in a market with stable numbers of such procedures.

Science.gov (United States)

Dexter, Franklin; Epstein, Richard H; Lubarsky, David A

2018-05-01

Although having a large diversity of types of procedures has a substantial operational impact on the surgical suites of hospitals, the strategic importance is unknown. In the current study, we used longitudinal data for all hospitals and patient ages in the State of Florida to evaluate whether hospitals with greater diversity of types of physiologically complex major therapeutic procedures (PCMTP) also had greater rates of surgical growth. Observational cohort study. 1479 combinations of hospitals in the State of Florida and fiscal years, 2008-2015. The types of International Classification of Diseases, Ninth revision, Clinical Modification (ICD-9-CM) procedures studied were PCMT, defined as: a) major therapeutic procedure; b) >7 American Society of Anesthesiologists base units; and c) performed during a hospitalization with a Diagnosis Related Group with a mean length of stay ≥4.0days. The number of procedures of each type of PCMTP commonly performed at each hospital was calculated by taking 1/Herfindahl index (i.e., sum of the squares of the proportions of all procedures of each type of PCMTP). Over the 8 successive years studied, there was no change in the number of PCMTP being performed (Kendall's τ b =-0.014±0.017 [standard error], P=0.44; N=1479 hospital×years). Busier and larger hospitals commonly performed more types of PCMTP, respectively categorized based on performed PCMTP (τ=0.606±0.017, P<0.0001) or hospital beds (τ=0.524±0.017, P<0.0001). There was no association between greater diversity of types of PCMTP commonly performed and greater annual growth in numbers of PCMTP (τ=0.002±0.019, P=0.91; N=1295 hospital×years). Conclusions were the same with multiple sensitivity analyses. Post hoc, it was recognized that hospitals performing a greater diversity of PCMTP were more similar to the aggregate of other hospitals within the same health district (τ=0.550±0.017, P<0.0001). During a period with no overall growth in PCMTP, hospitals with

Endoscopic sutured gastroplasty: procedure evolution from first-in-man cases through current technique.

Science.gov (United States)

Kumar, Nitin; Abu Dayyeh, Barham K; Lopez-Nava Breviere, Gontrand; Galvao Neto, Manoel P; Sahdala, Nicole P; Shaikh, Sohail N; Hawes, Robert H; Gostout, Christopher J; Goenka, Mahesh K; Orillac, Jorge R; Alvarado, Alonso; Jirapinyo, Pichamol; Zundel, Natan; Thompson, Christopher C

2018-04-01

Endoscopic sutured gastroplasty (ESG) has evolved over time. With the advent of full-thickness endoscopic suturing, an efficient technique for ESG was developed and refined. This prospective first-in-man trial started in April 2012 and represents the first use of full-thickness endoscopic suturing for primary obesity therapy. The trial focused on procedure development, reproducibility, safety, and short-term efficacy. The trial was performed at centers in five countries, in three phases. Phase I was evaluation of safety and technical feasibility of various procedure techniques; stitch patterns and sequences were assessed for efficiency, safety, and feasibility. Phase II entailed continued procedure refinement to establish a standardized technique. Phase III entailed evaluation of technical feasibility and weight loss outcomes in 77 patients; the procedure was performed using the standardized technique, and there was no procedure development. Data were prospectively collected into a registry. In Phase I, the procedure was created and modified to improve time efficiency. Safety and technical feasibility were established, and short-term weight loss was demonstrated. In Phase II, a number of stitch patterns were attempted, and the stitch pattern was modified and finalized. 22 patients were included, and 1-year total weight loss was 17.3 ± 2.6%. In Phase III, conformity with the final technique was high. 77 patients were included, with a mean BMI of 36.1 ± 0.6 kg/m 2 . Mean weight loss was 16.0 ± 0.8% at 6 months and 17.4 ± 1.2% at 12 months (n = 44). Postprocedural nausea, vomiting, and epigastric pain were frequently reported; there were no reported significant adverse events post-procedure or during the follow-up period. Following a methodical procedure development phase, ESG demonstrated safety and short-term efficacy in this trial. The procedure also achieved meaningful weight loss during the follow-up period.

Involving patients in patient safety programmes: A scoping review and consensus procedure by the LINNEAUS collaboration on patient safety in primary care.

Science.gov (United States)

Trier, Hans; Valderas, Jose M; Wensing, Michel; Martin, Helle Max; Egebart, Jonas

2015-09-01

Patient involvement has only recently received attention as a potentially useful approach to patient safety in primary care. To summarize work conducted on a scoping review of interventions focussing on patient involvement for patient safety; to develop consensus-based recommendations in this area. Scoping review of the literature 2006-2011 about methods and effects of involving patients in patient safety in primary care identified evidence for previous experiences of patient involvement in patient safety. This information was fed back to an expert panel for the development of recommendations for healthcare professionals and policy makers. The scoping review identified only weak evidence in support of the effectiveness of patient involvement. Identified barriers included a number of patient factors but also the healthcare workers' attitudes, abilities and lack of training. The expert panel recommended the integration of patient safety in the educational curricula for healthcare professionals, and expected a commitment from professionals to act as first movers by inviting and encouraging the patients to take an active role. The panel proposed a checklist to be used by primary care clinicians at the point of care for promoting patient involvement. There is only weak evidence on the effectiveness of patient involvement in patient safety. The recommendations of the panel can inform future policy and practice on patient involvement in safety in primary care.

Quality procedure management for improved nuclear safety

International Nuclear Information System (INIS)

Forzano, P.; Castagna, P.

1995-01-01

Emergency Operating Procedures and Accident Management Procedures are the next step in the computerization of NPP control rooms. Different improvements are presently conceivable for this operator aid tool, and research activities are in development. Undergoing activities regard especially formal aspects of knowledge representation, Human-Machine interface and procedure life cycle management. These aspects have been investigated deeply by Ansaldo, and partially incorporated in the DIAM prototype. Nuclear Power Plant Procedures can be seen from essentially two viewpoints: the process and the information management. From the first point of view, it is important to supply the knowledge apt to solve problems connected with the control of the process, from the second one the focus of attention is on the knowledge representation, its structure, elicitation and maintenance, and formal quality assurance. These two aspects of procedure representation can be considered and solved separately. In particular, methodological, formal and management issues require long and tedious activities, that in most cases constitute a great barrier for procedures development and upgrade. To solve these problems, Ansaldo is developing DIAM, a wide integrated tool for procedure management to support in procedure writing, updating, usage, and documentation. One of the most challenging features of DIAM is AUTO-LAY, a CASE sub-tool that, in a complete automatical way, structures parts or complete flow diagram. This is the feature that is partial present in some other CASE products, that, anyway, do not allow complex graph handling and isomorphism between video and paper representation. AUTO-LAY has the unique prerogative to draw graphs of any complexity to section them in pages, and to automatically compose a document. This has been recognized in the literature as the most important a second-generation CASE improvement. (Author) 9 Figs., 5 Refs

Procedures to relate the NII safety assessment principles for nuclear reactors to risk

CERN Document Server

Kelly, G N; Hemming, C R

1985-01-01

Within the framework of the Public Inquiry into the proposed pressurised water reactor (PWR) at Sizewell, estimates were made of the levels of individual and societal risk from a PWR designed in a manner which would conform to the safety assessment principles formulated by the Nuclear Installations Inspectorate (NII). The procedures used to derive these levels of risk are described in this report. The opportunity has also been taken to revise the risk estimates made at the time of the Inquiry by taking account of additional data which were not then available, and to provide further quantification of the likely range of uncertainty in the predictions. This re-analysis has led to small changes in the levels of risk previously evaluated, but these are not sufficient to affect the broad conclusions reached before. For a reactor just conforming to the NII safety assessment principles a maximum individual risk of fatal cancer of about 10 sup - sup 6 per year of reactor operation has been estimated; the societal ris...

The procedures used to review safety analysis reports for packagings submitted to the US Department of Energy for certification

International Nuclear Information System (INIS)

Popper, G.F.; Raske, D.T.; Turula, P.

1988-01-01

This paper presents an overview of the procedures used at the Argonne National Laboratory (ANL) to review Safety Analysis Reports for Packagings (SARPs) submitted to the US Department of Energy (DOE) for issuance of a Certificate of Compliance. Prior to certification and shipment of a packaging for the transport of radioactive materials, a SARP must be prepared describing the design, contents, analyses, testing, and safety features of the packaging. The SARP must be reviewed to ensure that the specific packaging meets all DOE orders and federal regulations for safe transport. The ANL SARP review group provides an independent review and evaluation function for the DOE to ensure that the packaging meets all the prescribed requirements. This review involves many disciplines and includes evaluating the general information, drawings, construction details, operating procedures, maintenance and test programs, and the quality assurance plan for compliance with requirements. 14 refs., 6 figs

Reactor safety

International Nuclear Information System (INIS)

Butz, H.P.; Heuser, F.W.; May, H.

1985-01-01

The paper comprises an introduction into nuclear physics bases, the safety concept generally speaking, safety devices of pwr type reactors, accident analysis, external influences, probabilistic safety assessment and risk studies. It further describes operational experience, licensing procedures under the Atomic Energy Law, research in reactor safety and the nuclear fuel cycle. (DG) [de

Effect of aspect ratio and number of meshes on convergence of steady-state flow calculation using Newton-Raphson iterative procedure

International Nuclear Information System (INIS)

Shimizu, Takeshi

1997-01-01

In this paper, we discuss the stability of the convergence of a nonlinear iteration procedure which may be affected by a large number of numerical factors in a complicated way. A numerical parallel channel flow problem is solved using the finite element method and the Newton-Raphson iteration procedure. The numerical factors, on which we focus attention in this study, are the aspect ratio of the channel and the number of divided meshes. We propose a nondimensional value, which is obtained from the Reynolds number, the aspect ratio and the number of meshes. The results of the numerical experiment show that the threshold of divergence in the iteration is indicated clearly by the present nondimensional value. (author)

Probabilistic safety evaluation: Development of procedures with applications on components used in nuclear power plants

International Nuclear Information System (INIS)

Dillstroem, P.

2000-12-01

A probabilistic procedure has been developed by SAQ Kontroll AB to calculate two different failure probabilities, P F : Probability of failure, defect size given by NDT/NDE. Probability of failure, defect not detected by NDT/NDE. Based on the procedure, SAQ Kontroll AB has developed a computer program PROPSE (PRObabilistic Program for Safety Evaluation). Within PROPSE, the following features are implemented: Two different algorithms to calculate the probability of failure are included: Simple Monte Carlo Simulation (MCS), with an error estimate on P F . First-Order Reliability Method (FORM), with sensitivity factors using the most probable point of failure in a standard normal space. Using these factors, it is possible to rank the parameters within an analysis. Estimation of partial safety factors, given an input target failure probability and characteristic values for fracture toughness, yield strength, tensile strength and defect depth. Extensive validation has been carried out, using the probabilistic computer program STAR6 from Nuclear Electric and the deterministic program SACC from SAQ Kontroll AB. The validation showed that the results from PROPSE were correct, and that the algorithms used in STAR6 were not intended to work for a general problem, when the standard deviation is either 'small' or 'large'. Distributions, to be used in a probabilistic analysis, are discussed. Examples on data to be used are also given

Probabilistic safety evaluation: Development of procedures with applications on components used in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Dillstroem, P. [Det Norske Veritas AB, Stockholm (Sweden)

2000-12-01

A probabilistic procedure has been developed by SAQ Kontroll AB to calculate two different failure probabilities, P{sub F}: Probability of failure, defect size given by NDT/NDE. Probability of failure, defect not detected by NDT/NDE. Based on the procedure, SAQ Kontroll AB has developed a computer program PROPSE (PRObabilistic Program for Safety Evaluation). Within PROPSE, the following features are implemented: Two different algorithms to calculate the probability of failure are included: Simple Monte Carlo Simulation (MCS), with an error estimate on P{sub F}. First-Order Reliability Method (FORM), with sensitivity factors using the most probable point of failure in a standard normal space. Using these factors, it is possible to rank the parameters within an analysis. Estimation of partial safety factors, given an input target failure probability and characteristic values for fracture toughness, yield strength, tensile strength and defect depth. Extensive validation has been carried out, using the probabilistic computer program STAR6 from Nuclear Electric and the deterministic program SACC from SAQ Kontroll AB. The validation showed that the results from PROPSE were correct, and that the algorithms used in STAR6 were not intended to work for a general problem, when the standard deviation is either 'small' or 'large'. Distributions, to be used in a probabilistic analysis, are discussed. Examples on data to be used are also given.

Ratio dependence in small number discrimination is affected by the experimental procedure

Directory of Open Access Journals (Sweden)

Christian eAgrillo

2015-10-01

Full Text Available Adults, infants and some non-human animals share an approximate number system (ANS to estimate numerical quantities, and are supposed to share a second, ‘object-tracking’, system (OTS that supports the precise representation of a small number of items (up to 3 or 4. In relative numerosity judgments, accuracy depends on the ratio of the two numerosities (Weber’s Law, for numerosities > 4 (the typical ANS range, while for numerosities ≤ 4 (OTS range there is usually no ratio effect. However, recent studies have found evidence for ratio effects for small numerosities, challenging the idea that the OTS might be involved for small number discrimination. Here we tested the hypothesis that the lack of ratio effect in the numbers 1-4 is largely dependent on the type of stimulus presentation.We investigated relative numerosity judgments in college students using three different procedures: a simultaneous presentation of intermingled and separate groups of dots in separate experiments, and a further experiment with sequential presentation. As predicted, in the large number range, ratio dependence was observed in all tasks. By contrast, in the small number range, ratio insensitivity was found in one task (sequential presentation. In a fourth experiment, we showed that the presence of intermingled distractors elicited a ratio effect, while easily distinguishable distractors did not. As the different ratio sensitivity for small and large numbers has been often interpreted in terms of the activation of the OTS and ANS, our results suggest that numbers 1-4 may be represented by both numerical systems and that the experimental context, such as the presence/absence of task-irrelevant items in the visual field, would determine which system is activated.

Design for safety: theoretical framework of the safety aspect of BIM system to determine the safety index

Directory of Open Access Journals (Sweden)

Ai Lin Evelyn Teo

2016-12-01

Full Text Available Despite the safety improvement drive that has been implemented in the construction industry in Singapore for many years, the industry continues to report the highest number of workplace fatalities, compared to other industries. The purpose of this paper is to discuss the theoretical framework of the safety aspect of a proposed BIM System to determine a Safety Index. An online questionnaire survey was conducted to ascertain the current workplace safety and health situation in the construction industry and explore how BIM can be used to improve safety performance in the industry. A safety hazard library was developed based on the main contributors to fatal accidents in the construction industry, determined from the formal records and existing literature, and a series of discussions with representatives from the Workplace Safety and Health Institute (WSH Institute in Singapore. The results from the survey suggested that the majority of the firms have implemented the necessary policies, programmes and procedures on Workplace Safety and Health (WSH practices. However, BIM is still not widely applied or explored beyond the mandatory requirement that building plans should be submitted to the authorities for approval in BIM format. This paper presents a discussion of the safety aspect of the Intelligent Productivity and Safety System (IPASS developed in the study. IPASS is an intelligent system incorporating the buildable design concept, theory on the detection, prevention and control of hazards, and the Construction Safety Audit Scoring System (ConSASS. The system is based on the premise that safety should be considered at the design stage, and BIM can be an effective tool to facilitate the efforts to enhance safety performance. IPASS allows users to analyse and monitor key aspects of the safety performance of the project before the project starts and as the project progresses.

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

International Nuclear Information System (INIS)

1986-11-01

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

Probabilistic safety analysis procedures guide. Sections 1-7 and appendices. Volume 1, Revision 1

International Nuclear Information System (INIS)

Bari, R.A.; Buslik, A.J.; Cho, N.Z.

1985-08-01

A procedures guide for the performance of probabilistic safety assessment has been prepared for interim use in the Nuclear Regulatory Commission programs. It will be revised as comments are received, and as experience is gained from its use. The probabilistic safety assessment studies performed are intended to produce probabilistic predictive models that can be used and extended by the utilities and by NRC to sharpen the focus of inquiries into a range of issues affecting reactor safety. This first volume of the guide describes the determination of the probability (per year) of core damage resulting from accident initiators internal to the plant (i.e., intrinsic to plant operation) and from loss of off-site electric power. The scope includes human reliability analysis, a determination of the importance of various core damage accident sequences, and an explicit treatment and display of uncertainties for key accident sequences. The second volume deals with the treatment of the so-called external events including seismic disturbances, fires, floods, etc. Ultimately, the guide will be augmented to include the plant-specific analysis of in-plant processes (i.e., containment performance). This guide provides the structure of a probabilistic safety study to be performed, and indicates what products of the study are valuable for regulatory decision making. For internal events, methodology is treated in the guide only to the extent necessary to indicate the range of methods which is acceptable; ample reference is given to alternative methodologies which may be utilized in the performance of the study. For external events, more explicit guidance is given

Treaty implementation applied to conventions on nuclear safety

International Nuclear Information System (INIS)

Montjoie, Michel

2015-01-01

Given that safety is the number one priority for the nuclear industry, it would seem normal that procedures exist to ensure the effective implementation of the provisions of the conventions on nuclear safety, as already exist for numerous international treaties. Unfortunately, these procedures are either weak or even nonexistent. Therefore, consideration must be given to whether this weakness represents a genuine deficiency in ensuring the main objective of these conventions, which is to achieve a high level of nuclear safety worldwide. But, before one can even address that issue, a prior question must be answered: does the specific nature of the international legal framework on nuclear safety automatically result in a lack of non-compliance procedures in international conventions on the subject? If so, the lack of procedures is justified, despite the drawbacks. The specific nature of the international law on nuclear safety, which in 1994 shaped the content of the CNS by notably not 'allowing' (even today) the incorporation of precise international rules have been taken into account. The next step is to examine whether the absence of non-compliance procedures (which could have been integrated into the text) is a hindrance in ensuring the objectives of the conventions on nuclear safety, and to examine the procedures that could have been used, based on existing provisions in other areas of international law (environmental law, financial law, disarmament law, human rights, etc.). International environmental law will be the main source of this study, as it has certain similarities with the international law on nuclear safety due to the sometimes vague nature of its obligations and irrespective of the fact that one of the purposes of nuclear safety is in particular to protect the environment from radiological hazards. Indeed, the provisions of the law on nuclear safety are mainly technical and designed to guarantee the normal operation of nuclear facilities

Safety: Preventive Medicine.

Science.gov (United States)

Kotula, John R.; Digenakis, Anthony

1985-01-01

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

Research on advanced system safety assessment procedures (4)

International Nuclear Information System (INIS)

Suzuki, Kazuhiko; Shimada, Yukiyasu

2001-03-01

The past research reports in the area of safety engineering proposed the Computer-aided HAZOP system to be applied to Nuclear Reprocessing Facilities. Automated HAZOP system has great advantage compared with human analysts in terms of accuracy of the results, and time required to conduct HAZOP studies. This report surveys the literature on risk assessment and safety design based on the concept of independent protection layers (IPLs). Furthermore, to improve HAZOP System, tool is proposed to construct the basic model and the internal state model. Such HAZOP system is applied to analyze two kinds of processes, where the ability of the proposed system is verified. In addition, risk assessment support system is proposed to integrate safety design environment and assessment result to be used by other plants as well as to enable the underline plant to use other plants' information. This technique can be implemented using web-based safety information systems. (author)

United States Nuclear Regulatory Commission Staff Practice and Procedure Digest

International Nuclear Information System (INIS)

1980-02-01

This first supplement to the second edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board and Atomic Safety and Licensing Board decisions issued during the period from April 1, 1978 to September 30, 1978 interpreting the NRC's Rules of Practice in 10 CFR Part 2. The supplement also includes additional material from adjudicatory decisions rendered prior to April 1, 1978 and, to a very limited degree, material from adjudicatory decisions and regulation changes after September 30, 1978. The supplement, which is intended to be used as a pocket-part supplement to the Digest itself, includes a number of new subsections and topics not covered in the Digest. The new subsections are noted in the index for the supplement

Radiological safety in petroleum industry. Towards prevention culture

International Nuclear Information System (INIS)

Truppa, Walter A.

2007-01-01

Within the frame of regulatory control of industrial applications the audit of sealed and open radioactive sources in oil uses is one of the most relevant. The handling of radioactive sources, the requirement of procedures and training are just a few examples among all those that make up the radiological safety culture. A number of requirements divided into three main groups: operational safety at the storage area of radioactive sources, during transportation and during the applications (Cementation, well logging and use of radiotracers) are highlighted. Due to the great number of aspects that have to be taken in account as well as the interrelation of all control processes it is highly recommended that aspects of safety culture and quality should be considered and improvements regarding prevention, should be introduced so as to correct deviations that could arise in order to avoid radiological risk situations, emphasizing risk perception situations, attitude training, implementation of audit and level of safety in the facilities and control of duties, involving radiological material handling, described in the present work. (author) [es

Exploration and safety evaluations of salt formations and site selection procedures; Erkundung und Sicherheitsbewertung von Salzformationen und Standortauswahlverfahren

Energy Technology Data Exchange (ETDEWEB)

Krapf, Eva Barbara

2016-12-12

In 2011 the final decision for the withdrawal from the nuclear energy program was decided in the Federal Republic of Germany. The majority of the produced radioactive waste originate in the operation as well as in the decommissioning and dismantling of nuclear facilities. The long-term containment of especially heat-developing and high-level waste in an underground disposal facility is pursued. The Site Selection Act (StandAG), passed in 2013, defined further procedural steps as well as responsibilities and the way of public participation during the site selection. In this context the newly founded Commission Storage of Highly Radioactive Waste was assigned with the task of giving relevant recommendations based on their investigation of specific aspects and fundamental questions. The objective of this procedure is the selection of the site that can provide the best possible safety for humans and the environment during the defined period of one million years. The Commissions' final report was published in July 2016. In this thesis a possible approach for exploring sites in connection with safety investigations is recommended. The site selection procedure described in the StandAG represents the basis for the considerations. Geoscientific exclusion criteria, minimum requirements as well as weighing criteria can be developed regarding the relevant geoscientific and climatic changes during the defined period of one million years. In contrast to the recommendations made by the Commission Storage of Highly Radioactive Waste no previously existing report has been revised and adapted. Rather, all issues relevant for the long-term containment of radioactive waste in a disposal facility had been newly developed. The considerations are related to salt domes as host rock. Furthermore, according to the StandAG preliminary safety investigations are required in every step of the site selection. The recommendations made in this thesis concerning content and feasibility of

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

Safety parameter display system for Kalinin NPP

International Nuclear Information System (INIS)

Andreev, V.I.; Videneev, E.N.; Tissot, J.C.; Joonekindt, D.; Davidenko, N.N.; Shaftan, G.I.; Dounaev, V.G.; Neboyan, V.T.

1995-01-01

The paper discusses the safety parameter display system (SPDS), which is being designed for Kalinin NPP. The assessment of the safety status of the plant is done by the continuous monitoring of six critical safety functions and the corresponding status trees. Besides, a number of additional functions are realized within the scope of KlnNPP, aimed at providing the operator and the safety engineer in the main control room with more detailed information in accidental situation as well as during the normal operation. In particular, these functions are: archiving, data logs and alarm handling, safety actions monitoring, mnemonic diagrams indicating the state of main technological equipment and basic plant parameters, reference data, etc. As compared with the traditional scope of functions of this kind of systems, the functionality of KlnNPP SPDS is significantly expanded due to the inclusion in it the operator support function ''computerized procedures''. The basic SPDS implementation platform is ADACS of SEMA GROUP design. The system architecture includes two workstations in the main control room: one is for reactor operator and the other one for safety engineer. Every station has two CRT screens which ensures computerized procedures implementation and provides for extra services for the operator. Also, the information from the SPDS is transmitted to the local crisis center and to the crisis center of the State utility organization concern ''Rosenergoatom''. (author). 3 refs, 6 figs, 1 tab

Newer techniques for intravascular and intraoperative neurointerventional procedures

International Nuclear Information System (INIS)

Higashida, R.T.; Halbach, V.V.; Hieshima, G.B.; Yang, P.

1987-01-01

A videotape demonstrating newer techniques used in intravascular and intraoperative embolization procedures will be presented. The authors discuss the use of some of the newer embolic agents, real-time digital subtraction angiography, roadmapping techniques, and the use of microcatheters and steerable micro guide wires, which has greatly facilitated neurovascullar embolization procedures and enhanced patient safety. A number of actual intraoperative and intravascular cases will be shown demonstrating treatment of vascular malformations of the brain and spinal cord, carotid cavernous sinus fistulas, aneurysms and dural arteriovenous malformations. The indications for treatment, patient selection, technical preparation and newer methodologies and approaches to complex vascular lesions of the brain and spinal cord are discussed in detail

10 April 2014: Safety Day at CERN

CERN Multimedia

Antonella Del Rosso

2014-01-01

A wide variety of chemicals is used every day in the different laboratories and workshops around CERN. Potentially toxic, corrosive, polluting or hazardous in other ways, these chemicals all have to be handled carefully, as we will be reminded by the Safety Day campaign to be held by the HSE Unit on 10 April to mark World Day for Safety and Health at Work.   The use of chemicals at CERN is regulated by "Safety Regulation SR-C, Chemical Agents", which defines the minimum health and safety protection requirements for people exposed to the potentially hazardous effects of dangerous chemicals. This regulation is complemented by other Safety guides. Regretfully, despite strict procedures and regular inspections, accidents caused by the improper use of chemicals do occur every year. "Unfortunately, each year we see a small number of accidents related to the handling of chemicals," confirms chemicals expert Jonathan Gulley, who is a member of the Prevention and Sa...

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

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

International Nuclear Information System (INIS)

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

2000-01-01

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

Development of a procedure for qualitative and quantitative evaluation of human factors as a part of probabilistic safety assessments of nuclear power plants. Part A

International Nuclear Information System (INIS)

Richei, A.

1998-01-01

The objective of this project is the development of a procedure for the qualitative and quantitative evaluation of human factors in the probabilistic safety assessment for nuclear power plants. The Human Error Rate Assessment and Optimizing System (HEROS) is introduced. The evaluation of a task with HEROS is realized in the three evaluation levels, i.e. 'Management Structure', 'Working Environment' and 'Man-Machine-Interface'. The developed expert system uses the fuzzy set theory for an assessment. For the evaluation of cognitive tasks evaluation criteria are derived also. The validation of the procedure is based on three examples, reflecting the common practice of probabilistic safety assessments and including problems, which cannot, respectively - only insufficiently - be evaluated with the established human risk analysis procedures. HERO applications give plausible and comprehensible results. (orig.) [de

CRITICALITY SAFETY LIMIT EVALUATION PROGRAM (CSLEP's) AND QUICK SCREENS: ANSWERS TO EXPEDITED PROCESSING LEGACY CRITICALITY SAFETY LIMITS AND EVALUATIONS

International Nuclear Information System (INIS)

TOFFER, H.

2006-01-01

Since the end of the cold war, the need for operating weapons production facilities has faded. Criticality Safety Limits and controls supporting production modes in these facilities became outdated and furthermore lacked the procedure based rigor dictated by present day requirements. In the past, in many instances, the formalism of present day criticality safety evaluations was not applied. Some of the safety evaluations amounted to a paragraph in a notebook with no safety basis and questionable arguments with respect to double contingency criteria. When material stabilization, clean out, and deactivation activities commenced, large numbers of these older criticality safety evaluations were uncovered with limits and controls backed up by tenuous arguments. A dilemma developed: on the one hand, cleanup activities were placed on very aggressive schedules; on the other hand, a highly structured approach to limits development was required and applied to the cleanup operations. Some creative approaches were needed to cope with the limits development process

Laser safety and practice

International Nuclear Information System (INIS)

Low, K.S.

1995-01-01

Lasers are finding increasing routine applications in many areas of science, medicine and industry. Though laser radiation is non-ionizing in nature, the usage of high power lasers requires specific safety procedures. This paper briefly outlines the properties of laser beams and various safety procedures necessary in their handling and usage. (author)

Work procedures and risk factors for high rdiation exposure among radiologic technologists in South Korea

Energy Technology Data Exchange (ETDEWEB)

Kim, Jae Young; Choi, Yeong Chull [Dept. of Preventive Medicine, Keimyung University College of Medicine, Daegu (Korea, Republic of); Lee, Won Jin; Cha, Eun Shil [Dept. of Preventive Medicine, Korea University College of Medicine, Seoul (Korea, Republic of)

2016-12-15

Radiologic technologists currently consist of 31.5% among diagnostic radiation workers in South Korea. Among diagnostic radiation workers, radiologic technologists receive the highest annual and collective doses in South Korea. Comprehensive assessment of the work practices and associated radiation doses from diagnostic radiology procedures should be undertaken for effective prevention for radiologic technologists. Using the national survey, this study aimed (1) to explore the distribution of the work procedures performed by gender, (2) to evaluate occupational radiation exposure by work characteristics and safety compliance, (3) to identify the primary factors influencing high radiation exposure among radiologic technologists in South Korea. This study provided detailed information on work practices, number of procedures performed on weekly basis, and occupational radiation doses among radiologic technologists in South Korea. Average radiation dose for radiologic technologists is higher than other countries, and type of facility, work safety, and wearing lead apron explained quite a portion of increased risk in the association between radiology procedures and radiation exposure among radiologic technologists.

Work procedures and risk factors for high rdiation exposure among radiologic technologists in South Korea

International Nuclear Information System (INIS)

Kim, Jae Young; Choi, Yeong Chull; Lee, Won Jin; Cha, Eun Shil

2016-01-01

Radiologic technologists currently consist of 31.5% among diagnostic radiation workers in South Korea. Among diagnostic radiation workers, radiologic technologists receive the highest annual and collective doses in South Korea. Comprehensive assessment of the work practices and associated radiation doses from diagnostic radiology procedures should be undertaken for effective prevention for radiologic technologists. Using the national survey, this study aimed (1) to explore the distribution of the work procedures performed by gender, (2) to evaluate occupational radiation exposure by work characteristics and safety compliance, (3) to identify the primary factors influencing high radiation exposure among radiologic technologists in South Korea. This study provided detailed information on work practices, number of procedures performed on weekly basis, and occupational radiation doses among radiologic technologists in South Korea. Average radiation dose for radiologic technologists is higher than other countries, and type of facility, work safety, and wearing lead apron explained quite a portion of increased risk in the association between radiology procedures and radiation exposure among radiologic technologists.

Management of construction safety at KKNPP site

International Nuclear Information System (INIS)

Khare, P.K.

2016-01-01

Construction is considered as one of the most hazardous activities owing to the number of accidents and injuries. At KKNPP, management of industrial safety has been envisaged since the preliminary stage of construction planning, including design aspects. The governing principles of safety management are evolved from the Factories Act, 1948, the Atomic Energy(Factories) Rules, 1996, AERB safety guidelines on Control of works (2011) and Corporate HSE policy of NPCIL (2014). Numerous risk assessment and hazard control measures are adopted consistently to ensure a safe work environment during the construction, which includes Job Hazard Analysis, work permit through Computerized Maintenance Management System, safety procedures, exclusive safety training facility for the contractor's workmen, safety motivational measures, safety surveillance and reporting through Safety Related Deficiencies Management System. Assessment of efficacy of safety management system is continuously done through safety audits and observations are being circulated and discussed in committee meetings. Fire safety is also being taken care of since inception of project work. Well-equipped fire station with trained fire fighters was made available since the beginning as per AERB safety standard on fire protection system for Nuclear facilities. Fire prevention measures specific to the work are implemented during all activities. (author)

47 CFR 80.319 - Radiotelegraph distress call and message transmission procedure.

Science.gov (United States)

2010-10-01

...) SAFETY AND SPECIAL RADIO SERVICES STATIONS IN THE MARITIME SERVICES Safety Watch Requirements and Procedures Distress, Alarm, Urgency and Safety Procedures § 80.319 Radiotelegraph distress call and message...

Procedures For Microbial-Ecology Laboratory

Science.gov (United States)

Huff, Timothy L.

1993-01-01

Microbial Ecology Laboratory Procedures Manual provides concise and well-defined instructions on routine technical procedures to be followed in microbiological laboratory to ensure safety, analytical control, and validity of results.

The nuclear licensing and supervisory procedures for nuclear facilities in the Federal Republic of Germany

International Nuclear Information System (INIS)

Franzen, L.F.

1982-02-01

A combined system has been developed in the Federal Republic of Germany: the States execute the Atomic Energy Act on behalf of the Federal Government. Despite these differences, the safety requirements and the safety standard achieved vary only insignificantly, as a result of a world-wide communication and of international cooperation. The legal prerequesites for the German nuclear licensing procedures have been established about 20 years ago, and, by a number of amendments have been adapted to new perceptions and developments. Several supplementary ordinances, due to further developments in nuclear technology, are being prepared. The work on associated technical provision, which had been neglected for a long time, has in recent years been tackled systematically and should, before long, lead to a comprehensive programme of safety standards, which simplifies and expedites the nuclear licensing procedures. Essential features of the licensing procedure are the phased structure and the division into intermediate steps which render it possible to adapt the safety requirements to the advancing state of science and technology. The responsible authorities call in experts for the safety verification of the application documents. It is the task of these experts to make assessments and to conduct quality examinations in the manufacturing plants and at the site, and to carry out recurrent tests. The public is involved by the announcement of the projects, the display of the documents and by the opportunity to raise objections during the licensing procedure. Licenses granted can be contested before the administrative courts. This procedure paves the way for the achievement of a satisfactory balance between private and public interests. (orig./HP)

United States Nuclear Regulatory Commission Staff Practice and Procedure Digest. Digest No. 2

International Nuclear Information System (INIS)

1978-08-01

This second edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to March 31, 1978 interpreting the NRC's Rules of Practice in 10 CFR Part 2. This second edition replaces the first edition and its supplements and includes appropriate changes reflecting the recent amendments to the Rules of Practice which became effective on May 26, 1978

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

International Nuclear Information System (INIS)

1996-04-01

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

Factory Acceptance Test Procedure Westinghouse 100 ton Hydraulic Trailer

International Nuclear Information System (INIS)

Aftanas, B.L.

1994-01-01

This Factory Acceptance Test Procedure (FAT) is for the Westinghouse 100 Ton Hydraulic Trailer. The trailer will be used for the removal of the 101-SY pump. This procedure includes: safety check and safety procedures; pre-operation check out; startup; leveling trailer; functional/proofload test; proofload testing; and rolling load test

Investigation of the possibility of a calculative reactor safety estimation in the licence procedure for nuclear reactors

International Nuclear Information System (INIS)

Adler, B.; Kampf, T.

1975-12-01

Up to now it is impossible to calculate completely the safety of nuclear reactors. Therefore the authors have collected and employed a number of at a high degree independent safety parameters for mathematical evaluation of the reactor safety. By means of computer programs such parameters from about 400 research reactors have been analysed and the fluctuation ranges of their greatest density were determined. The limits of these fluctuation ranges are quickly available and can be used as recommended values for the layout and for the safety estimation of research reactors. A comparison of the existing layout recommendations and the determined fluctuation ranges in most cases shows a good agreement. In some cases corrections and new layout recommendations have been proposed. The determined fluctuation ranges found their first practical application in the estimation of the Rossendorf Equipment for Critical Experiments (RAKE). (author)

Metrics design for safety assessment

NARCIS (Netherlands)

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

2016-01-01

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

A study on fire design accidental loads for aluminum safety helidecks

Directory of Open Access Journals (Sweden)

Sang Jin Kim

2016-11-01

Full Text Available The helideck structure must satisfy the safety requirements associated with various environmental and accidental loads. Especially, there have been a number of fire accidents offshore due to helicopter collision (take-off and/or landing in recent decades. To prevent further accidents, a substantial amount of effort has been directed toward the management of fire in the safety design of offshore helidecks. The aims of this study are to introduce and apply a procedure for quantitative risk assessment and management of fires by defining the fire loads with an applied example. The frequency of helicopter accidents are considered, and design accidental levels are applied. The proposed procedures for determining design fire loads can be efficiently applied in offshore helideck development projects.

Safety system status monitoring

International Nuclear Information System (INIS)

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

1984-03-01

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

Safety system status monitoring

Energy Technology Data Exchange (ETDEWEB)

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

1984-03-01

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

Procedural-Based Category Learning in Patients with Parkinson's Disease: Impact of Category Number and Category Continuity

Directory of Open Access Journals (Sweden)

J. Vincent eFiloteo

2014-02-01

Full Text Available Previously we found that Parkinson's disease (PD patients are impaired in procedural-based category learning when category membership is defined by a nonlinear relationship between stimulus dimensions, but these same patients are normal when the rule is defined by a linear relationship (Filoteo et al., 2005; Maddox & Filoteo, 2001. We suggested that PD patients' impairment was due to a deficit in recruiting ‘striatal units' to represent complex nonlinear rules. In the present study, we further examined the nature of PD patients' procedural-based deficit in two experiments designed to examine the impact of (1 the number of categories, and (2 category discontinuity on learning. Results indicated that PD patients were impaired only under discontinuous category conditions but were normal when the number of categories was increased from two to four. The lack of impairment in the four-category condition suggests normal integrity of striatal medium spiny cells involved in procedural-based category learning. In contrast, and consistent with our previous observation of a nonlinear deficit, the finding that PD patients were impaired in the discontinuous condition suggests that these patients are impaired when they have to associate perceptually distinct exemplars with the same category. Theoretically, this deficit might be related to dysfunctional communication among medium spiny neurons within the striatum, particularly given that these are cholinergic neurons and a cholinergic deficiency could underlie some of PD patients’ cognitive impairment.

Regulatory activities in reactor safety

International Nuclear Information System (INIS)

Salvatore, J.E.L.

1987-01-01

The safety phylosophy in designs and operation of nuclear power plants and, the steps for evaluating the safety and quality assurance, in the licensing procedure are described. The CNEN organization structure and the licensing procedure for nuclear power plants in Brazil are presented. (M.C.K.) [pt

The computerised procedure system COPMA and its user interface

International Nuclear Information System (INIS)

Krogsaeter, M.; Larsen, J.; Nilsen, S.; Oewre, F.

1990-01-01

At the OECD Halden Reactor Project, the COPMA system has been developed in order to investigate whether procedures can be executed more safety and efficiently if they are computerised, i.e. if the operator uses a CRT-based system instead of written manuals. Procedures are entered in a procedure data base using PED, a procedure editor. Each procedure is given a textual as well as a graphical representation. For the textual representation, the language PROLA is used, a language which has been designed for simple procedure specification. The COPMA online system lets the operator execute procedures that are stored in the procedure data base. The operator interface is a screen divided into non-overlapping windows each serving a different purpose. All commands to the system are given by moving a mouse device around and clicking buttons on top of the mouse. A procedure consists of steps, each step containing a number of instructions. The operator works on one activity at a time, an activity to be seen as a procedure instance. A graph shows the overall procedure (or activity) structure in a window and activity execution is traced in the graph. Another windows shows the instructions of the step currently being executed. The operator steps through the activity by selecting whether and how to execute the listed instructions. COPMA can maintain the status of several activities in parallel, so that the operator can easily switch between different activities. COPMA is linked to a PWR nuclear simulator over Ethernet using the TCP/IP protocol. This gives a number of advantages as compared to conventional written procedures, especially the fact that COPMA can help collect data from the procedure data base automatically

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

International Nuclear Information System (INIS)

1993-02-01

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

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

International Nuclear Information System (INIS)

1992-11-01

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

Surgical procedures performed in the neonatal intensive care unit on critically ill neonates: feasibility and safety

International Nuclear Information System (INIS)

Mallick, M.S.; Jado, A.M.; Al-Bassam, A.R.

2008-01-01

Transferring unstable, ill neonates to and from the operating rooms carries significant risks and can lead to morbidity. We report on our experience in performing certain procedures in critically ill neonates in the neonatal intensive care unit (NICU). We examined the feasibility and safety for such an approach. All surgical procedures performed in the NICU between January 1999 and December 2005 were analyzed in terms of demographic data, diagnosis, preoperative stability of the patient, procedures performed, complications and outcome. Operations were performed at beside in the NICU in critically ill, unstable neonates who needed emergency surgery, in neonates of low birth weight (<1000 gm) and in neonates on special equipments like higher frequency ventilators and nitrous oxide. Thirty-seven surgical procedures were performed including 12 laparotomies, bowel resection and stomies, 7 repairs of congenital diaphragmatic hernias, 4 ligations of patent ductus arteriosus and various others. Birth weights ranged between 850 gm and 3500 gm (mean 2000 gm). Gestational age ranged between 25 to 42 weeks (mean, 33 weeks). Age at surgery was between 1 to 30 days (mean, 30 days). Preoperatively, 19 patients (51.3%) were on inotropic support and all were intubated and mechanically ventilated. There was no mortality related to surgical procedures. Postoperatively, one patient developed wound infection and disruption. Performing major surgical procedures in the NICU is both feasible and safe. It is useful in very low birth weight, critically ill neonates who have definite risk attached to transfer to the operating room. No special area is needed in the NICU to perform complication-free surgery, but designing an operating room within the NICU will be ideal. (author)

Safety excavation; Seguranca em escavacoes

Energy Technology Data Exchange (ETDEWEB)

Ribeiro, Walter Manoel [TRANSPETRO - PETROBRAS Transporte S.A., Rio de Janeiro, RJ (Brazil)

2003-07-01

In the construction and maintenance services of buried pipelines, the excavation is the activity that contains larger risk, could cause serious accidents. Norms, procedures and technical articles, national and international goods, should be followed for legal and technical aspects. This paper - Safety in Excavations - has purpose to gather all the technical concepts and of safety in a document denominated Procedure of Safety Excavation, serving as instrument to systematize and control the execution of excavation services in construction civil, assembly and pipelines repairs, seeking the people, facilities and the environment's safety. (author)

Procedure for conducting probabilistic safety assessment: level 1 full power internal event analysis

Energy Technology Data Exchange (ETDEWEB)

Jung, Won Dae; Lee, Y. H.; Hwang, M. J. [and others

2003-07-01

This report provides guidance on conducting a Level I PSA for internal events in NPPs, which is based on the method and procedure that was used in the PSA for the design of Korea Standard Nuclear Plants (KSNPs). Level I PSA is to delineate the accident sequences leading to core damage and to estimate their frequencies. It has been directly used for assessing and modifying the system safety and reliability as a key and base part of PSA. Also, Level I PSA provides insights into design weakness and into ways of preventing core damage, which in most cases is the precursor to accidents leading to major accidents. So Level I PSA has been used as the essential technical bases for risk-informed application in NPPs. The report consists six major procedural steps for Level I PSA; familiarization of plant, initiating event analysis, event tree analysis, system fault tree analysis, reliability data analysis, and accident sequence quantification. The report is intended to assist technical persons performing Level I PSA for NPPs. A particular aim is to promote a standardized framework, terminology and form of documentation for PSAs. On the other hand, this report would be useful for the managers or regulatory persons related to risk-informed regulation, and also for conducting PSA for other industries.

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

Propofol for procedural sedation and analgesia reduced dedicated emergency nursing time while maintaining safety in a community emergency department.

Science.gov (United States)

Reynolds, Joshua C; Abraham, Michael K; Barrueto, Fermin F; Lemkin, Daniel L; Hirshon, Jon M

2013-09-01

Procedural sedation and analgesia is a core competency in emergency medicine. Propofol is replacing midazolam in many emergency departments. Barriers to performing procedural sedation include resource utilization. We hypothesized that emergency nursing time is shorter with propofol than midazolam, without increasing complications. Retrospective analysis of a procedural sedation registry for two community emergency departments with combined census of 100,000 patients/year. Demographics, procedure, and ASA physical classification status of adult patients receiving procedural sedation between 2007-2010 with midazolam or propofol were analyzed. Primary outcome was dedicated emergency nursing time. Secondary outcomes were procedural success, ED length of stay, and complication rate. Comparative statistics were performed with Mann-Whitney, Kruskal-Wallis, chi-square, or Fisher's exact test. Linear regression was performed with log-transformed procedural sedation time to define predictors. Of 328 procedural sedation and analgesia, 316 met inclusion criteria, of which 60 received midazolam and 256 propofol. Sex distribution varied between groups (midazolam 3% male; propofol 55% male; P = 0.04). Age, procedure, and ASA status were not significantly different. Propofol had shorter procedural sedation time (propofol 32.5 ± 24.2 minutes; midazolam 78.7 ± 51.5 minutes; P differences between complication rates (propofol 14%; midazolam 13%; P = 0.88) or emergency department length of stay (propofol 262.5 ± 132.8 minutes; midazolam 288.6 ± 130.6 minutes; P = 0.09). Use of propofol resulted in shorter emergency nursing time and higher procedural success rate than midazolam with a comparable safety profile. Copyright © 2013 Emergency Nurses Association. Published by Mosby, Inc. All rights reserved.

49 CFR 244.17 - Procedures.

Science.gov (United States)

2010-10-01

... Other Regulations Relating to Transportation (Continued) FEDERAL RAILROAD ADMINISTRATION, DEPARTMENT OF TRANSPORTATION REGULATIONS ON SAFETY INTEGRATION PLANS GOVERNING RAILROAD CONSOLIDATIONS, MERGERS, AND ACQUISITIONS OF CONTROL Safety Integration Plans § 244.17 Procedures. (a) Each applicant shall file one...

Nuclear safety. Volume 36, Number 2, July--December 1995

Energy Technology Data Exchange (ETDEWEB)

None

1995-12-01

The primary scope of the journal is safety in the design, construction, operation, and decommissioning of nuclear power reactors worldwide and the research and analysis activities that promote this goal, but it also encompasses the safety aspects of the entire nuclear fuel cycle, including fuel fabrication, spent-fuel processing and handling, and nuclear waste disposal, the handling of fissionable materials and radioisotopes, and the environmental effects of all these activities. The following subjects are covered here: (1) the Chernobyl accident; (2) general safety considerations; (3) accident analysis; (4) design features; (5) environmental effects; (6) operating experiences; (7) US NRC information and analyses; and (8) recent developments. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

Safety analysis report 231-Z Building

Energy Technology Data Exchange (ETDEWEB)

Powers, C.S.

1989-03-01

This report provides an intensive review of the nuclear safety of the operation of the 231-Z Building. For background information complete descriptions of the floor plan, building services, alarm systems, and glove box systems are included in this report. In addition, references are included to The Plutonium Laboratory Radiation Work Procedures, Safety Guides, 231-Z Operating Procedures Manual and Nuclear Materials accountability Procedures. Engineered and administrative features contribute to the overall safety of personnel, the building, and environs. The consequences of credible incidents were considered and are discussed.

Recommended safety procedures for the selection and use of demonstration-type gas discharge devices in schools

International Nuclear Information System (INIS)

1979-01-01

A 1972 survey of 30 Ottawa secondary schools revealed a total of 347 actual or potential X-ray sources available in these schools. More than half of these sources were gas discharge tubes. Some gas discharge tubes, in particular the cold cathode type, can emit X-rays at significantly high levels. Unless such tubes are used carefully, and with regard for good radiation safety practices, they can result in exposures to students that are in excess of the maximum levels recommended by the International Commission on Radiological Protection. Several cases of the recommended dose being exceeded were found in the classes surveyed. This document has been prepared to assist science teachers and others using demonstration-type gas discharge devices to select and use such devices so as to present negligible risk to themselves and students. Useful information on safety procedures to be followed when performing demonstrations or experiments is included. (J.T.A.)

Development of a procedure for qualitative and quantitative evaluation of human factors as a part of probabilistic safety assessments of nuclear power plants. Part B. Technical documentation

International Nuclear Information System (INIS)

Richei, A.

1998-01-01

As international studies have shown, accidents in plants are increasingly caused by combinations of technical failures and human errors. Therefore careful investigations of man-machine-interactions to determine human reliability are gaining importance worldwide. Regarding nuclear power plants such investigations are usually carried out within the scope of probabilistic safety assessments. A great number of procedures to evaluate human factors has been developed up to now. However, none of them is able to take into account the whole spectrum of requirements - as for instance transferability of date to other plants, analysis of weak points, and evaluation of cognitive tasks - for a complete and reliable probabilistic safety assessment. Based on an advanced model for a man-machine-system, the Human Error Rate Assessment and Optimizing System (HEROS) and a corresponding expert system of the same name are introduced. This expert system enables the quantification of human error probabilities for plant operator actions on the one hand and is also capable of providing quantitative statements regarding the optimization of man-machine-system in terms of human error probability minimization on the other one. Three relevant evaluation levels, i.e. 'Management Structure', 'Working Environment' and 'Man-Machine-Interface', are derived from a model of the man-machine-system. Linguistic variables are assigned to all performance shaping factors at these levels. These variables are used to establish a rule-based expert system. The knowledge bases of this system are represented by rules. Processing of these rules is carried out by means of the fuzzy set theory, after provision of relevant data for a particular personal action to be evaluated. This procedure enables a simple and effective use of ergonomic studies as the relevant database, which is also transferable to other plants with any design. The expert system consist in total of 16 rule bases in which all ascertainable and

Safety for Users

CERN Multimedia

HR Department

2008-01-01

CERN welcomes more than 8000 Users every year. The PH Department as host to these scientific associates requires the highest safety standards. The PH Safety Office has published a Safety Flyer for Users. Important safety topics and procedures are presented. Although the Flyer is intended primarily to provide safety information for Users, the PH Safety Office invites all those on the CERN sites to keep a copy of the flyer as it gives guidance in matters of safety and explains what to do in the event of an emergency. Link: http://ph-dep.web.cern.ch/ph-dep/Safety/SafetyOffice.html PH-Safety Office PH Department

Safety for Users

CERN Multimedia

HR Department

2008-01-01

CERN welcomes more than 8000 Users every year. The PH Department as host to these scientific associates requires the highest safety standards. The PH Safety Office has published a safety flyer for Users. Important safety topics and procedures are presented. Although the flyer is intended primarily to provide safety information for Users, the PH Safety Office invites all those on the CERN sites to keep a copy of the flyer as it gives guidance in matters of safety and explains what to do in the event of an emergency. The flyer is available at: http://ph-dep.web.cern.ch/ph-dep/Safety/SafetyOffice.html PH-Safety Office PH Department

Can proceduralization support coping with the unexpected?

International Nuclear Information System (INIS)

Norros, Leena; Savioja, Paula; Liinasuo, Marja; Wahlstrom, Mikael

2014-01-01

Operations of safety critical industries unquestionably require a diversity of technical and organizational control measures to increase stability and predictability of the complex sociotechnical systems. Nevertheless, experiences from recent severe accidents and results of safety research have questioned the effectiveness of the prevailing safety management strategy that mainly relies on standardization and designed-in defenses. This paper discusses the identified need to balance between stability and flexibility in a concrete safety issue, i.e., proceduralization. The main research problem of our study is whether procedure guided practice can offer sufficient support for flexibility of operating activity. We shall frame our study with the help of a model that explains different aspects of procedures. We then elaborate how these different aspects were considered empirically in our 3-phase study. In the first study we interviewed 62 main control room operators and asked how they consider procedures to support balancing. In the second study we observed in detail 12 NPP operator crews' activity in a simulated loss-of-coolant accident. In a third study we inquired 5 procedure designers about their conceptions concerning procedure guidance in operator work. Drawing on either interview or behavioral data we analyzed the personnel's stance to the flexibility and stability balancing, and how the conceptions portray in the practices of procedure usage. Our results demonstrate that the operators are aware of the need for balancing flexibility and stability and consider successful balancing to represent 'good' professional action. In actual action many operators, however, tend towards more straightforward following of procedures. Designers also see the capability for balancing stability and flexibility as a key operator competence but describe actual acting simply as procedure-following. According to the documents of the nuclear community, procedure

Can proceduralization support coping with the unexpected?

Energy Technology Data Exchange (ETDEWEB)

Norros, Leena; Savioja, Paula; Liinasuo, Marja; Wahlstrom, Mikael [VTT Technical Research Centre of Finland, Vuorimiehentie (Finland)

2014-08-15

Operations of safety critical industries unquestionably require a diversity of technical and organizational control measures to increase stability and predictability of the complex sociotechnical systems. Nevertheless, experiences from recent severe accidents and results of safety research have questioned the effectiveness of the prevailing safety management strategy that mainly relies on standardization and designed-in defenses. This paper discusses the identified need to balance between stability and flexibility in a concrete safety issue, i.e., proceduralization. The main research problem of our study is whether procedure guided practice can offer sufficient support for flexibility of operating activity. We shall frame our study with the help of a model that explains different aspects of procedures. We then elaborate how these different aspects were considered empirically in our 3-phase study. In the first study we interviewed 62 main control room operators and asked how they consider procedures to support balancing. In the second study we observed in detail 12 NPP operator crews' activity in a simulated loss-of-coolant accident. In a third study we inquired 5 procedure designers about their conceptions concerning procedure guidance in operator work. Drawing on either interview or behavioral data we analyzed the personnel's stance to the flexibility and stability balancing, and how the conceptions portray in the practices of procedure usage. Our results demonstrate that the operators are aware of the need for balancing flexibility and stability and consider successful balancing to represent 'good' professional action. In actual action many operators, however, tend towards more straightforward following of procedures. Designers also see the capability for balancing stability and flexibility as a key operator competence but describe actual acting simply as procedure-following. According to the documents of the nuclear community, procedure

Safety in the Operating Theatre | a Multi Factor Approach for Patients and Teams

NARCIS (Netherlands)

Wauben, L.S.G.L.

2010-01-01

Due to the advances in high-tech technology in the operating theatre, the increased number of persons involved, and the increased complexity of surgical procedures, medical errors are inflicted. To answer the main question: How to improve patient safety in the operating theatre during surgery? this

Towards Verification of Operational Procedures Using Auto-Generated Diagnostic Trees

Science.gov (United States)

Kurtoglu, Tolga; Lutz, Robyn; Patterson-Hine, Ann

2009-01-01

The design, development, and operation of complex space, lunar and planetary exploration systems require the development of general procedures that describe a detailed set of instructions capturing how mission tasks are performed. For both crewed and uncrewed NASA systems, mission safety and the accomplishment of the scientific mission objectives are highly dependent on the correctness of procedures. In this paper, we describe how to use the auto-generated diagnostic trees from existing diagnostic models to improve the verification of standard operating procedures. Specifically, we introduce a systematic method, namely the Diagnostic Tree for Verification (DTV), developed with the goal of leveraging the information contained within auto-generated diagnostic trees in order to check the correctness of procedures, to streamline the procedures in terms of reducing the number of steps or use of resources in them, and to propose alternative procedural steps adaptive to changing operational conditions. The application of the DTV method to a spacecraft electrical power system shows the feasibility of the approach and its range of capabilities

Safety Precautions and Operating Procedures in an (A)BSL-4 Laboratory: 1. Biosafety Level 4 Suit Laboratory Suite Entry and Exit Procedures.

Science.gov (United States)

Janosko, Krisztina; Holbrook, Michael R; Adams, Ricky; Barr, Jason; Bollinger, Laura; Newton, Je T'aime; Ntiforo, Corrie; Coe, Linda; Wada, Jiro; Pusl, Daniela; Jahrling, Peter B; Kuhn, Jens H; Lackemeyer, Matthew G

2016-10-03

Biosafety level 4 (BSL-4) suit laboratories are specifically designed to study high-consequence pathogens for which neither infection prophylaxes nor treatment options exist. The hallmarks of these laboratories are: custom-designed airtight doors, dedicated supply and exhaust airflow systems, a negative-pressure environment, and mandatory use of positive-pressure ("space") suits. The risk for laboratory specialists working with highly pathogenic agents is minimized through rigorous training and adherence to stringent safety protocols and standard operating procedures. Researchers perform the majority of their work in BSL-2 laboratories and switch to BSL-4 suit laboratories when work with a high-consequence pathogen is required. Collaborators and scientists considering BSL-4 projects should be aware of the challenges associated with BSL-4 research both in terms of experimental technical limitations in BSL-4 laboratory space and the increased duration of such experiments. Tasks such as entering and exiting the BSL-4 suit laboratories are considerably more complex and time-consuming compared to BSL-2 and BSL-3 laboratories. The focus of this particular article is to address basic biosafety concerns and describe the entrance and exit procedures for the BSL-4 laboratory at the NIH/NIAID Integrated Research Facility at Fort Detrick. Such procedures include checking external systems that support the BSL-4 laboratory, and inspecting and donning positive-pressure suits, entering the laboratory, moving through air pressure-resistant doors, and connecting to air-supply hoses. We will also discuss moving within and exiting the BSL-4 suit laboratories, including using the chemical shower and removing and storing positive-pressure suits.

46 CFR 154.665 - Welding procedures.

Science.gov (United States)

2010-10-01

... 46 Shipping 5 2010-10-01 2010-10-01 false Welding procedures. 154.665 Section 154.665 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) CERTAIN BULK DANGEROUS CARGOES SAFETY STANDARDS... Construction § 154.665 Welding procedures. Welding procedure tests for cargo tanks for a design temperature...

49 CFR 192.225 - Welding procedures.

Science.gov (United States)

2010-10-01

... 49 Transportation 3 2010-10-01 2010-10-01 false Welding procedures. 192.225 Section 192.225... BY PIPELINE: MINIMUM FEDERAL SAFETY STANDARDS Welding of Steel in Pipelines § 192.225 Welding procedures. (a) Welding must be performed by a qualified welder in accordance with welding procedures...

Procedure for seismic evaluation and design of small bore piping

International Nuclear Information System (INIS)

Bilanin, W.; Sills, S.

1991-01-01

Simplified methods for the seismic design of small bore piping in nuclear power plants have teen used for many years. Various number of designers have developed unique methods to treat the large number of class 2 and 3 small bore piping systems. This practice has led to a proliferation of methods which are not standardized in the industry. These methods are generally based on enveloping the results of rigorous dynamic or conservative static analysis and result in an excessive number of supports and unrealistically high support loadings. Experience and test data have become available which warranted taking another look at the present methods for analysis of small bore piping. A recently completed Electric Power Research Institute and NCIG (a utility group) activity developed a new procedure for the seismic design and evaluation of small bore piping which provides significant safety and cost benefits. The procedure streamlines the approach to inertial stresses, which is the main feature that achieves the new benefits. Criteria in the procedure for seismic anchor movement and support design are based analysis and focus the designer on credible failure mechanisms. A walkdown of the as-constructed piping system to identify and eliminate undesirable piping features such as adverse spatial interaction is required

49 CFR 385.317 - Will a safety audit result in a safety fitness determination by the FMCSA?

Science.gov (United States)

2010-10-01

... 49 Transportation 5 2010-10-01 2010-10-01 false Will a safety audit result in a safety fitness... SAFETY REGULATIONS SAFETY FITNESS PROCEDURES New Entrant Safety Assurance Program § 385.317 Will a safety audit result in a safety fitness determination by the FMCSA? A safety audit will not result in a safety...

Procedure generation and verification

International Nuclear Information System (INIS)

Sheely, W.F.

1986-01-01

The Department of Energy has used Artificial Intelligence of ''AI'' concepts to develop two powerful new computer-based techniques to enhance safety in nuclear applications. The Procedure Generation System, and the Procedure Verification System, can be adapted to other commercial applications, such as a manufacturing plant. The Procedure Generation System can create a procedure to deal with the off-normal condition. The operator can then take correct actions on the system in minimal time. The Verification System evaluates the logic of the Procedure Generator's conclusions. This evaluation uses logic techniques totally independent of the Procedure Generator. The rapid, accurate generation and verification of corrective procedures can greatly reduce the human error, possible in a complex (stressful/high stress) situation

Implementation of radiation safety program in a medical institution

International Nuclear Information System (INIS)

Palanca, Elena D.

1999-01-01

A medical institution that utilizes radiation for the diagnosis and treatment of diseases of malignancies develops and implements a radiation safety program to keep occupational exposures of radiation workers and exposures of non-radiation workers and the public to the achievable and a more achievable minimum, to optimize the use of radiation, and to prevent misadministration. The hospital radiation safety program is established by a core medical radiation committee composed of trained radiation safety officers and head of authorized users of radioactive materials and radiation machines from the different departments. The radiation safety program sets up procedural guidelines of the safe use of radioactive material and of radiation equipment. It offers regular training to radiation workers and radiation safety awareness courses to hospital staff. The program has a comprehensive radiation safety information system or radsis that circularizes the radiation safety program in the hospital. The radsis keeps the drafted and updated records of safety guides and policies, radioactive material and equipment inventory, personnel dosimetry reports, administrative, regulatory and licensing activity document, laboratory procedures, emergency procedures, quality assurance and quality control program process, physics and dosimetry procedures and reports, personnel and hospital staff training program. The medical radiation protection committee is tasked to oversee the actual implementation of the radiation safety guidelines in the different radiation facilities in the hospital, to review personnel exposures, incident reports and ALARA actions, operating procedures, facility inspections and audit reports, to evaluate the existing radiation safety procedures, to make necessary changes to these procedures, and make modifications of course content of the training program. The effective implementation of the radiation safety program provides increased confidence that the physician and

Work Pressure and Safety Behaviors among Health Workers in Ghana: The Moderating Role of Management Commitment to Safety

Directory of Open Access Journals (Sweden)

Kwesi Amponsah-Tawaih

2016-12-01

Conclusion: When employees perceive safety communication, safety systems and training to be positive, they seem to comply with safety rules and procedures than voluntarily participate in safety activities.

Accuracy and safety of ward based pleural ultrasound in the Australian healthcare system.

Science.gov (United States)

Hammerschlag, Gary; Denton, Matthew; Wallbridge, Peter; Irving, Louis; Hew, Mark; Steinfort, Daniel

2017-04-01

Ultrasound has been shown to improve the accuracy and safety of pleural procedures. Studies to date have been performed in large, specialized units, where pleural procedures are performed by a small number of highly specialized physicians. There are no studies examining the safety and accuracy of ultrasound in the Australian healthcare system where procedures are performed by junior doctors with a high staff turnover. We performed a retrospective review of the ultrasound database in the Respiratory Department at the Royal Melbourne Hospital to determine accuracy and complications associated pleural procedures. A total of 357 ultrasounds were performed between October 2010 and June 2013. Accuracy of pleural procedures was 350 of 356 (98.3%). Aspiration of pleural fluid was successful in 121 of 126 (96%) of patients. Two (0.9%) patients required chest tube insertion for management of pneumothorax. There were no recorded pleural infections, haemorrhage or viscera puncture. Ward-based ultrasound for pleural procedures is safe and accurate when performed by appropriately trained and supported junior medical officers. Our findings support this model of pleural service care in the Australian healthcare system. © 2016 Asian Pacific Society of Respirology.

Radiation safety

International Nuclear Information System (INIS)

Van Riessen, A.

2002-01-01

Full text: Experience has shown that modem, fully enclosed, XRF and XRD units are generally safe. This experience may lead to complacency and ultimately a lowering of standards which may lead to accidents. Maintaining awareness of radiation safety issues is thus an important role for all radiation safety officers. With the ongoing progress in technology, a greater number of radiation workers are more likely to use a range of instruments/techniques - eg portable XRF, neutron beam analysis, and synchrotron radiation analysis. The source for each of these types of analyses is different and necessitates an understanding of the associated dangers as well as use of specific radiation badges. The trend of 'suitcase science' is resulting in scientists receiving doses from a range of instruments and facilities with no coordinated approach to obtain an integrated dose reading for an individual. This aspect of radiation safety needs urgent attention. Within Australia a divide is springing up between those who work on Commonwealth property and those who work on State property. For example a university staff member may operate irradiating equipment on a University campus and then go to a CSIRO laboratory to operate similar equipment. While at the University State regulations apply and while at CSIRO Commonwealth regulations apply. Does this individual require two badges? Is there a need to obtain two licences? The application of two sets of regulations causes unnecessary confusion and increases the workload of radiation safety officers. Radiation safety officers need to introduce risk management strategies to ensure that both existing and new procedures result in risk minimisation. A component of this strategy includes ongoing education and revising of regulations. AXAA may choose to contribute to both of these activities as a service to its members as well as raising the level of radiation safety for all radiation workers. Copyright (2002) Australian X-ray Analytical

Demographic, procedural and 30-day safety results from the WEB Intra-saccular Therapy Study (WEB-IT).

Science.gov (United States)

Fiorella, David; Molyneux, Andrew; Coon, Alexander; Szikora, Istvan; Saatci, Isil; Baltacioglu, Feyyaz; Sultan, Ali; Arthur, Adam

2017-12-01

The Woven EndoBridge (WEB) represents a novel intrasaccular therapeutic option for the treatment of intracranial wide-necked bifurcation aneurysms (WNBAs). The WEB-IT Study is a pivotal Investigational Device Exemption (IDE) study to determine the safety and effectiveness of the WEB device for the treatment of WNBAs located in the anterior and posterior intracranial circulations. We present the patient demographics, procedural characteristics, and 30-day adverse event data for the US WEB-IT study. WEB-IT is a prospective multicenter single-arm interventional study conducted at 25 US and 6 international centers. The study enrolled 150 adults with WNBAs of the anterior and posterior intracranial circulations. All patients were intended to receive a WEB device delivered via standard endovascular neurosurgical embolization techniques. The study was conducted under Good Clinical Practices and included independent adjudication effectiveness outcomes and all adverse events. One hundred and fifty patients enrolled at 27 investigational sites underwent attempted treatment with the WEB. Mean age was 59 years (range 29-79) and 110 (73.3%) of the patients were female. Treated aneurysms were located at the basilar apex (n=59, 39.3%), middle cerebral artery bifurcation (n=45, 30%), anterior communicating artery (n=40, 26.7%), and internal carotid artery terminus (n=6, 4%). Average aneurysm size was 6.4 mm (range 3.6-11.4) with a mean neck size of 4.8 mm (range 2.0-8.2, mean dome to neck ratio 1.34). Nine patients presented with ruptured aneurysms. Of the enrolled patients, 98.7% were treated successfully with WEB devices. Mean±SD fluoroscopy time was 30.2±15.7 min. One primary safety event (PSE) (0.7%)-a delayed parenchymal hemorrhage 22 days after treatment-occurred between the index procedure and 30-day follow-up. In addition to the single PSE, there were seven (4.7%) minor ischemic strokes (5 resolved without sequelae and 2 had a modified Rankin Scale score of 1

Number of radiological examinations in Finland in 2008

International Nuclear Information System (INIS)

Tenkanen-Rautakoski, P.

2010-06-01

STUK (Radiation and Nuclear Safety Authority in Finlad) collected the number of radiological examinations classified to those made to adult and child patients in Finland in 2008. The work was based on the statute of the Ministry of Social Affairs and Health on the medical use of radiation. In 2008, approximately 3.9 million x-ray examinations were made in Finland. Earlier, the number of x-ray examinations has been investigated in 1984, 1995, 2000 and in 2005. During this time the total number of x-ray examinations has slightly diminished. During 2005 and 2008 the number of x-ray examinations has slightly increased, although the average number of examinations per inhabitant has still slightly decreased. The proportions of conventional x-ray examinations, computed tomography examinations, angiographic and interventional procedures were ca. 90.2%, 8.3%, 0.8% and 0.8%, respectively. In proportion to the Finnish population about 717 x-ray examinations per 1000 inhabitants were performed in 2008. Dental examinations are excluded from this number, but CT examinations (ca. 60 per 1000 inhabitants) and interventional x-ray procedures (ca. 5 per 1000 inhabitants) are included. Slightly more than 0.5 million ultrasound examinations and 190 000 MRI examinations were reported. Of the all x-ray examinations made in 2008, ca 7.5% were made to child patients. 0-16-year-old were thought to be child patients in this study. 8% of conventional x-ray examinations and 2% of computed tomography examinations and angiographic examination were made to child patients. (orig.)

Relevance of microbial finished product testing in food safety management

DEFF Research Database (Denmark)

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

2016-01-01

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

Licensing procedures and safety criteria for research reactors in France

International Nuclear Information System (INIS)

Berry, J.L.; Lerouge, B.

1980-11-01

This paper summarizes the recent evolution of the French research reactor capacity, describes the licensing process, the main safety criteria which are taken into consideration, and associated safety research. Some of the existing facilities underwent important modifications to comply with more severe safety criteria, increase the experimental capabilities or qualify new low-enrichment fuels for research reactors. At the end, a few considerations are given to the consequences of the Osiris core conversion

Safety management: a few techniques and their application

International Nuclear Information System (INIS)

Soundararajan, S.

2016-01-01

Industrial safety practice has grown in its stature tremendously since the age of industrial revolution. A number of modern techniques are available to strengthen design safety features, to review operational safety, and to critically appraise and upgrade practices of occupational safety and health management. This talk focuses on three prominent yet simple techniques and their usefulness in the overall safety management of a workplace. Any industrial set-up undergoes different stages in its life cycle-conceptual design, actual design, construction, fabrication and installation, commissioning, operation, shutdown/re-start up and decommissioning. Checklist procedure is a safety tool that can be applied at any of these stages. Thus it is a quite useful technique in safety management and accident prevention. It can serve as a form of approval from one step to another in the course of any routine or specific task. Safety Audit or Safety Review is a critical safety management appraisal tool. It gives a reasonable indication of how well a company's safety programme works, how hazards are recognised, how well employees are motivated and so on. It gives a clear picture about where a company stands as far as framing and implementation of its SHE policy is concerned. Each of the above tools is complementing each other and required to be applied at appropriate juncture in sustaining good safety management system at the workplace

EUS-Guided Vascular Procedures: A Literature Review

Directory of Open Access Journals (Sweden)

Tomislav Bokun

2013-01-01

Full Text Available Endoscopic ultrasound (EUS is continuously stepping into the therapeutic arena, simultaneously evolving in different directions, such as the management of pancreatic and biliary diseases, celiac neurolysis, delivering local intratumoral therapy, and EUS-guided endosurgery. EUS-guided vascular procedures are also challenging, considering the variety of vascular pathology, proximity of the vascular structures to the GI tract wall, high resolution, and real-time guidance offering an attractive access route and precise delivery of the intervention. The literature on vascular therapeutic EUS demonstrates techniques for the management of upper GI variceal and nonvariceal bleeding, pseudoaneurysms, and coiling and embolization procedures, as well as the creation of intrahepatic portosystemic shunts. The paucity of studies, diversity of study designs, and the number of animal model studies hamper a systematic approach to the conclusion and decision making important to clinicians and healthcare policy makers. Nevertheless, theoretical benefits and findings up to date concerning technical feasibility, efficacy, and safety of the procedures drive further research and development in this rather young therapeutic arena.

Integration of emergency action levels with Combustion Engineering Emergency Operating Procedures

International Nuclear Information System (INIS)

Faletti, D.W.; Jamison, J.D.

1985-09-01

This report documents the development of a method for integrating Emergency Action Levels (EALs) with plant-specific Emergency Operating Procedures (EOPs) using the Combustion Engineering Owners' Group Emergency Operating Procedure Technical Guidelines (CEOG EOPTFs). EALs are discrete conditions or values of plant operating parameters which, if exceeded, require declaration of an appropriate level of emergency. At most operating plants, the EALs and event classification procedures are totally separate from the Emergency Operating Procedures used by the plant staff to control the plant during abnormal conditions. Control room personnel using the EOPs to deal with abnormal plant conditions must recognize when plant safety is sufficiently degraded that an emergency declaration may be warranted, and then enter a separate classification procedure containing EALs for a number of plant conditions and parameters. The operator then compares the existing plant conditions to the EALs and makes an emergency declaration accordingly. Using the Combustion Engineering Owners' Group Technical Guidelines document, a set of emergency class definitions and criteria were developed based on the status of the three main fission product barriers (fuel cladding, primary coolant system and containment). The EOPTGs were then annotated with suggested guidance to a procedure writer. The proposed method was tested by applying it to the reactor accident sequences that were shown in the reactor safety study to dominate accident risk. The object of the test was to determine if an EAL set linked to the EOP annotations would produce timely and accurate classification of the risk-dominant sequences. 6 refs., 13 figs., 31 tabs

Bariatric Surgery Procedures

Science.gov (United States)

... Meetings of Interest Online Education Job Board CME Policies CBN Fellowship Certificate Research Grant Program Resources All Resources Approved Procedures Patient Safety Vignettes Dr. Mason Historical Library Governing Documents Guidelines Access and Insurance Position and ...

Steel Erection Safety. Module SH-39. Safety and Health.

Science.gov (United States)

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

This student module on steel erection safety is one of 50 modules concerned with job safety and health. This module identifies typical jobsite hazards encountered by steel erectors, as well as providing safe job procedures for general and specific construction activities. Following the introduction, 11 objectives (each keyed to a page in the text)…

Operating room data management: improving efficiency and safety in a surgical block.

Science.gov (United States)

Agnoletti, Vanni; Buccioli, Matteo; Padovani, Emanuele; Corso, Ruggero M; Perger, Peter; Piraccini, Emanuele; Orelli, Rebecca Levy; Maitan, Stefano; Dell'amore, Davide; Garcea, Domenico; Vicini, Claudio; Montella, Teresa Maria; Gambale, Giorgio

2013-03-11

European Healthcare Systems are facing a difficult period characterized by increasing costs and spending cuts due to economic problems. There is the urgent need for new tools which sustain Hospitals decision makers work. This project aimed to develop a data recording system of the surgical process of every patient within the operating theatre. The primary goal was to create a practical and easy data processing tool to give hospital managers, anesthesiologists and surgeons the information basis to increase operating theaters efficiency and patient safety. The developed data analysis tool is embedded in an Oracle Business Intelligence Environment, which processes data to simple and understandable performance tachometers and tables. The underlying data analysis is based on scientific literature and the projects teams experience with tracked data. The system login is layered and different users have access to different data outputs depending on their professional needs. The system is divided in the tree profile types Manager, Anesthesiologist and Surgeon. Every profile includes subcategories where operators can access more detailed data analyses. The first data output screen shows general information and guides the user towards more detailed data analysis. The data recording system enabled the registration of 14.675 surgical operations performed from 2009 to 2011. Raw utilization increased from 44% in 2009 to 52% in 2011. The number of high complexity surgical procedures (≥120 minutes) has increased in certain units while decreased in others. The number of unscheduled procedures performed has been reduced (from 25% in 2009 to 14% in 2011) while maintaining the same percentage of surgical procedures. The number of overtime events decreased in 2010 (23%) and in 2011 (21%) compared to 2009 (28%) and the delays expressed in minutes are almost the same (mean 78 min). The direct link found between the complexity of surgical procedures, the number of unscheduled procedures

Licensing procedures and safety criteria for research reactors in France

International Nuclear Information System (INIS)

Berry, J.L.; Lerouge, B.

1983-01-01

From the very beginning of the CEA up to now, a great deal of work has been devoted to the development and utilization of research reactors in France for the needs of fundamental and applied research, production of radioisotopes, and training. In recent years, new reactors were commissioned while others were decommissioned. Moreover some of the existing facilities underwent important modifications to comply with more severe safety criteria, increase the experimental capabilities or qualify new low-enrichment fuels for research reactors (Osiris and Isis). This paper summarizes the recent evolution of the French research reactor capacity, describes the licensing process, the main safety criteria which are taken into consideration, and associated safety research. At the end, a few considerations are given to the consequences of the Osiris core conversion. Safety of research reactors has been studied in detail and many improvements have been brought due to: implementation of a specific experimental program, and adaptation of safety principles and rules elaborated for power reactors. Research reactors in operation in France have been built within a 22 year period. Meanwhile, safety rules have been improved. Old reactors do not comply with all the new rules but modifications are continuously made: after analysis of incidents, when replacement of equipment has to be carried out, when an important modification (fuel conversion for example) is decided upon

Licensing procedures and safety criteria for research reactors in France

Energy Technology Data Exchange (ETDEWEB)

Berry, J L; Lerouge, B [Centre d' Etudes Nucleaires de Saclay (France)

1983-08-01

From the very beginning of the CEA up to now, a great deal of work has been devoted to the development and utilization of research reactors in France for the needs of fundamental and applied research, production of radioisotopes, and training. In recent years, new reactors were commissioned while others were decommissioned. Moreover some of the existing facilities underwent important modifications to comply with more severe safety criteria, increase the experimental capabilities or qualify new low-enrichment fuels for research reactors (Osiris and Isis). This paper summarizes the recent evolution of the French research reactor capacity, describes the licensing process, the main safety criteria which are taken into consideration, and associated safety research. At the end, a few considerations are given to the consequences of the Osiris core conversion. Safety of research reactors has been studied in detail and many improvements have been brought due to: implementation of a specific experimental program, and adaptation of safety principles and rules elaborated for power reactors. Research reactors in operation in France have been built within a 22 year period. Meanwhile, safety rules have been improved. Old reactors do not comply with all the new rules but modifications are continuously made: after analysis of incidents, when replacement of equipment has to be carried out, when an important modification (fuel conversion for example) is decided upon.

Rock mass and shaft concrete lining temperature measurement procedure: Final draft

International Nuclear Information System (INIS)

1986-10-01

This procedure document describes the equipment and procedures which will be used to obtain temperature data from within rock-mass and shaft linings at the Deaf Smith Exploratory Shaft Facility. Temperature measurement methods for instrument temperature correction, fluid temperature correction, heated surface monitoring and air temperature monitoring are outside the scope of this procedure, and are covered in the appropriate individual test procedures. Calibration, acceptance testing and the assignment of transducer reference numbers are outside the scope of this procedure. Section 2.0 provides a summary of the temperature measurement methods which will be employed, together with the measurement locations, environmental considerations and measurement requirements. Test layouts, including detailed descriptions of instruments, support requirements and detailed installation procedures are also presented. Section 3.0 describes the requirements for data recording, ADAS monitoring, and data reporting. Section 4.0 defines personnel responsibilities and qualifications. In addition a measurement and installation schedule is provided, and safety and contingency plans are described. Section 5.0 discusses management and quality assurance requirements. Cited references are listed in Section 6.0. 7 refs., 9 figs

Radiation safety

International Nuclear Information System (INIS)

Jain, Priyanka

2014-01-01

The use of radiation sources is a privilege; in order to retain the privilege, all persons who use sources of radiation must follow policies and procedures for their safe and legal use. The purpose of this poster is to describe the policies and procedures of the Radiation Protection Program. Specific conditions of radiation safety require the establishment of peer committees to evaluate proposals for the use of radionuclides, the appointment of a radiation safety officer, and the implementation of a radiation safety program. In addition, the University and Medical Centre administrations have determined that the use of radiation producing machines and non-ionizing radiation sources shall be included in the radiation safety program. These Radiation Safety policies are intended to ensure that such use is in accordance with applicable State and Federal regulations and accepted standards as directed towards the protection of health and the minimization of hazard to life or property. It is the policy that all activities involving ionizing radiation or radiation emitting devices be conducted so as to keep hazards from radiation to a minimum. Persons involved in these activities are expected to comply fully with the Canadian Nuclear Safety Act and all it. The risk of prosecution by the Department of Health and Community Services exists if compliance with all applicable legislation is not fulfilled. (author)

An investigation of safety attitude in a number of manufacturing companies in Urmia

Directory of Open Access Journals (Sweden)

Abolfazl Ghahramani

2016-12-01

Result: The results indicated that majority of participants (78.9 % had a moderate safety attitude level and the mean (±SD score of total safety attitude was 3.19 (±0.25. “Commitment to safety and participation in safety activities” and “safety talk and risk information communication” obtained the highest and lowest scores of safety attitude factors, with mean (SD of 3.97(±0.52 and 2.53(±0.58, respectively. In addition, the participants from private companies showed a better safety attitude than those of governmental companies (P-value<0.05. Managers and workers, who had previously received safety training, reported a different attitude toward various factors of safety attitude, in comparison with untrained groups. Conclusion: Since the majority of participants had a moderate safety attitude, this research suggests the study companies to attempt in order to increase the quantity and quality of safety training courses, as well as safety communication of managers and supervisors with workers for improving their attitude toward safety and subsequently decreasing occupational accidents.

Basic safety rule number no.2002-01

International Nuclear Information System (INIS)

2002-12-01

The purpose of this rule is to define acceptable methods for the development of probabilistic safety assessments(P.S.A.) and proven applications of P.S.A. for operating or future pressurized water reactors (PWR type reactors) of the French nuclear power programme, incorporating available French and international experience in this area. The standing group of experts for nuclear reactors has been consulted for the drafting of this rule. (N.C.)

The effect of facility characteristics on patient safety, patient experience, and service availability for procedures in non-hospital-affiliated outpatient settings: A systematic review.

Science.gov (United States)

Berglas, Nancy F; Battistelli, Molly F; Nicholson, Wanda K; Sobota, Mindy; Urman, Richard D; Roberts, Sarah C M

2018-01-01

Over recent decades, numerous medical procedures have migrated out of hospitals and into freestanding ambulatory surgery centers (ASCs) and physician offices, with possible implications for patient outcomes. In response, states have passed regulations for office-based surgeries, private organizations have established standards for facility accreditation, and professional associations have developed clinical guidelines. While abortions have been performed in office setting for decades, states have also enacted laws requiring that facilities that perform abortions meet specific requirements. The extent to which facility requirements have an impact on patient outcomes-for any procedure-is unclear. We conducted a systematic review to examine the effect of outpatient facility type (ASC vs. office) and specific facility characteristics (e.g., facility accreditation, emergency response protocols, clinician qualifications, physical plant characteristics, other policies) on patient safety, patient experience and service availability in non-hospital-affiliated outpatient settings. To identify relevant research, we searched databases of the published academic literature (PubMed, EMBASE, Web of Science) and websites of governmental and non-governmental organizations. Two investigators reviewed 3049 abstracts and full-text articles against inclusion/exclusion criteria and assessed the quality of 22 identified articles. Most studies were hampered by methodological challenges, with 12 of 22 not meeting minimum quality criteria. Of 10 studies included in the review, most (6) examined the effect of facility type on patient safety. Existing research appears to indicate no difference in patient safety for outpatient procedures performed in ASCs vs. physician offices. Research about specific facility characteristics is insufficient to draw conclusions. More and higher quality research is needed to determine if there is a public health problem to be addressed through facility

Investigating ethnic minorities' perceptions of safety climate in the construction industry.

Science.gov (United States)

Chan, Albert P C; Wong, Francis K W; Hon, Carol K H; Lyu, Sainan; Javed, Arshad Ali

2017-12-01

An increasing number of ethnic minorities (EMs) have been employed in the construction industry to alleviate severe labor shortages in many countries. Unfortunately, statistics show that EMs have higher fatal and non-fatal occupational injury rates than their local counterparts. However, EMs are often underrepresented in safety climate (SC) research as they are difficult to reach and gauge their perception. A positive relationship has been widely found between SC and safety performance. Understanding the safety perceptions of EMs helps to reduce injuries and improve their safety performance. Based on a sample of 320 EMs from 20 companies in the construction industry, exploratory factor analysis (EFA) and confirmatory factor analysis (CFA) were used to identify the SC factors of EMs, and validate the extracted factors, respectively. Multivariate analysis of variance was undertaken to examine mean differences in perceptions of SC by personal characteristics. Three SC factors for EMs encapsulating 16 variables were identified through EFA. The hypothesized CFA model for a three-factor structure derived from EFA showed a satisfactory goodness-of-fit, composite reliability, and construct validity. Three SC factors were identified, namely: (a) safety management commitment, safety resources, and safety communication; (b) employee's involvement and workmate's influence; and (c) perception of safety rules, procedures and risks. The perceptions of SC differed significantly by nationality, marital status, the number of family members supported, and drinking habit. This study reveals the perception of EMs toward SC. The findings highlight the areas for safety improvement and provide leading indicators for safety performance of EMs. The findings are also enlightening for countries with a number of EMs, such as the United Sates, the United Kingdom, Australia, Singapore, and the Middle East. Copyright © 2017. Published by Elsevier Ltd.

Complex intravenous anesthesia in interventional procedures

International Nuclear Information System (INIS)

Xie Zonggui; Hu Yuanming; Huang Yunlong; You Yong; Wu Juan; Huang Zengping; Li Jian

2006-01-01

Objective: To evaluate the value and safety of Diprivan and Fentany intravenous administration of analgesia in interventional procedures. Methods: Diprivan with Fentany intravenous administration for analgesia was used in eighty interventional procedures of sixty-five patients, without tracheal tube insertion. Vital signs including HR, BP, arterial oxygen saturation (SpO 2 ) and patients' reaction to operating were recorded. Results: Intravenous anesthesia was cared out successfully in eighty interventional procedures, with patients under sleeping condition during the operation, together with no pain and no agony memory of the procedure. The amount of Diprivan was 500±100 mg and Fentany was 0.2±0.025 mg. Mean arterial pressure and SpO 2 were 11.4±2.2 kPa, 10.6±2.1 kPa and 98±1.0, 96±1.5 respectively before and after ten minutes of the operation, with no significant difference. Conclusions: Diprivan with Fentany intravenous administration for interventional procedure analgesia possess good safety, painless and no agony memory of the procedure; therefor ought to be recommended. (authors)

Development and methodology of level 1 probability safety assessment at PUSPATI TRIGA Reactor

International Nuclear Information System (INIS)

Maskin, Mazleha; Tom, Phongsakorn Prak; Lanyau, Tonny Anak; Saad, Mohamad Fauzi; Ismail, Ahmad Razali; Abu, Mohamad Puad Haji; Brayon, Fedrick Charlie Matthew; Mohamed, Faizal

2014-01-01

As a consequence of the accident at the Fukushima Dai-ichi Nuclear Power Plant in Japan, the safety aspects of the one and only research reactor (31 years old) in Malaysia need be reviewed. Based on this decision, Malaysian Nuclear Agency in collaboration with Atomic Energy Licensing Board and Universiti Kebangsaan Malaysia develop a Level-1 Probability Safety Assessment on this research reactor. This work is aimed to evaluate the potential risks of incidents in RTP and at the same time to identify internal and external hazard that may cause any extreme initiating events. This report documents the methodology in developing a Level 1 PSA performed for the RTP as a complementary approach to deterministic safety analysis both in neutronics and thermal hydraulics. This Level-1 PSA work has been performed according to the procedures suggested in relevant IAEA publications and at the same time numbers of procedures has been developed as part of an Integrated Management System programme implemented in Nuclear Malaysia

Development and methodology of level 1 probability safety assessment at PUSPATI TRIGA Reactor

International Nuclear Information System (INIS)

Mazleha Maskin; Phongsakorn, P.T.; Tonny, A.L.; Fedrick, C.M.B.; Faizal Mohamed; Mohamad Fauzi Saad; Ahmad Razali Ismail; Mohamad Puad Haji Abu

2013-01-01

Full-text: As a consequence of the accident at the Fukushima Dai-ichi Nuclear Power Plant in Japan, the safety aspects of the one and only research reactor (31 years old) in Malaysia need be reviewed. Based on this decision, Malaysian Nuclear Agency in collaboration with Atomic Energy Licensing Board and Universiti Kebangsaan Malaysia develop a Level-1 Probability Safety Assessment on this research reactor. This work is aimed to evaluate the potential risks of incidents in RTP and at the same time to identify internal and external hazard that may cause any extreme initiating events. This report documents the methodology in developing a Level 1 PSA performed for the RTP as a complementary approach to deterministic safety analysis both in neutronics and thermal hydraulics. This Level-1 PSA work has been performed according to the procedures suggested in relevant IAEA publications and at the same time numbers of procedures has been developed as part of an Integrated Management System programme implemented in Nuclear Malaysia. (author)

X-ray and nuclear radiation facilities: personnel safety features

International Nuclear Information System (INIS)

Mason, W.J.; Pipes, E.W.; Rucker, T.R.; Smith, D.N.; West, C.M.

1976-10-01

The Oak Ridge Y-12 Plant is a research and production installation. The nature and versatility of this work require the use of a large number and variety of x-ray and radiographic sources for nondestructive testing and material analyses. Presently, there are over 80 x-ray generators in the plant, which range in size from small, portable units which operate at a less than 50 kilovolts potential and 0.1 milliampere current to an electron linear accelerator which operates at 12-million electron volts and produces a radiation beam of such intensity that it could deliver a lethal dose to man in a fraction of a minute. There are also almost 50 gamma and neutron sources in use in the plant. These units range in size from a few millicuries to several hundred curies. Although the radiation safety at each of these facilities was considered adequate, the administrative and maintenance procedures became unduly complicated. Accordingly, engineering standards and uniform operating procedures were considered necessary to alleviate these complications and, in so doing, provide an improved measure of radiation safety. Development and implementation of these standards are described and the general philosophy and approach to these standards are outlined. Use of a matrix (type of installation versus radiation safety feature) to facilitate equipment classification and personnel safety feature requirements is presented. Included is a set of the standards showing formats, matrices, etc., and the detailed standards for each safety feature

Analytical procedures. Pt. 1

International Nuclear Information System (INIS)

Weber, G.

1985-01-01

In analytical procedures (Boole procedures) there is certain to be a close relationship between the safety assessment and reliability assessment of technical facilities. The paper gives an overview of the organization of models, fault trees, the probabilistic evaluation of systems, evaluation with minimum steps or minimum paths regarding statistically dependent components and of systems liable to suffer different kinds of outages. (orig.) [de

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

Procedure proposed for performance of a probabilistic safety analysis for the event of ''Air plane crash''

International Nuclear Information System (INIS)

Hoffmann, H.H.

1998-01-01

A procedures guide for a probabilistic safety analysis for the external event 'Air plane crash' has been prepared. The method is based on analysis done within the framework of PSA for German NPPs as well as on international documents. Both crashes of military air planes and commercial air planes contribute to the plant risk. For the determination of the plant related crash rate the air traffic will be divided into 3 different categories of air traffic: - The landing and takeoff phase, - the airlane traffic and waiting loop traffic, - the free air traffic, and the air planes into different types and weight classes. (orig./GL) [de

Safety of research reactors. Topical issues paper no. 4

International Nuclear Information System (INIS)

Alcala-Ruiz, F.; Ferraz-Bastos, J.L.; Kim, S.C.; Voth, M.; Boeck, H.; Dimeglio, F.; Litai, D.

2001-01-01

Assessment of Research Reactors (INSARR) missions. The prime objective of these missions has been to conduct a comprehensive operational safety review of the research reactor facility and to verify compliance with the IAEA Safety Standards. The methods used during an INSARR mission have been collected and analysed. Some of the important issues identified are the following: general ageing of the facility; uncertain status of many research reactors (in extended shutdown); indefinite deferral of return to operation or decommissioning; inadequate regulatory supervision; insufficient systematic (periodic) reassessment of safety; lack of quality assurance (QA) programmes; lack of an international safety convention or arrangement; lack of financial support for safety measures (e.g. safety reassessment, safety upgrading, decommissioning) and utilization; lack of clear utilization programmes; inadequate emergency preparedness; inadequate safety documentation (e.g. safety analysis report, operating rules and procedures, emergency plan); inadequate funding of shutdown reactors; weak safety culture; loss of expertise and corporate memory; loss of information concerning radioactive materials contained in retired experimental devices stored in the facility indefinitely; obsolescence of equipment and lack of spare parts; inadequate training and qualifications of regulators and operators; safety implications of new fuel types. These issues have been addressed by the IAEA Secretariat and the chairman of the International Nuclear Safety Advisory Group (INSAG). INSAG has identified three major safety issues that are: the increasing age of research reactors, the number of research reactors that are not operating anymore but have not been decommissioned, and the number of research reactors in countries that do not have appropriate regulatory authorities. This issue paper discusses the concerns generated by an analysis of the results of INSARR missions and those expressed by INSAG. The

Characterization of aerosols produced by surgical procedures: A summary

Energy Technology Data Exchange (ETDEWEB)

Yeh, Hsu-Chi; Muggenburg, B.A.; Lundgren, D.L.; Turner, R.S.; Guilmette, R.A.; Snipes, M.B.; Jones, R.K.

1994-11-01

In many types of surgery, especially orthopedic procedures, power tools such as saws and drills are used. These tools can impart considerable energy in disrupting tissue and may produce aerosolized blood and material from bone and other tissues. Surgical lasers and electrocautery tools can also produce aerosols due to vaporization of blood and tissues. A number of studies have been reported concerning production of aerosols during surgery, and some of the aerosols produced may contain infectious materials. Health care workers have expressed concern and questions pertaining to the occupational transmission of blood-borne pathogens including the human immunodeficiency virus (HIV) and hepatitis B virus (HBV) via blood aerosols during surgery. Little or no data existed characterizing the aerosols produced performing surgical procedures. Because of this lack of data, the National Institute for Occupational Safety and Health funded a project at ITRI to assess the extent of aerosolization of blood and other tissues during surgical procedures in the laboratory and in a hospital surgical suite.

Characterization of aerosols produced by surgical procedures: A summary

International Nuclear Information System (INIS)

Yeh, Hsu-Chi; Muggenburg, B.A.; Lundgren, D.L.; Turner, R.S.; Guilmette, R.A.; Snipes, M.B.; Jones, R.K.

1994-01-01

In many types of surgery, especially orthopedic procedures, power tools such as saws and drills are used. These tools can impart considerable energy in disrupting tissue and may produce aerosolized blood and material from bone and other tissues. Surgical lasers and electrocautery tools can also produce aerosols due to vaporization of blood and tissues. A number of studies have been reported concerning production of aerosols during surgery, and some of the aerosols produced may contain infectious materials. Health care workers have expressed concern and questions pertaining to the occupational transmission of blood-borne pathogens including the human immunodeficiency virus (HIV) and hepatitis B virus (HBV) via blood aerosols during surgery. Little or no data existed characterizing the aerosols produced performing surgical procedures. Because of this lack of data, the National Institute for Occupational Safety and Health funded a project at ITRI to assess the extent of aerosolization of blood and other tissues during surgical procedures in the laboratory and in a hospital surgical suite

40 CFR 68.52 - Operating procedures.

Science.gov (United States)

2010-07-01

...) CHEMICAL ACCIDENT PREVENTION PROVISIONS Program 2 Prevention Program § 68.52 Operating procedures. (a) The... for safely conducting activities associated with each covered process consistent with the safety information for that process. Operating procedures or instructions provided by equipment manufacturers or...

Carpentry and Finishing Procedures. Building Maintenance. Module II. Instructor's Guide.

Science.gov (United States)

Hawk, Sam; Brunk, Art

This curriculum guide, keyed to the building maintenance competency profile developed by industry and education professionals, provides three units on carpentry and finishing procedures. The first unit, Exterior Carpentry, contains the following lessons: carpentry safety procedures, ladder and scaffolding safety, door installation/repair,…

Quantitative analysis of education effect by the number of contamination in an unsealed radioisotope facility

International Nuclear Information System (INIS)

Matsuda, Naoki; Yoshida, Masahiro; Takao, Hideaki; Kaneko, Mamoru; Yamaguchi, Yukiko; Okumura, Yutaka

2002-01-01

The educational program for radiation workers is essential for the safety of radiation facility that stands on radiation protection practice by each worker. However, there appears no distinct criterion for quantitative evaluation of the education effect on radiation safety. The effectiveness of education was assessed by the number and the frequency (number of contamination/number of users) of contamination, a major incident involving radioactive materials, based on the long-term contamination surveillance data from 1996 to 2001 in Nagasaki University Radioisotope Center. Facility staffs monitored contamination in the facility every day. In 1996 and 1997, the yearly total number and the frequency of contamination found in a molecular biology room, a most frequently-used laboratory, were 150 and 1.21, respectively. The improvement of education program, including introduction of technical procedures to avoid contamination in molecular biological experiments, pre-entry instruction for fresh workers to demonstrate radiation safety practices on site, and spreading the new concept 'contamination happens by all means' through the radiation workers, markedly reduced both the number and the frequency of contamination to 33 and 0.48, respectively. This reduction seemed to be attributable for two different reasons; improvement of skills to avoid contamination, and thorough execution of monitoring and decontamination. These results suggested that contamination was a possible criterion for evaluating effectiveness of education program for radiation workers. (author)

Implementation of safety parameter display system on Russian NPPs with WWER reactors

International Nuclear Information System (INIS)

Dounaev, V.G.; Neboyan, V.T.

1996-01-01

This report gives a short overview of the status of safety parameter display systems (SPDS) implementation on Russian NPPs with WWER reactors and also discusses the SPDS, which is being developed for Kalinin NPP. The assessment of the safety status of the plant is done by the continuous monitoring of six critical safety functions and the corresponding status trees. Besides, a number of additional functions are realized within the scope of KlnNPP, aimed at providing the operator and the safety engineer in the main control room with more detailed information in accidental situation as well as during the normal operation. In particular, these functions are: archiving, data logs and alarm handling, safety actions monitoring, mnemonic diagrams indicating the state of main technological equipment and basic plant parameters, reference data, etc. Also, the operator support function ''computerized procedures'' is included in the scope of SPDS. The basic SPDS implementation platform is ADACS of SEMA GROUP design. The system architecture includes two workstations in the main control room: one is for reactor operator and the other one for safety engineer. Every station has two CRT screens which ensures computerized procedures implementation and provides for extra services for the operator. Also, the information from the SPDS is transmitted to the local crisis centre and to the crisis centre of the State utility organization concern ''Rosenergoatom''. (author). 3 refs

Identifying the most significant indicators of the total road safety performance index.

Science.gov (United States)

Tešić, Milan; Hermans, Elke; Lipovac, Krsto; Pešić, Dalibor

2018-04-01

The review of the national and international literature dealing with the assessment of the road safety level has shown great efforts of the authors who tried to define the methodology for calculating the composite road safety index on a territory (region, state, etc.). The procedure for obtaining a road safety composite index of an area has been largely harmonized. The question that has not been fully resolved yet concerns the selection of indicators. There is a wide range of road safety indicators used to show a road safety situation on a territory. Road safety performance index (RSPI) obtained on the basis of a larger number of safety performance indicators (SPIs) enable decision makers to more precisely define the earlier goal- oriented actions. However, recording a broader comprehensive set of SPIs helps identify the strengths and weaknesses of a country's road safety system. Providing high quality national and international databases that would include comparable SPIs seems to be difficult since a larger number of countries dispose of a small number of identical indicators available for use. Therefore, there is a need for calculating a road safety performance index with a limited number of indicators (RSPI ln n ) which will provide a comparison of a sufficient quality, of as many countries as possible. The application of the Data Envelopment Analysis (DEA) method and correlative analysis has helped to check if the RSPI ln n is likely to be of sufficient quality. A strong correlation between the RSPI ln n and the RSPI has been identified using the proposed methodology. Based on this, the most contributing indicators and methodologies for gradual monitoring of SPIs, have been defined for each country analyzed. The indicator monitoring phases in the analyzed countries have been defined in the following way: Phase 1- the indicators relating to alcohol, speed and protective systems; Phase 2- the indicators relating to roads and Phase 3- the indicators relating to

Report on the results of the safety culture survey conducted in PNRI

International Nuclear Information System (INIS)

Garcia, Corazon M.; Nohay, Carl M.; Badinas, Nelson P.; Melendez, Johnylen V.; Parami, Vangeline K.

2001-01-01

An initial safety culture survey was conducted in the Philippine Nuclear Research Institute (PNRI). Sixty six (66) questionnaires as given in A. Adams and A. Williamson's Measurement of Safety Culture in the Nuclear Industry, UNSW, July 1999 were distributed to the different units of PNRI. The number of sets of survey sheets distributed to the different units corresponded to the number of personnel in the unit based on the information obtained from them. Results were obtained from only 33 respondents. ANSTO has been requested to analyze the results of this survey. While waiting for the results from ANSTO, we attempted to proceed with this analysis in order to learn and practice applying the procedure based on the reference cited above.The respondents from the PNRI showed on the overall neutral views towards safety and their work. Although a minority showed positive responses to safety while a small minority showed negative responses. A remarkable result is that all respondents show strong concern over the welfare of the institute, indicating that there is still a good chance for safety culture to be developed positively among the employees given the proper strategies for motivation. (author)

Probabilistic safety assessment

International Nuclear Information System (INIS)

Hoertner, H.; Schuetz, B.

1982-09-01

For the purpose of assessing applicability and informativeness on risk-analysis methods in licencing procedures under atomic law, the choice of instruments for probabilistic analysis, the problems in and experience gained in their application, and the discussion of safety goals with respect to such instruments are of paramount significance. Naturally, such a complex field can only be dealt with step by step, making contribution relative to specific problems. The report on hand shows the essentials of a 'stocktaking' of systems relability studies in the licencing procedure under atomic law and of an American report (NUREG-0739) on 'Quantitative Safety Goals'. (orig.) [de

Unresolved safety issues summary. Volume 3, Number 3. Aqua book

International Nuclear Information System (INIS)

1981-01-01

The 'Unresolved Safety Issues' summary is designed to provide the management of the Nuclear Regulatory Commission with a quarterly overview of the progress and plans for completion of generic tasks addressing Unresolved Safety Issues reported to Congress pursuant to section 210 of The Energy Reorganization Act of 1974 as amended. This summary utilizes data collected from the Office of Nuclear Reactor Regulation, Office of Nuclear Regulatory Research, and the National Laboratories and is prepared by the office of Management and Program Analysis. The definition of what constitutes completion of an unresolved safety issue (USI) has recently been expanded to include the implementation of the technical resolution. This is in acknowledgement of the fact that real safety benefits occur only after the implementation has taken place. The schedules in this book include a milestone at the end of each action plan which represents the initiation of the implementation process both with respect to incorporation of the technical resolution in the NRC official guidance or requirements and also the application of changes to individual operating plants. The schedule for implementation will not normally be included in the task action plan(s) for the resolution of a USI since the nature and extent of the activities necessary to accomplish the implementation cannot normally be reasonably determined prior to the determination of a technical resolution. The progress and status for implementation of unresolved safety issues for which a technical resolution has been completed are reported specifically in a separate table provided in this summary

Safety case: An international perspective

International Nuclear Information System (INIS)

Pescatore, C.; Voinis, S.

2002-01-01

In recent years, it has become more and more evident that repository development will involve a number of stages punctuated by interdependent decisions on whether and how to move to the next stage. These decisions require a clear and traceable presentation of technical arguments that will help in giving confidence in the feasibility and safety of the proposed concept. The depth of understanding and technical information available to support decisions will vary from step to step. A safety case is a key item to support the decision to move to the next stage in repository development. Progress is noted, in the past decade, in the performance and safety assessment areas, particularly in the methodologies for repository system analysis. Progress is also observed regarding the understanding of the natural system and its characterisation, treatment of uncertainties, and modelling. Some areas are under active development, e.g. the area of scenario development and analysis. Finally, to increase confidence, rigorous quality assurance procedures need to be implemented, as well as the factoring of the contribution of R and D in underground research laboratories. The paper summarises the lessons learnt within relevant NEA initiatives as they evolved over the course of a decade and now allow a comprehensive view of what constitutes a safety case. (author)

Safety and security profiles of industry networks used in safety- critical applications

Directory of Open Access Journals (Sweden)

Mária FRANEKOVÁ

2008-01-01

Full Text Available The author describes the mechanisms of safety and security profiles of industry and communication networks used within safety – related applications in technological and information levels of process control recommended according to standards IEC 61784-3,4. Nowadays the number of vendors of the safety – related communication technologies who guarantees besides the standard communication, the communication amongst the safety – related equipment according to IEC 61508 is increasing. Also the number of safety – related products is increasing, e. g. safety Fieldbus, safety PLC, safety curtains, safety laser scanners, safety buttons, safety relays and other. According to world survey the safety Fieldbus denoted the highest growth from all manufactured safety products.The main part of this paper is the description of the safety-related Fieldbus communication system, which has to guaranty Safety Integrity Level.

B plant/WESF integrated annual safety appraisal

International Nuclear Information System (INIS)

Anderson, J.K.

1990-12-01

This report provides the results of the Fiscal Year 1990 Annual Integrated Safety Appraisal of the B Plant and Waste Encapsulation and Storage Facility in the Hanford Site 200 East Area. The appraisal was conducted in August and September 1990, by the Defense Waste Disposal Safety group, in conjunction with Health Physics and Emergency Preparedness. Reports of these three organizations for their areas of responsibility are presented. The purpose of the appraisal was to determine if the areas being appraised meet US Department of Energy (DOE) and Westinghouse Hanford Company (WHC) requirements and current industry standards of good practice. A further purpose was to identify areas in which program effectiveness could be improved. In accordance with the guidance of WHC Management Requirements and Procedures 5.6, previously identified deficiencies which are being resolved by line management were not repeated as Findings or Observations unless progress or intended disposition was considered to be unsatisfactory. The overall assessment is that there are no major safety problems associated with current operations. Programs are in place to provide the necessary safety controls, evaluations, overviews, and support. In most respects these programs are being implemented effectively. However, there are a number of deficiencies in details of program design and implementation. The appraisal identified a total of 23 Findings and 27 Observations of deficiencies. All Observations are Seriousness Category 3. Fifteen Findings were Category 2 and 8 were Category 3. Most of the Category 2 Findings were so categorized on the basis of noncompliance with mandatory DOE Orders or WHC policies and procedures, rather than potential risk to personnel

Combustion Safety Simplified Test Protocol Field Study

Energy Technology Data Exchange (ETDEWEB)

Brand, L [Gas Technology Inst., Des Plaines, IL (United States); Cautley, D. [Gas Technology Inst., Des Plaines, IL (United States); Bohac, D. [Gas Technology Inst., Des Plaines, IL (United States); Francisco, P. [Gas Technology Inst., Des Plaines, IL (United States); Shen, L. [Gas Technology Inst., Des Plaines, IL (United States); Gloss, S. [Gas Technology Inst., Des Plaines, IL (United States)

2015-11-05

"9Combustions safety is an important step in the process of upgrading homes for energy efficiency. There are several approaches used by field practitioners, but researchers have indicated that the test procedures in use are complex to implement and provide too many false positives. Field failures often mean that the house is not upgraded until after remediation or not at all, if not include in the program. In this report the PARR and NorthernSTAR DOE Building America Teams provide a simplified test procedure that is easier to implement and should produce fewer false positives. A survey of state weatherization agencies on combustion safety issues, details of a field data collection instrumentation package, summary of data collected over seven months, data analysis and results are included. The project provides several key results. State weatherization agencies do not generally track combustion safety failures, the data from those that do suggest that there is little actual evidence that combustion safety failures due to spillage from non-dryer exhaust are common and that only a very small number of homes are subject to the failures. The project team collected field data on 11 houses in 2015. Of these homes, two houses that demonstrated prolonged and excessive spillage were also the only two with venting systems out of compliance with the National Fuel Gas Code. The remaining homes experienced spillage that only occasionally extended beyond the first minute of operation. Combustion zone depressurization, outdoor temperature, and operation of individual fans all provide statistically significant predictors of spillage.

A procedure for the analysis of errors of commission in a Probabilistic Safety Assessment of a nuclear power plant at full power

International Nuclear Information System (INIS)

Julius, J.; Jorgenson, E.; Parry, G.W.; Mosleh, A.M.

1995-01-01

This paper describes an analytical procedure that has been developed to facilitate the identification of errors of commission for inclusion in a Probabilistic Safety Assessment (PSA) of a nuclear power plant operating at full power. The procedure first identifies the opportunities for error by determining when operators are required to intervene to bring the plant to a safe condition following a transient, and then identifying under what conditions this is likely to occur using a model of the causes of error. In order to make the analysis practicable, a successive screening approach is used to identify those errors with the highest potential of occurrence. The procedure has been applied as part of a PSA study, and the results of that application are summarized. For the particular plant to which the procedure was applied, the conclusion was that, because of the nature of the procedures, the high degree of redundancy in the instrumentation, the operating practices, and the control board layouts, the potential for significant errors of commission is low

Reprocessing plants safety

International Nuclear Information System (INIS)

Davies, A.G.; Leighton, C.; Millington, D.

1989-01-01

The reprocessing of irradiated nuclear fuel at British Nuclear Fuels (BNFL) Sellafield site consists of a number of relatively self-contained activities carried out in separate plants across the site. The physical conditions and time scales applied in reprocessing and storage make it relatively benign. The potential for minor releases of radioactivity under fault conditioning is minimised by plant design definition of control procedures, training and supervision. The risks to both the general public and workforce are shown to be low with all the safety criteria being met. Normal operating conditions also have the potential for some occupational radiation exposure and the plant and workers are monitored continuously. Exposure levels have been reduced steadily and will continue to fall with plant improvements. (U.K.)

Operation safety at Ignalina NPP

International Nuclear Information System (INIS)

Zheltobriukh, G.

1999-01-01

An improvement of operational safety at Ignalina NPP covers: improvement of management structure and safety culture; symptom-based emergency operating procedures; staff training and full scope simulator; program of components ageing; metal inspection; improvement of fire safety. The first plan of Ignalina NPP Safety culture development for 1997 purposed to the SAR recommendation implementation was prepared and approved by the General Director

DASS: A decision aid integrating the safety parameter display system and emergency functional recovery procedures. Final report

International Nuclear Information System (INIS)

Johnson, S.E.

1984-08-01

Using a stand-alone developmental test-bed consisting of a minicomputer and a high-resolution color graphics computer, displays and supporting software incorporating advanced on-line decision-aid concepts were developed and evaluated. The advanced concepts embodied in displays designed for the operating crew of a PWR plant include: (1) an integrated display format which supports a top-down approach to problem detection, recovery planning, and control; (2) introduction of nonobservable plant parameters derived from first principles mass and energy balances as part of the displayed information; and (3) systematic processing and display of key success path (plant safety system) attributes. The prototype system, referred to as the PWR-DASS (Disturbance Analysis and Surveillance System), consists of 18 displays targeted for principal use by the control room systems manager. PWR-DASS was conceived to fulfill an operational void not fully supported by safety parameter display systems or reformulated emergency procedure guidelines. The results from the evaluation by licensed operators suggest that organization and display of desired critical safety function and success path information as incorporated in the PWR-DASS prototype can support the systems manager's overview. The results also point to the need for several refinements required for a field grade system, and to the need for a simulator-based evaluation of the prototype or its successor. (author)

49 CFR 385.321 - What failures of safety management practices disclosed by the safety audit will result in a...

Science.gov (United States)

2010-10-01

... disclosed by the safety audit will result in a notice to a new entrant that its USDOT new entrant... MOTOR CARRIER SAFETY REGULATIONS SAFETY FITNESS PROCEDURES New Entrant Safety Assurance Program § 385.321 What failures of safety management practices disclosed by the safety audit will result in a notice...

49 CFR 385.107 - The safety audit.

Science.gov (United States)

2010-10-01

... 49 Transportation 5 2010-10-01 2010-10-01 false The safety audit. 385.107 Section 385.107 Transportation Other Regulations Relating to Transportation (Continued) FEDERAL MOTOR CARRIER SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION FEDERAL MOTOR CARRIER SAFETY REGULATIONS SAFETY FITNESS PROCEDURES Safety Monitoring System for Mexico-Domicile...

40 CFR 240.209-3 - Recommended procedures: Operations.

Science.gov (United States)

2010-07-01

... Occupational Respiratory Disease, National Institute for Occupational Safety and Health, Morgantown, W. Va. (c) Training in first aid practices and emergency procedures should be given all personnel. (d) Personal safety devices such as hard hats, gloves, safety glasses, and footwear should be provided for facility employees...

Medical interventional procedures--reducing the radiation risks

International Nuclear Information System (INIS)

Cousins, C.; Sharp, C.

2004-01-01

Over the last 40 years, the number of percutaneous interventional procedures using radiation has increased significantly, with many secondary care clinicians using fluoroscopically guided techniques. Many procedures can deliver high radiation doses to patients and staff, with the potential to cause immediate and delayed radiation effects. The challenge for interventionists is to maximize benefit, whilst minimizing radiation risk to patients and staff. Non-radiologist clinicians are often inadequately trained in radiation safety and radiobiology. However, clinical governance and legislation now requires a more rigorous approach to protecting patients and staff. Protection can be ensured, and risks can be controlled, by appropriate design, procurement and commissioning of equipment; quality assurance; and optimal operational technique, backed by audit. Interventionists need knowledge and skills to reduce the risks. Appropriate training should include awareness of the potential for radiation injury, equipment operational parameters, doses measurement and recording methods and dose reduction techniques. Clinical governance requires informed consent, appropriate patient counselling and follow-up

Medical interventional procedures--reducing the radiation risks

Energy Technology Data Exchange (ETDEWEB)

Cousins, C. E-mail: claire.cousins@addenbrookes.nhs.uk; Sharp, C

2004-06-01

Over the last 40 years, the number of percutaneous interventional procedures using radiation has increased significantly, with many secondary care clinicians using fluoroscopically guided techniques. Many procedures can deliver high radiation doses to patients and staff, with the potential to cause immediate and delayed radiation effects. The challenge for interventionists is to maximize benefit, whilst minimizing radiation risk to patients and staff. Non-radiologist clinicians are often inadequately trained in radiation safety and radiobiology. However, clinical governance and legislation now requires a more rigorous approach to protecting patients and staff. Protection can be ensured, and risks can be controlled, by appropriate design, procurement and commissioning of equipment; quality assurance; and optimal operational technique, backed by audit. Interventionists need knowledge and skills to reduce the risks. Appropriate training should include awareness of the potential for radiation injury, equipment operational parameters, doses measurement and recording methods and dose reduction techniques. Clinical governance requires informed consent, appropriate patient counselling and follow-up.

49 CFR 229.105 - Steam generator number.

Science.gov (United States)

2010-10-01

... 49 Transportation 4 2010-10-01 2010-10-01 false Steam generator number. 229.105 Section 229.105..., DEPARTMENT OF TRANSPORTATION RAILROAD LOCOMOTIVE SAFETY STANDARDS Safety Requirements Steam Generators § 229.105 Steam generator number. An identification number shall be marked on the steam generator's...

9 CFR 381.311 - Recall procedure.

Science.gov (United States)

2010-01-01

... CERTIFICATION POULTRY PRODUCTS INSPECTION REGULATIONS Canning and Canned Products § 381.311 Recall procedure... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Recall procedure. 381.311 Section 381.311 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE AGENCY...

A study on optimization of the nuclear safety system

International Nuclear Information System (INIS)

Lee, Sang Hoon; Koh, Byung Joon; Kim, Jin Soo; Kim, Byoung Do; Cho, Seong Won; Kwon, Seog Kwon; Choi, Kwang Sik

1986-12-01

The number of nuclear facilities (nuclear power plants, research reactors, nuclear fuel facilities) under construction or in operation in Korea continues to increase and this has brought about increased importance and concerns toward nuclear safety in Korea. Also, domestic nuclear related organizations are increasingly carrying out the design/construction of nuclear power plants and the development /supply of nuclear fuels. In order to flexibly respond to these changes and to suggest direction to take, it is necessary to re-examine the current nuclear safety regulation system. This study is carried out in two stages and this report describes the results of the analysis and the assessment of the nuclear licencing system of such foreign countries as sweden and German, as the first of the two. In this regard, this study includes the analysis on the backgrounds on the choice of nuclear licensing system, the analysis on the licensing procedures, the analysis on the safety inspection system and the enforcement laws, the analysis on the structure and function of the regulatory, business and research organizations as well as the analysis on the relationship between the safety research and the regulatory duties. In this study, the German safety inspection system and the enforcement procedures and the Swedish nuclear licensing system are analyzed in detail. By comparing and assessing the finding with the current Korea Nuclear Licensing System, this study points out some reform measures of the Korean system that needs to improved. With the changing situations in mind, this study aims to develop the nuclear safety regulation system optimized for Korean situation by re-examining the current regulation system. (Author)

Safety indicators: an efficient tool for a better safety

International Nuclear Information System (INIS)

Aufort, P.; Lars, R.

1993-01-01

Safety indicators based on the examination of the Operating Technical Specifications have been defined with the aim of following the in-operation safety level of French nuclear power plants. These safety indicators are operation feedback tools which permit the a posteriori justification and the adjustment of actual procedures. They would allow detection of an abnormal unavailability occurrence rate or a situation revealing a potential safety problem. So, data acquisition, processing, analysis and display software allowing trend analysis of these indicators has been developed so far as: a reflexion tool for the power plant operators about the safety instructions and the adjustment of preventive maintenance, and a help for decision making at a national level for the examination and the improvement of Operating Technical Specifications. This paper presents the objectives of these safety indicators, the processing tool associated, the preliminary results obtained and more elaborate processing of these indicators. These safety indicators may be very useful in framing probabilistic safety assessments. (author)

Preharvest food safety.

Science.gov (United States)

Childers, A B; Walsh, B

1996-07-23

Preharvest food safety is essential for the protection of our food supply. The production and transport of livestock and poultry play an integral part in the safety of these food products. The goals of this safety assurance include freedom from pathogenic microorganisms, disease, and parasites, and from potentially harmful residues and physical hazards. Its functions should be based on hazard analysis and critical control points from producer to slaughter plant with emphasis on prevention of identifiable hazards rather than on removal of contaminated products. The production goal is to minimize infection and insure freedom from potentially harmful residues and physical hazards. The marketing goal is control of exposure to pathogens and stress. Both groups should have functional hazard analysis and critical control points management programs which include personnel training and certification of producers. These programs must cover production procedures, chemical usage, feeding, treatment practices, drug usage, assembly and transportation, and animal identification. Plans must use risk assessment principles, and the procedures must be defined. Other elements would include preslaughter certification, environmental protection, control of chemical hazards, live-animal drug-testing procedures, and identification of physical hazards.

Safety culture in nuclear installations. Management of safety and safety culture in Indian NPPs

International Nuclear Information System (INIS)

Rawal, S.C.

2002-01-01

Nuclear Power Corporation Of India Ltd. (NPCIL) is a company owned by Government of India and is responsible for Design, Construction, Commissioning, Operation and Decommissioning of Nuclear Power plants in India. Presently, a total of 13 Nuclear power Stations are in operation with an installed capacity of 2620 MWe and 2 VVR type PWR Units of 1000 MWe capacity each, 2 PHWR type units of 500 MWe capacity each and 4 PHWR type 220 MWe capacity each are under construction. NPPs generation capacity has been increased from 70% to 85% in the span Of last 7 years with high level of safety standards. This could be achieved through Management commitment towards building a strong Safety Culture. Safety culture is that assembly of characteristics and attitudes in organisation and individuals which establishes that as an overriding priority nuclear plant safety issues receives the attention warranted by their significance. This definition of safety culture brings out two major components in its manifestation. The framework within which individuals within the organisation works.The attitude and response of individual towards the safety issues over productivity and economics in the organisational work practices. The two attributes of safety culture are built in and upgraded in each individuals through special training at the time of entry in the organisation and later through in built procedures in the work practices, motivation and encouragement for free participation of each individuals. Individuals are encouraged to participate in Quality circle teams at the sectional level and review of safety proposal originated by individuals in Station operation Review Committee at Station level, in addition to this to continuously enhance the safety culture, refresher training courses are being organised at regular intervals. The safety related proposals are categorised in to two namely: Proposals from Operating Plants, and Proposals from projects and Design. The concept of safety

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

International Nuclear Information System (INIS)

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

2001-01-01

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

Safety, danger and catastrophe inevitability in operation of safety-critical software algorithms: a possible new look at software safety analysis

International Nuclear Information System (INIS)

Povyakalo, A.A.

2000-01-01

The paper provides basic definitions and describes the basic procedure of the Formal Qualitative Safety Analysis (FQSA) of critical software algorithms. The procedure is described by C-based pseudo-code. It uses the notion of weakest precondition and representation of a given critical algorithm by a Gurevich's Abstract State Mashine (GASM). For a given GASM and a given Catastrophe Condition the procedure results in a Catastrophe Inevitability Condition (it means that every sequence of algorithm steps lead to a catastrophe early or late), Danger Condition (it means that next step may lead to a catastrophe or make a catastrophe to be inevitable, but a catastrophe may be prevented yet), Safety Condition (it means that a next step can not lead to a catastrophe or make a catastrophe to be inevitable). The using of proposed procedure is illustrated by a simplest test example of algorithm. The FQSA provides a logical basis for PSA of critical algorithm. (author)

Implementing and measuring safety goals and safety culture. 4. Utility's Activities for Better Safety Culture After the JCO Accident

International Nuclear Information System (INIS)

Omoto, Akira

2001-01-01

three activities described below. As a part of self-diagnosis of organizational behavior and an individual's factors influencing safety, measurement was carried out by asking questions to every employee at the station, i.e., 21 questions asking if we are appropriately implementing safety culture 'standards' as set forth in INSAG-4 (Ref. 2). The purpose was twofold: to educate about INSAG-4 and to find areas for improvement. The results indicated that employees want to learn more about (a) the background for the specific actions required/prescribed in the procedures/guidelines and (b) how things go wrong if they do not strictly follow the procedures/guidelines. These were important findings, which led to the reconstruction of the on-site education and training. Considering that employees should be well informed on safety culture; management's policy; and lessons learned from incidents, domestic or international, we started the bimonthly magazine Safety Culture. The first publication included articles on 'Lessons Learned from JCO', 'The Results from the Self- Diagnosis', 'Lessons from an Incident at Hunterston NPS (LOOP Followed by Operator Actions for Safe Shutdown)', and others. The on-site training system has two elements: on-the-job training and off-the-job study with classroom and hands-on training. Most of the employees are trained at the On-Site Training Center with equipment and are qualified for specific job categories. Training of operators has its own lengthy program. Given the foregoing findings, we (a) started lectures on JCO lessons learned, (b) modified the educational system at the On-Site Training Center to nurture the employees with well-balanced knowledge and thinking (Fig. 1), and (c) prepared documents that describe the background and reasons for the actions required/prescribed in the procedures/guidelines for use in on-the-job training. The important point to be remembered about the JCO accident is that the criticality safety at this facility

40 CFR 243.201 - Safety.

Science.gov (United States)

2010-07-01

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

Safety design

International Nuclear Information System (INIS)

Kunitomi, Kazuhiko; Shiozawa, Shusaku

2004-01-01

JAERI established the safety design philosophy of the HTTR based on that of current reactors such as LWR in Japan, considering inherent safety features of the HTTR. The strategy of defense in depth was implemented so that the safety engineering functions such as control of reactivity, removal of residual heat and confinement of fission products shall be well performed to ensure safety. However, unlike the LWR, the inherent design features of the high-temperature gas-cooled reactor (HTGR) enables the HTTR meet stringent regulatory criteria without much dependence on active safety systems. On the other hand, the safety in an accident typical to the HTGR such as the depressurization accident initiated by a primary pipe rupture shall be ensured. The safety design philosophy of the HTTR considers these unique features appropriately and is expected to be the basis for future Japanese HTGRs. This paper describes the safety design philosophy and safety evaluation procedure of the HTTR especially focusing on unique considerations to the HTTR. Also, experiences obtained from an HTTR safety review and R and D needs for establishing the safety philosophy for the future HTGRs are reported

Selection and verification of safety parameters in safety parameter display system for nuclear power plants

International Nuclear Information System (INIS)

Zhang Yuangfang

1992-02-01

The method and results for safety parameter selection and its verification in safety parameter display system of nuclear power plants are introduced. According to safety analysis, the overall safety is divided into six critical safety functions, and a certain amount of safety parameters which can represent the integrity degree of each function and the causes of change are strictly selected. The verification of safety parameter selection is carried out from the view of applying the plant emergency procedures and in the accident man oeuvres on a full scale nuclear power plant simulator

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

Science.gov (United States)

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

2015-11-01

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

Compendium of computer codes for the safety analysis of LMFBR's

International Nuclear Information System (INIS)

1975-06-01

A high level of mathematical sophistication is required in the safety analysis of LMFBR's to adequately meet the demands for realism and confidence in all areas of accident consequence evaluation. The numerical solution procedures associated with these analyses are generally so complex and time consuming as to necessitate their programming into computer codes. These computer codes have become extremely powerful tools for safety analysis, combining unique advantages in accuracy, speed and cost. The number, diversity and complexity of LMFBR safety codes in the U. S. has grown rapidly in recent years. It is estimated that over 100 such codes exist in various stages of development throughout the country. It is inevitable that such a large assortment of codes will require rigorous cataloguing and abstracting to aid individuals in identifying what is available. It is the purpose of this compendium to provide such a service through the compilation of code summaries which describe and clarify the status of domestic LMFBR safety codes. (U.S.)

Fire Safety Trianing in Health Care Institutions.

Science.gov (United States)

American Hospital Association, Chicago, IL.

The manual details the procedures to be followed in developing and implementing a fire safety plan. The three main steps are first, to organize; second, to set up a procedure and put it in writing; and third, to train and drill employees and staff. Step 1 involves organizing a safety committee, appointing a fire marshall, and seeking help from…

Implication of human factors in terms of safety

International Nuclear Information System (INIS)

Furuta, Kazuo

2001-01-01

A critical accident of JCO occurred on September 30, 1999 gave a large impact not only to common society but also to nuclear energy field. This accident occurred by direct reason perfectly out of forecasting of the participants of nuclear energy, where a company made up a guideline violating from business allowance and safety rule and workmen also operated under a procedure out of the guideline. After the accident, a number of countermeasures on equipments, rules, and regulations were carried out, but discussion on software such as their operating methods, concrete regulation on business and authority of operators, and training of specialists seems to be much late. Safety is a problem on a complex system, containing not only hardware but also software such as human, organization, society, and so on. Then, here was discussed on a problem directly faced by conventional safety, engineering centering at hardware through thinking of a problem on human factors. (G.K.)

French concepts of ''passive safety''

International Nuclear Information System (INIS)

Dennielou, Y.; Serret, M.

1990-01-01

N 4 model, the French 1400 MW PWR of the 90's, exhibits many advanced features. As far as safety is concerned, the fully computerized control room design takes advantage of the operating experience feedback and largely improves the man machine interface. New post-accident procedures have been developed (the so-called ''physical states oriented procedures''). A complete consistent set of ''Fundamental Safety Rules'' have been issued. This however doesn't imply any significant modification of standard PWR with regard to the passive aspects of safety systems or functions. Nevertheless, traditional PWR safety systems largely use passive aspects: natural circulation, reactivity coefficients, gravity driven control rods, injection accumulators, so on. Moreover, probability calculations allow for comparison between the respective contributions of passive and of active failures. In the near future, eventual options of future French PWRs to be commissioned after 2000 will be evaluated; simplification, passive and forgiving aspects of safety systems will be thoroughly considered. (author)

Decommissioning licensing procedure

International Nuclear Information System (INIS)

Perello, M.

1979-01-01

Decommissioning or closure of a nuclear power plant, defined as the fact that takes place from the moment that the plant stops producing for the purpose it was built, is causing preocupation. So this specialist meeting on Regulatory Review seems to be the right place for presenting and discusing the need of considering the decommissioning in the safety analysis report. The main goal of this paper related to the licensing procedure is to suggest the need of a new chapter in the Preliminary Safety Analysis Report (P.S.A.R.) dealing with the decommissioning of the nuclear power plant. Therefore, after a brief introduction the problem is exposed from the point of view of nuclear safety and finally a format of the new chapter is proposed. (author)

Safety Precautions and Operating Procedures in an (A)BSL-4 Laboratory: 2. General Practices.

Science.gov (United States)

Mazur, Steven; Holbrook, Michael R; Burdette, Tracey; Joselyn, Nicole; Barr, Jason; Pusl, Daniela; Bollinger, Laura; Coe, Linda; Jahrling, Peter B; Lackemeyer, Matthew G; Wada, Jiro; Kuhn, Jens H; Janosko, Krisztina

2016-10-03

Work in a biosafety level 4 (BSL-4) containment laboratory requires time and great attention to detail. The same work that is done in a BSL-2 laboratory with non-high-consequence pathogens will take significantly longer in a BSL-4 setting. This increased time requirement is due to a multitude of factors that are aimed at protecting the researcher from laboratory-acquired infections, the work environment from potential contamination and the local community from possible release of high-consequence pathogens. Inside the laboratory, movement is restricted due to air hoses attached to the mandatory full-body safety suits. In addition, disinfection of every item that is removed from Class II biosafety cabinets (BSCs) is required. Laboratory specialists must be trained in the practices of the BSL-4 laboratory and must show high proficiency in the skills they are performing. The focus of this article is to outline proper procedures and techniques to ensure laboratory biosafety and experimental accuracy using a standard viral plaque assay as an example procedure. In particular, proper techniques to work safely in a BSL-4 environment when performing an experiment will be visually emphasized. These techniques include: setting up a Class II BSC for experiments, proper cleaning of the Class II BSC when finished working, waste management and safe disposal of waste generated inside a BSL-4 laboratory, and the removal of inactivated samples from inside a BSL-4 laboratory to the BSL-2 laboratory.

Long-term safety and feasibility of three-vessel multimodality intravascular imaging in patients with ST-elevation myocardial infarction

DEFF Research Database (Denmark)

Taniwaki, Masanori; Radu, Maria D; Garcia-Garcia, Hector M

2015-01-01

We assessed the feasibility and the procedural and long-term safety of intracoronary (i.c) imaging for documentary purposes with optical coherence tomography (OCT) and intravascular ultrasound (IVUS) in patients with acute ST-elevation myocardial infarction (STEMI) undergoing primary PCI in the s......We assessed the feasibility and the procedural and long-term safety of intracoronary (i.c) imaging for documentary purposes with optical coherence tomography (OCT) and intravascular ultrasound (IVUS) in patients with acute ST-elevation myocardial infarction (STEMI) undergoing primary PCI...... in the setting of IBIS-4 study. IBIS4 (NCT00962416) is a prospective cohort study conducted at five European centers including 103 STEMI patients who underwent serial three-vessel coronary imaging during primary PCI and at 13 months. The feasibility parameter was successful imaging, defined as the number...... of pullbacks suitable for analysis. Safety parameters included the frequency of peri-procedural complications, and major adverse cardiac events (MACE), a composite of cardiac death, myocardial infarction (MI) and any clinically-indicated revascularization at 2 years. Clinical outcomes were compared...

Nuclear safety, Volume 38, Number 1, January--March 1997

Energy Technology Data Exchange (ETDEWEB)

None

1997-03-01

This journal contains nine articles which fall under the following categories: (1) general safety considerations; (2) control and instrumentation; (3) design features (4) environmental effects; (5) US Nuclear Regulatory Commission information and analyses; and (6) recent developments.

DOT-7A packaging test procedure

International Nuclear Information System (INIS)

Kelly, D.L.

1995-01-01

This test procedure documents the steps involved with performance testing of Department of Transportation Specification 7A (DOT-7A) Type A packages. It includes description of the performance tests, the personnel involved, appropriate safety considerations, and the procedures to be followed while performing the tests. Westinghouse Hanford Company (WHC) is conducting the evaluation and testing discussed herein for the Department of Energy-Headquarters, Division of Quality Verification and Transportation Safety (EH-321). Please note that this report is not in WHC format. This report is being submitted through the Engineering Documentation System so that it may be used for reference and information purposes

Post-earthquake building safety inspection: Lessons from the Canterbury, New Zealand, earthquakes

Science.gov (United States)

Marshall, J.; Jaiswal, Kishor; Gould, N.; Turner, F.; Lizundia, B.; Barnes, J.

2013-01-01

The authors discuss some of the unique aspects and lessons of the New Zealand post-earthquake building safety inspection program that was implemented following the Canterbury earthquake sequence of 2010–2011. The post-event safety assessment program was one of the largest and longest programs undertaken in recent times anywhere in the world. The effort engaged hundreds of engineering professionals throughout the country, and also sought expertise from outside, to perform post-earthquake structural safety inspections of more than 100,000 buildings in the city of Christchurch and the surrounding suburbs. While the building safety inspection procedure implemented was analogous to the ATC 20 program in the United States, many modifications were proposed and implemented in order to assess the large number of buildings that were subjected to strong and variable shaking during a period of two years. This note discusses some of the key aspects of the post-earthquake building safety inspection program and summarizes important lessons that can improve future earthquake response.

Laboratory errors and patient safety.

Science.gov (United States)

Miligy, Dawlat A

2015-01-01

Laboratory data are extensively used in medical practice; consequently, laboratory errors have a tremendous impact on patient safety. Therefore, programs designed to identify and reduce laboratory errors, as well as, setting specific strategies are required to minimize these errors and improve patient safety. The purpose of this paper is to identify part of the commonly encountered laboratory errors throughout our practice in laboratory work, their hazards on patient health care and some measures and recommendations to minimize or to eliminate these errors. Recording the encountered laboratory errors during May 2008 and their statistical evaluation (using simple percent distribution) have been done in the department of laboratory of one of the private hospitals in Egypt. Errors have been classified according to the laboratory phases and according to their implication on patient health. Data obtained out of 1,600 testing procedure revealed that the total number of encountered errors is 14 tests (0.87 percent of total testing procedures). Most of the encountered errors lay in the pre- and post-analytic phases of testing cycle (representing 35.7 and 50 percent, respectively, of total errors). While the number of test errors encountered in the analytic phase represented only 14.3 percent of total errors. About 85.7 percent of total errors were of non-significant implication on patients health being detected before test reports have been submitted to the patients. On the other hand, the number of test errors that have been already submitted to patients and reach the physician represented 14.3 percent of total errors. Only 7.1 percent of the errors could have an impact on patient diagnosis. The findings of this study were concomitant with those published from the USA and other countries. This proves that laboratory problems are universal and need general standardization and bench marking measures. Original being the first data published from Arabic countries that

DISPELLING MYTHS AND MISCONCEPTIONS TO IMPLEMENT A SAFETY CULTURE

Energy Technology Data Exchange (ETDEWEB)

Potts, T. Todd; Smith, Ken; Hylko, James M.

2003-02-27

Industrial accidents are typically reported in terms of technological malfunctions, ignoring the human element in accident causation. However, over two-thirds of all accidents are attributable to human and organizational factors (e.g., planning, written procedures, job factors, training, communication, and teamwork), thereby affecting risk perception, behavior and attitudes. This paper reviews the development of WESKEM, LLC's Environmental, Safety, and Health (ES&H) Program that addresses human and organizational factors from a top-down, bottom-up approach. This approach is derived from the Department of Energy's Integrated Safety Management System. As a result, dispelling common myths and misconceptions about safety, while empowering employees to ''STOP work'' if necessary, have contributed to reducing an unusually high number of vehicle, ergonomic and slip/trip/fall incidents successfully. Furthermore, the safety culture that has developed within WESKEM, LLC's workforce consists of three common characteristics: (1) all employees hold safety as a value; (2) each individual feels responsible for the safety of their co-workers as well as themselves; and (3) each individual is willing and able to ''go beyond the call of duty'' on behalf of the safety of others. WESKEM, LLC as a company, upholds the safety culture and continues to enhance its existing ES&H program by incorporating employee feedback and lessons learned collected from other high-stress industries, thereby protecting its most vital resource - the employees. The success of this program is evident by reduced accident and injury rates, as well as the number of safe work hours accrued while performing hands-on field activities. WESKEM, LLC (Paducah + Oak Ridge) achieved over 800,000 safe work hours through August 2002. WESKEM-Paducah has achieved over 665,000 safe work hours without a recordable injury or lost workday case since it started operations on

A regulatory frame for safety digital systems in nuclear power plants

International Nuclear Information System (INIS)

Mozas Garcia, A.

1998-01-01

The paper focuses on Spanish experience regarding software based systems for safety applications from the regulator's point of view. It describes the actual situation in Spain, number and models of reactors, modernization projects, digital systems implemented and licensing documentation and processes already followed by some upgrading projects. The paper wonders what documents should be required for safety and reliability demonstration of a safety system, when they should be reviewed, and what other activities may be necessary to acquire confidence on a particular system. It describes Spanish laws regarding nuclear safety under which, national standards from the NPP design original country apply to nuclear reactors in Spain. It finally suggests that an international standard jointly used by system manufacturers, nuclear licensees and nuclear safety authorities, both from the country where the NPP is installed, and from the original design country, should be developed so that rapid and easy agreement on licensing issues is reached among all parties. The last part of the paper describes the licensing approach proposed by CSN (Spanish Nuclear Safety Authority). It is still under development and it is based on previous experience on digital systems for non-safety applications. It consists of constructing several frames: 1) databases of existing software based systems, 2) guides for inspection and 3) questionnaires for helping in verification and validation activities evaluation. The scope is to establish a well defined procedure that helps in evaluating the particular system. However, in order for such a procedure to be useful, both regulators and utilities and, perhaps also system manufacturers, should agree on it. Joint CSN-utilities working groups may be suitable for such a purpose. (author)

Development of safety factors to be used for evaluation of cracked nuclear components

International Nuclear Information System (INIS)

Brickstad, B.; Bergman, M.

1996-10-01

A modified concept for safety evaluation is introduced which separately accounts for the failure mechanisms fracture and plastic collapse. For application on nuclear components a set of safety factors are also proposed that retain the safety margins expressed in ASME, section III and XI. By performing comparative studies of the acceptance levels for surface cracks in pipes and a pressure vessel, it is shown that some of the anomalies connected with the old safety procedures are removed. It is the authors belief that the outlined safety evaluation procedure has the capability of treating cracks in a consistent way and that the procedure together with the proposed safety factors fulfill the basic safety requirements for nuclear components. Hopefully, it is possible in the near future to develop a probabilistic safety assessment procedure in Sweden, which enables a systematic treatment of uncertainties in the involved data. 14 refs

Standard Procedure for Grid Interaction Analysis

International Nuclear Information System (INIS)

Svensson, Bertil; Lindahl, Sture; Karlsson, Daniel; Joensson, Jonas; Heyman, Fredrik

2015-01-01

Grid events, simultaneously affecting all safety related auxiliary systems in a nuclear power plant, are critical and must be carefully addressed in the design, upgrading and operational processes. Up to now, the connecting grid has often been treated as either fully available or totally unavailable, and too little attention has been paid to specify the grid performance criteria. This paper deals with standard procedures for grid interaction analysis, to derive tools and criteria to handle grid events challenging the safety systems of the plant. Critical external power system events are investigated and characterised, with respect to severity and rate of occurrence. These critical events are then grouped with respect to impact on the safety systems, when a disturbance propagates into the plant. It is then important to make sure that 1) the impact of the disturbance will never reach any critical system, 2) the impact of the disturbance will be eliminated before it will hurt any critical system, or 3) the critical systems will be proven to be designed in such a way that they can withstand the impact of the disturbance, and the associated control and protection systems can withstand voltage and frequency transients associated with the disturbances. A number of representative disturbance profiles, reflecting connecting grid conditions, are therefore derived, to be used for equipment testing. (authors)

Evaluation of periodic safety status analyses

International Nuclear Information System (INIS)

Faber, C.; Staub, G.

1997-01-01

In order to carry out the evaluation of safety status analyses by the safety assessor within the periodical safety reviews of nuclear power plants safety goal oriented requirements have been formulated together with complementary evaluation criteria. Their application in an inter-disciplinary coopertion covering the subject areas involved facilitates a complete safety goal oriented assessment of the plant status. The procedure is outlined briefly by an example for the safety goal 'reactivity control' for BWRs. (orig.) [de

Methodology for comprehensive patient, worker and public radiation protection considerations while introducing new medical procedures

International Nuclear Information System (INIS)

Neeman, E.; Keren, M.

2001-01-01

Patient protection is a major consideration while introducing new medical procedure. But protection of the workers and the public should be considered too. A methodology of combining non-patient radiation protection considerations with the introduction of new medical procedures is described. The new medical procedure was the Intracoronary Gamma Irradiation for the Prevention of Restenosis by using Iridium 192 gamma radiation sources. The usual authors' responsibility is the licensing of the use of radioactive materials while keeping public protection. According to this responsibility, the methodology's original orientation is public protection. As a result of coordination between several competent authorities, managed by the authors, the methodology was adopted for patient and worker protection too. Applicants, actually possible users (hospitals) of the new procedure, were obliged to plan medical procedures and working area according to dose limits and constrains as recommended by the International Atomic Energy Agency and local competent authorities. Exposure calculations had to consider the usual parameters as sources types and activity, dose rate and dose levels, duration and number of treatments. Special attention was given to the presence workers and public by chance presence in or near treatment area. A usual condition to give a license was the installation of continuous (during treatment) radiation monitoring systems. But a special attention was given to physical barriers and procedures in order to stop unauthorized personal to arrive near to working area. Satisfactory staff training for normal operation and emergency situations are essential, including appropriate safety procedures and the presence of safety assistance team while executing treatment. (author)

Robot-assisted procedures in pediatric neurosurgery.

Science.gov (United States)

De Benedictis, Alessandro; Trezza, Andrea; Carai, Andrea; Genovese, Elisabetta; Procaccini, Emidio; Messina, Raffaella; Randi, Franco; Cossu, Silvia; Esposito, Giacomo; Palma, Paolo; Amante, Paolina; Rizzi, Michele; Marras, Carlo Efisio

2017-05-01

OBJECTIVE During the last 3 decades, robotic technology has rapidly spread across several surgical fields due to the continuous evolution of its versatility, stability, dexterity, and haptic properties. Neurosurgery pioneered the development of robotics, with the aim of improving the quality of several procedures requiring a high degree of accuracy and safety. Moreover, robot-guided approaches are of special interest in pediatric patients, who often have altered anatomy and challenging relationships between the diseased and eloquent structures. Nevertheless, the use of robots has been rarely reported in children. In this work, the authors describe their experience using the ROSA device (Robotized Stereotactic Assistant) in the neurosurgical management of a pediatric population. METHODS Between 2011 and 2016, 116 children underwent ROSA-assisted procedures for a variety of diseases (epilepsy, brain tumors, intra- or extraventricular and tumor cysts, obstructive hydrocephalus, and movement and behavioral disorders). Each patient received accurate preoperative planning of optimal trajectories, intraoperative frameless registration, surgical treatment using specific instruments held by the robotic arm, and postoperative CT or MR imaging. RESULTS The authors performed 128 consecutive surgeries, including implantation of 386 electrodes for stereo-electroencephalography (36 procedures), neuroendoscopy (42 procedures), stereotactic biopsy (26 procedures), pallidotomy (12 procedures), shunt placement (6 procedures), deep brain stimulation procedures (3 procedures), and stereotactic cyst aspiration (3 procedures). For each procedure, the authors analyzed and discussed accuracy, timing, and complications. CONCLUSIONS To the best their knowledge, the authors present the largest reported series of pediatric neurosurgical cases assisted by robotic support. The ROSA system provided improved safety and feasibility of minimally invasive approaches, thus optimizing the surgical

Human Factors Process Task Analysis Liquid Oxygen Pump Acceptance Test Procedure for the Advanced Technology Development Center

Science.gov (United States)

Diorio, Kimberly A.

2002-01-01

A process task analysis effort was undertaken by Dynacs Inc. commencing in June 2002 under contract from NASA YA-D6. Funding was provided through NASA's Ames Research Center (ARC), Code M/HQ, and Industrial Engineering and Safety (IES). The John F. Kennedy Space Center (KSC) Engineering Development Contract (EDC) Task Order was 5SMA768. The scope of the effort was to conduct a Human Factors Process Failure Modes and Effects Analysis (HF PFMEA) of a hazardous activity and provide recommendations to eliminate or reduce the effects of errors caused by human factors. The Liquid Oxygen (LOX) Pump Acceptance Test Procedure (ATP) was selected for this analysis. The HF PFMEA table (see appendix A) provides an analysis of six major categories evaluated for this study. These categories include Personnel Certification, Test Procedure Format, Test Procedure Safety Controls, Test Article Data, Instrumentation, and Voice Communication. For each specific requirement listed in appendix A, the following topics were addressed: Requirement, Potential Human Error, Performance-Shaping Factors, Potential Effects of the Error, Barriers and Controls, Risk Priority Numbers, and Recommended Actions. This report summarizes findings and gives recommendations as determined by the data contained in appendix A. It also includes a discussion of technology barriers and challenges to performing task analyses, as well as lessons learned. The HF PFMEA table in appendix A recommends the use of accepted and required safety criteria in order to reduce the risk of human error. The items with the highest risk priority numbers should receive the greatest amount of consideration. Implementation of the recommendations will result in a safer operation for all personnel.

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

International Nuclear Information System (INIS)

1989-04-01

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

REVIEW Of COMPUTERIZED PROCEDURE GUIDELINES FOR NUCLEAR POWER PLANT CONTROL ROOMS

Energy Technology Data Exchange (ETDEWEB)

David I Gertman; Katya Le Blanc; Ronald L Boring

2011-09-01

Computerized procedures (CPs) are recognized as an emerging alternative to paper-based procedures for supporting control room operators in nuclear power plants undergoing life extension and in the concept of operations for advanced reactor designs. CPs potentially reduce operator workload, yield increases in efficiency, and provide for greater resilience. Yet, CPs may also adversely impact human and plant performance if not designed and implemented properly. Therefore, it is important to ensure that existing guidance is sufficient to provide for proper implementation and monitoring of CPs. In this paper, human performance issues were identified based on a review of the behavioral science literature, research on computerized procedures in nuclear and other industries, and a review of industry experience with CPs. The review of human performance issues led to the identification of a number of technical gaps in available guidance sources. To address some of the gaps, we developed 13 supplemental guidelines to support design and safety. This paper presents these guidelines and the case for further research.

40 CFR 240.209 - Safety.

Science.gov (United States)

2010-07-01

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

National Waste Repository Novi Han operational safety analysis report. Safety assessment methodology

International Nuclear Information System (INIS)

2003-01-01

The scope of the safety assessment (SA), presented includes: waste management functions (acceptance, conditioning, storage, disposal), inventory (current and expected in the future), hazards (radiological and non-radiological) and normal and accidental modes. The stages in the development of the SA are: criteria selection, information collection, safety analysis and safety assessment documentation. After the review the facilities functions and the national and international requirements, the criteria for safety level assessment are set. As a result from the 2nd stage actual parameters of the facility, necessary for safety analysis are obtained.The methodology is selected on the base of the comparability of the results with the results of previous safety assessments and existing standards and requirements. The procedure and requirements for scenarios selection are described. A radiological hazard categorisation of the facilities is presented. Qualitative hazards and operability analysis is applied. The resulting list of events are subjected to procedure for prioritization by method of 'criticality analysis', so the estimation of the risk is given for each event. The events that fall into category of risk on the boundary of acceptability or are unacceptable are subjected to the next steps of the analysis. As a result the lists with scenarios for PSA and possible design scenarios are established. PSA logical modeling and quantitative calculations of accident sequences are presented

Human factoring administrative procedures

International Nuclear Information System (INIS)

Grider, D.A.; Sturdivant, M.H.

1991-01-01

In nonnuclear business, administrative procedures bring to mind such mundane topics as filing correspondence and scheduling vacation time. In the nuclear industry, on the other hand, administrative procedures play a vital role in assuring the safe operation of a facility. For some time now, industry focus has been on improving technical procedures. Significant efforts are under way to produce technical procedure requires that a validated technical, regulatory, and administrative basis be developed and that the technical process be established for each procedure. Producing usable technical procedures requires that procedure presentation be engineered to the same human factors principles used in control room design. The vital safety role of administrative procedures requires that they be just as sound, just a rigorously formulated, and documented as technical procedures. Procedure programs at the Tennessee Valley Authority and at Boston Edison's Pilgrim Station demonstrate that human factors engineering techniques can be applied effectively to technical procedures. With a few modifications, those same techniques can be used to produce more effective administrative procedures. Efforts are under way at the US Department of Energy Nuclear Weapons Complex and at some utilities (Boston Edison, for instance) to apply human factors engineering to administrative procedures: The techniques being adapted include the following

Problems and concerns in radiation safety management related with decommissioning of tritium facility

International Nuclear Information System (INIS)

Kawano, Takao

2005-01-01

The tritium facility at the National Institute for Fusion Science has been closed in 2002 after decommissioning procedure. A number of works have been completed including technical measures and administrative documentations to be reported to the Ministry of Education, Culture, Sport, Science and Technology. All the operations were carried out in three successive terms; 1) survey and preparations, 2) actual decommissioning works, and 3) report of all procedures to the Minister. A valuable experience we had during this project has been summarized, and some problems have also been pointed out from a viewpoint of radiation safety management. (author)

Radiation safety among cardiology fellows.

Science.gov (United States)

Kim, Candice; Vasaiwala, Samip; Haque, Faizul; Pratap, Kiran; Vidovich, Mladen I

2010-07-01

Cardiology fellows can be exposed to high radiation levels during procedures. Proper radiation training and implementation of safety procedures is of critical importance in lowering physician health risks associated with radiation exposure. Participants were cardiology fellows in the United States (n = 2,545) who were contacted by e-mail to complete an anonymous survey regarding the knowledge and practice of radiation protection during catheterization laboratory procedures. An on-line survey engine, SurveyMonkey, was used to distribute and collect the results of the 10-question survey. The response rate was 10.5%. Of the 267 respondents, 82% had undergone formal radiation safety training. Only 58% of the fellows were aware of their hospital's pregnancy radiation policy and 60% knew how to contact the hospital's radiation safety officer. Although 52% of the fellows always wore a dosimeter, 81% did not know their level of radiation exposure in the previous year and only 74% of fellows knew the safe levels of radiation exposure. The fellows who had received formal training were more likely to be aware of their pregnancy policy, to know the contact information of their radiation safety officer, to be aware of the safe levels of radiation exposure, to use dosimeters and RadPad consistently, and to know their own level of radiation exposure in the previous year. In conclusion, cardiology fellows have not been adequately educated about radiation safety. A concerted effort directed at physician safety in the workplace from the regulatory committees overseeing cardiology fellowships should be encouraged. Published by Elsevier Inc.

Medical social consequences of the safety problems of oncological radiology

International Nuclear Information System (INIS)

Pilipenko, M.Yi.; Stadnik, L.L.; Shal'opa, O.Yu.; Rigan, M.M.; Skalets'kij, Yu.M.

2015-01-01

Actuality of the problem of patient safety in oncoradiology in Ukraine is grounded. The results of international audit TLD (IAEA/WHO) quality during dosimetry procedures cobalt-telegamma vehicles in Ukraine are investigated, as well as legal and regulatory framework providing for the safety of radiotherapy care, scientific publications on patient safety. Methods: statistical, analytical, bibliographical, systematic approach. On the example of radiation therapy using the results of the international program of the IAEA/WHO TLD audit quality dosimetry calibration devices for remote gamma therapy in Ukraine from 1998 to 2014 the attempt to assess the extent of medical and social consequences of underestimating of medical errors in oncoradiology is made. The problems of regulatory nature of medical errors in oncoradiology are preliminary identified. The problem of medical errors in the treatment of cancer radiation methods in Ukraine is extremely important. Usually the problems of errors in oncoradiology are considered in organizational, technical, personnel and technical aspects, while medical and social consequences of problem are not covered. About 10 thousand of cancer patients in year may suffer from errors related only to dose calculation according to the optimistic variant, while the number of patients for the same period on the pessimistic case can reach 15 thousand. There are a number of legal character problems in oncoradiology related to patient safety that require clarification. The first priority for improving the safety of patients in oncoradiology is the recording and analysis of radiation therapy defects and their consequences

New approaches to food safety economics

NARCIS (Netherlands)

Velthuis, A.G.J.; Unnevehr, L.J.; Hogeveen, H.; Huirne, R.B.M.

2002-01-01

Food-safety economics is a new research field, which needs a solid framework of concepts, procedures and data to support the decision-making process in food-safety improvement. Food safety is a theme that plays at many levels in the community: at the consumer level, at the farm or business level, at

Conceptual structure and the procedural affordances of rational numbers: relational reasoning with fractions and decimals.

Science.gov (United States)

DeWolf, Melissa; Bassok, Miriam; Holyoak, Keith J

2015-02-01

The standard number system includes several distinct types of notations, which differ conceptually and afford different procedures. Among notations for rational numbers, the bipartite format of fractions (a/b) enables them to represent 2-dimensional relations between sets of discrete (i.e., countable) elements (e.g., red marbles/all marbles). In contrast, the format of decimals is inherently 1-dimensional, expressing a continuous-valued magnitude (i.e., proportion) but not a 2-dimensional relation between sets of countable elements. Experiment 1 showed that college students indeed view these 2-number notations as conceptually distinct. In a task that did not involve mathematical calculations, participants showed a strong preference to represent partitioned displays of discrete objects with fractions and partitioned displays of continuous masses with decimals. Experiment 2 provided evidence that people are better able to identify and evaluate ratio relationships using fractions than decimals, especially for discrete (or discretized) quantities. Experiments 3 and 4 found a similar pattern of performance for a more complex analogical reasoning task. When solving relational reasoning problems based on discrete or discretized quantities, fractions yielded greater accuracy than decimals; in contrast, when quantities were continuous, accuracy was lower for both symbolic notations. Whereas previous research has established that decimals are more effective than fractions in supporting magnitude comparisons, the present study reveals that fractions are relatively advantageous in supporting relational reasoning with discrete (or discretized) concepts. These findings provide an explanation for the effectiveness of natural frequency formats in supporting some types of reasoning, and have implications for teaching of rational numbers.

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.

[Absolute numbers of peripheral blood CD34+ hematopoietic stem cells prior to a leukapheresis procedure as a parameter predicting the efficiency of stem cell collection].

Science.gov (United States)

Galtseva, I V; Davydova, Yu O; Gaponova, T V; Kapranov, N M; Kuzmina, L A; Troitskaya, V V; Gribanova, E O; Kravchenko, S K; Mangasarova, Ya K; Zvonkov, E E; Parovichnikova, E N; Mendeleeva, L P; Savchenko, V G

To identify a parameter predicting a collection of at least 2·106 CD34+ hematopoietic stem cells (HSC)/kg body weight per leukapheresis (LA) procedure. The investigation included 189 patients with hematological malignancies and 3 HSC donors, who underwent mobilization of stem cells with their subsequent collection by LA. Absolute numbers of peripheral blood leukocytes and CD34+ cells before a LA procedure, as well as a number of CD34+ cells/kg body weight (BW) in the LA product stored on the same day were determined in each patient (donor). There was no correlation between the number of leukocytes and that of stored CD34+ cells/kg BW. There was a close correlation between the count of peripheral blood CD34+ cells prior to LA and that of collected CD34+ cells calculated with reference to kg BW. The optimal absolute blood CD34+ cell count was estimated to 20 per µl, at which a LA procedure makes it possible to collect 2·106 or more CD34+ cells/kg BW.

47 CFR 80.331 - Bridge-to-bridge communication procedure.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 5 2010-10-01 2010-10-01 false Bridge-to-bridge communication procedure. 80..., Alarm, Urgency and Safety Procedures § 80.331 Bridge-to-bridge communication procedure. (a) Vessels subject to the Bridge-to-Bridge Act transmitting on the designated navigational frequency must conduct...

Requesting and granting exemptions to nuclear safety rules

International Nuclear Information System (INIS)

1995-02-01

This standard provides an acceptable process for requesting and granting exemptions to DOE Nuclear Safety rules. The provisions of 10 CFR Part 820.63 allow DOE to determine the procedures to be used to comply with the responsibilities regarding exemption relief from DOE nuclear safety rules. The procedure in this standard defines an acceptable method for meeting these responsibilities

Student manual, Book 2: Orientation to occupational safety compliance in DOE

Energy Technology Data Exchange (ETDEWEB)

Colley, D.L.

1993-10-01

This is a student hand-book an Occupational Safety Compliance in DOE. Topics include the following: Electrical; materials handling & storage; inspection responsibilities & procedures; general environmental controls; confined space entry; lockout/tagout; office safety, ergonomics & human factors; medical & first aid, access to records; construction safety; injury/illness reporting system; and accident investigation procedures.

Nuclear power safety

International Nuclear Information System (INIS)

1988-01-01

The International Atomic Energy Agency, the organization concerned with worldwide nuclear safety has produced two international conventions to provide (1) prompt notification of nuclear accidents and (2) procedures to facilitate mutual assistance during an emergency. IAEA has also expanded operational safety review team missions, enhanced information exchange on operational safety events at nuclear power plants, and planned a review of its nuclear safety standards to ensure that they include the lessons learned from the Chernobyl nuclear plant accident. However, there appears to be a nearly unanimous belief among IAEA members that may attempt to impose international safety standards verified by an international inspection program would infringe on national sovereignty. Although several Western European countries have proposed establishing binding safety standards and inspections, no specific plant have been made; IAEA's member states are unlikely to adopt such standards and an inspection program

Transient management using the safety function approach

International Nuclear Information System (INIS)

Corcoran, W.R.; Barrow, J.H.; Bischoff, G.C.; Callaghan, V.M.; Pearce, R.T.

1984-01-01

The safety function approach is described. Its use in the development of a transient management procedures system includes optimal recovery procedures tailored to specific, anticipated symptom sets and a functional recovery procedure which is more general. Simulator evaluations are described

9 CFR 113.39 - Cat safety tests.

Science.gov (United States)

2010-01-01

... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Cat safety tests. 113.39 Section 113... Procedures § 113.39 Cat safety tests. The safety tests provided in this section shall be conducted when... recommended for use in cats. (a) The cat safety test provided in this paragraph shall be used when the Master...

Safety in Agri-food chains

NARCIS (Netherlands)

Luning, P.A.; Vlieghere, de F.; Verhé, R.

2006-01-01

Increasing public demand for adequate and safe food supply has led to extensive development in the field of plant-animal production, food processing, quality and safety procedures, food analysis and control and regulations. However, safety of food can only be guaranteed by the integration of control

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

International Nuclear Information System (INIS)

1987-11-01

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

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

International Nuclear Information System (INIS)

1990-06-01

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

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

International Nuclear Information System (INIS)

1987-12-01

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

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

International Nuclear Information System (INIS)

1989-04-01

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

From Safety Culture to Culture for Safety — What is it that we Still Haven’t Learned

International Nuclear Information System (INIS)

Haber, S.B.

2016-01-01

In April 1986 the Chernobyl Accident happened. Several years later in 1991 the IAEA Independent Nuclear Safety Advisory Group published INSAG-4 and the concept of safety culture was defined for the nuclear community because of its relationship to the accident. Where the Three Mile Island Accident in 1979 had brought human factors issues in procedure development, human performance, and training to light, the Chernobyl Accident was discussed in terms of management, supervision, and safety culture. Work in the nuclear community evolved around the concept of safety culture although a clear understanding of what was actually meant was often missing. Methods to evaluate and assess safety culture were developed and efforts to integrate the findings of those evaluations into more traditional nuclear tools, such as probabilistic risk and safety assessment were attempted as well. Safety culture became thought of as a process that could be written into a procedure, measured by performance indicators and fixed in a corrective action program. The changes that organizations saw as a function of their safety culture improvement programs though were often just changes in some behaviors. Short term improvements in safety performance and the metrics to measure them were observed and many concluded they had really changed their safety culture. The changes were often not sustainable. The efforts did not include an in depth understanding of why individuals thought or behaved in the way that they did. In March 2011 the Fukushima Daiichi Accident happened. Initially it was accepted to explain it as a natural disaster. While the earthquake or the tsunami could not be prevented, there were things that could have been done before, during and immediately after the natural phenomena that would have helped to mitigate the consequences of the accident. The IAEA conducted an in-depth analysis of the human and organizational factors of that accident and drew a number of conclusions but none so

Iodine-125 safety procedures in a biochemical laboratory

International Nuclear Information System (INIS)

1989-01-01

Radioactive isotopes of iodine are of considerable importance in biochemical research and this 14 minute videotape is designed to give workers an introduction to the radiation safety aspects of their use. It deals with I-125, which is now generally used in preference to I-131, but the principles of safe working practice are the same for both isotopes. (author)

Qualification of safety-critical software for digital reactor safety system in nuclear power plants

International Nuclear Information System (INIS)

Kwon, Kee-Choon; Park, Gee-Yong; Kim, Jang-Yeol; Lee, Jang-Soo

2013-01-01

This paper describes the software qualification activities for the safety-critical software of the digital reactor safety system in nuclear power plants. The main activities of the software qualification processes are the preparation of software planning documentations, verification and validation (V and V) of the software requirements specifications (SRS), software design specifications (SDS) and codes, and the testing of the integrated software and integrated system. Moreover, the software safety analysis and software configuration management are involved in the software qualification processes. The V and V procedure for SRS and SDS contains a technical evaluation, licensing suitability evaluation, inspection and traceability analysis, formal verification, software safety analysis, and an evaluation of the software configuration management. The V and V processes for the code are a traceability analysis, source code inspection, test case and test procedure generation. Testing is the major V and V activity of the software integration and system integration phases. The software safety analysis employs a hazard operability method and software fault tree analysis. The software configuration management in each software life cycle is performed by the use of a nuclear software configuration management tool. Through these activities, we can achieve the functionality, performance, reliability, and safety that are the major V and V objectives of the safety-critical software in nuclear power plants. (author)

Safety procedures for the electron spectroscopy of actinides at the ALS

International Nuclear Information System (INIS)

Shuh, D.K.; Edelstein, N.M.; Bucher, J.J.

1996-01-01

This is an addendum to the ALS Experimental Safety Form Renewal for the continuation of actinide microspot experiments on beamlines 7.0. There are several modifications to the previously approved. procedures. There is an increase in the amount of allowable material of the low activity isotopes 238 U, 237 Np, 242 Pu, and 248 Cm. There is also the addition of 99 Tc and the activity isotopes 232 Th and 243 Am to the list of permissible sample materials. All of the materials are alpha-emitters with negligible gamma fields with the exception of 99 Tc which is a beta-emitter. There is a series of new experiments that requires the use of a crystal cleaver in the preparation chamber of the ultraESCA end station. The beamline 7.0 ultraESCA endstation has been suitably modified to permit the safe cleave of YUPd alloy rectangular ingots. AR of the sample materials are solids. The exact nature and composition of the samples are delineated in the sample preparation section that follows. A corresponding Radiological Work Authorization (RWA) must be issued for this work at ALS since the material amounts exceed those in the Low Activity Source (LAS) guidelines in Table I and those in the Values for Exemption of Sealed Source Inventory in Table II. The preliminary date for the next run of these sample materials has been tentatively scheduled in early February 1996 and this will be with the uranium cleave alloys, not the transuranic materials

Safety Training: Basic Safety and Access Courses

CERN Multimedia

Antonella Vignes

2005-01-01

Objective The purpose of the basic safety courses is to increase awareness for everyone working on the CERN site (CERN staff, associates, outside companies, students and apprentices) of the various existing on-site hazards, and how to recognize and avoid them. Safety course changes The current organization for basic safety courses is changing. There will be two main modifications: the organization of the courses and the implementation of a specific new training course for the LHC machine during the LHC tests and hardware commissioning phase. Organizational changes This concerns the existing basic safety training, currently called level1, level2 and level3. Under the new procedure, a video will be projected in registration building 55 and will run every day at 14.00 and 15.00 in English. The duration of the video will be 50 minutes. The course contents will be the same as the slides currently used, plus a video showing real situations. With this new organization, attendees will systematically follow the...

Safety Training: basic safety and access courses

CERN Multimedia

2005-01-01

Objective The purpose of the basic safety courses is to increase awareness for everyone working on the CERN site (CERN staff, associates, outside companies, students and apprentices) of the various hazards existing on site, and how to recognise and avoid them. Safety course changes The current organisation of basic safety courses is changing. There will be two main modifications: the organisation of the courses and the implementation of a specific new training course for the LHC machine during the LHC tests and hardware commissioning phase. Organisational changes This concerns the existing basic safety training, currently called level 1, level 2 and level 3. Under the new procedure, a video will be projected in registration building 55 and will run every day at 14.00 and 15.00 in English. The duration of the video will be 50 minutes. The course contents will be the same as the slides currently used, plus a video showing real situations. With this new organization, participants will systematically follow...

Strengthening safety compliance in nuclear power operations: a role-based approach.

Science.gov (United States)

Martínez-Córcoles, Mario; Gracia, Francisco J; Tomás, Inés; Peiró, José M

2014-07-01

Safety compliance is of paramount importance in guaranteeing the safe running of nuclear power plants. However, it depends mostly on procedures that do not always involve the safest outcomes. This article introduces an empirical model based on the organizational role theory to analyze the influence of legitimate sources of expectations (procedures formalization and leadership) on workers' compliance behaviors. The sample was composed of 495 employees from two Spanish nuclear power plants. Structural equation analysis showed that, in spite of some problematic effects of proceduralization (such as role conflict and role ambiguity), procedure formalization along with an empowering leadership style lead to safety compliance by clarifying a worker's role in safety. Implications of these findings for safety research are outlined, as well as their practical implications. © 2014 Society for Risk Analysis.

Nuclear safety in France

International Nuclear Information System (INIS)

Tanguy, P.

1979-01-01

A brief description of the main safety aspects of the French nuclear energy programme and of the general safety organization is followed by a discussion on the current thinking in CEA on some important safety issues. As far as methodology is concerned, the use of probabilistic analysis in the licensing procedure is being extensively developed. Reactor safety research is aimed at a better knowledge of the safety margins involved in the present designs of both PWRs and LMFBRs. A greater emphasis should be put during the next years in the safety of the nuclear fuel cycle installations, including waste disposals. Finally, it is suggested that further international cooperation in the field of nuclear safety should be developed in order to insure for all countries the very high safety level which has been achieved up till now. (author)

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…

The 8th questionnaire survey report of safety control in nuclear medicine

International Nuclear Information System (INIS)

2008-01-01

A questionnaire survey on safety of nuclear medicine studies was conducted under the subcommittee for radionuclide imaging and nuclear medicine technology of Japan Radioisotope Association to promote patient safety. Questionnaires were sent to 1300 hospitals and 21 clinical laboratories in Japan with 1034 facilities responded (78.3%). Sixty percents of the workers in the facilities were nuclear medicine technologists. Medical doctors comprised 20% of the workers, but 32% in the university hospitals. The number of laboratory technologists decreased in all categories of the facilities. Composite PET/CT scanners increased sharply, whereas 2-detector and 3-detector imaging systems decreased. Regular maintenance was performed in approximately 80% of the SPECT imaging systems, while the single head imaging systems were maintained less frequently. Filmless systems were employed in 25.3% of all of the facilities responded, with the higher rate in the university hospitals. The number of accidents and incidents in the facilities decreased. Falls on floor and fall from an examination bed were reported. The nuclear medicine technologists were concerned about safety mechanism of imaging systems, and dimension and height of examination beds. They also wanted prompt supply of safety information and easy interconnectivity among different data of various vendors' systems. The results of this survey may be a valuable source of information on safety of nuclear medicine procedures. (author)

Safety climate and the distracted driving experiences of truck drivers.

Science.gov (United States)

Swedler, David I; Pollack, Keshia M; Agnew, Jacqueline

2015-07-01

For truck drivers, distracted driving is a workplace behavior that increases occupational injury risk. We propose safety climate as an appropriate lens through which researchers can examine occupational distracted driving. Using a mixed methods study design, we surveyed truck drivers using the Safety Climate Questionnaire (SCQ) complemented by semi-structured interviews of experts on distracted driving and truck safety. Safety climate was assessed by using the entire SCQ as an overall climate score, followed by factor analysis that identified the following safety climate factors: Communications and Procedures; Management Commitment; and Work Pressure. In multivariate regression, the overall safety climate scale was associated with having ever experienced a crash and/or distraction-involved swerving. Interview participants described how these SCQ constructs could affect occupational distracted driving. To reduce distraction-related crashes in their organizations, management can adhere to safe policies and procedures, invest in engineering controls, and develop safer communication procedures. © 2015 Wiley Periodicals, Inc.

Administrative practices for nuclear criticality safety, ANSI/ANS-8.19-1996

International Nuclear Information System (INIS)

Smith, D.R.

1996-01-01

American National Standard, open-quotes Administrative Practices for Nuclear Criticality Safety,close quotes American National Standards Institute/American Nuclear Society (ANSI/ANS)-8.19-1996, addresses the responsibilities of management, supervision, and the criticality safety staff in the administration of an effective criticality safety program. Characteristics of operating procedures, process evaluations, material control procedures, and emergency plans are discussed

Student manual, Book 2: Orientation to occupational safety compliance in DOE

International Nuclear Information System (INIS)

Colley, D.L.

1993-01-01

This is a student hand-book an Occupational Safety Compliance in DOE. Topics include the following: Electrical; materials handling ampersand storage; inspection responsibilities ampersand procedures; general environmental controls; confined space entry; lockout/tagout; office safety, ergonomics ampersand human factors; medical ampersand first aid, access to records; construction safety; injury/illness reporting system; and accident investigation procedures

Aspects of the licensing procedures for enrichment reduction in research reactors

International Nuclear Information System (INIS)

Krull, W.

1983-01-01

The enrichment reduction for research reactors requires a licensing procedure. For this purpose the qualification of the new fuel has to be demonstrated and changes in reactor safety have to be investigated like reactivity values, form-factors, Pu- and fission product inventory, safety margins and accidents. Calculations should be partly experimentally verified. The possible extent of the licensing procedure is discussed. (orig.) [de

United States Nuclear Regulatory Commission staff practice and procedure digest. Commission, Appearl Board and Licensing Board decisions, July 1972-June 1985. Digest No. 4

International Nuclear Information System (INIS)

1986-01-01

This edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period July 1, 1972 to June 30, 1985 interpreting the NRC's Rules of Practice in 10 CFR Part 2. This edition replaces earlier editions and supplements and includes appropriate changes reflecting the amendment to the Rules of Practice effective June 30, 1985

Developing, adopting and adapting operating procedures

International Nuclear Information System (INIS)

Rabouhams, J.

1986-01-01

This lecture specifies all the dispositions which have been taken by EDF Nuclear and Fossil Generation Department - according to the fact that availability and safety largely depend on the quality of the procedures and their easy handling - in order to develop, adopt and adapt the operating procedures. The following points are treated: General organization of procedures for plant operation during normal and abnormal conditions; Personnel and extend of responsibility involved into the development of procedures (research center, training center, specialized services, nuclear station, etc.); Validation of the procedures by means of full-scope simulators; Modifications of the procedures taking into account operation experience in material and human fields; Development of simulation softs in order to perform the procedures in abnormal situations; Evolution of operating technics and future skills. (orig.)

United States Nuclear Regulatory Commission Staff practice and procedure digest: Commission, Appeal Board and Licensing Board Decisions, July 1972--December 1988

International Nuclear Information System (INIS)

1989-10-01

This Revision 2 of the fifth edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to December 31, 1988, interpreting the NRC's Rules of Practice in 10 CFR Part 2. This Revision 2 replaces in part earlier editions and revisions and includes appropriate changes reflecting the amendments to the Rules of Practice Effective through December 31, 1988. The Practice and Procedure Digest was originally prepared by attorneys in the NRC's Office of the Executive Legal Director (now, Office of the General Counsel) as an internal research tool. Because of its proven usefulness to those attorneys, it was decided that it might also prove useful to members of the public. Accordingly, the decision was made to publish the Digest and subsequent editions thereof. This edition of the Digest was prepared by attorneys from Aspen Systems Corporation pursuant to Contract number 18-89-346

Operational and environmental safety

International Nuclear Information System (INIS)

Anon.

1978-01-01

The responsibility of the DOE Office of Operational and Environmental Safety is to assure that DOE-controlled activities are conducted in a manner that will minimize risks to the public and employees and will provide protection for property and the environment. The program supports the various energy technologies by identifying and resolving safety problems; developing and issuing safety policies, standards, and criteria; assuring compliance with DOE, Federal, and state safety regulations; and establishing procedures for reporting and investigating accidents in DOE operations. Guidelines for the radiation protection of personnel; radiation monitoring at nuclear facilities; an assessment of criticality accidents by fault tree analysis; and the preparation of environmental, safety, and health standards applicable to geothermal energy development are discussed

Safety improvement of Paks nuclear power plant

International Nuclear Information System (INIS)

Vamos, G.

1999-01-01

Safety upgrading completed in the early nineties at the Paks NPP include: replacement of steam generator safety valves and control valves; reliability improvement of the electrical supply system; modification of protection logic; enhancement of the fire protection; construction of full scope Training Simulator. Design safety upgrading measures achieved in recent years were concerned with: relocation of steam generator emergency feed-water supply; emergency gas removal from the primary coolant system; hydrogen management in the containment; protection against sumps; preventing of emergency core cooling system tanks from refilling. Increasing seismic resistance, containment assessment, refurbishment of reactor protection system, improving reliability of emergency electrical supply, analysis of internal hazards are now being implemented. Safety upgrading measures which are being prepared include: bleed and feed procedures; reactor over-pressurisation protection in cold state; treatment of steam generator primary to secondary leak accidents. Operational safety improvements are dealing with safety culture, training measures and facilities; symptom based emergency operating procedures; in-service inspection; fire protection. The significance of international cooperation is emphasised in view of achieving nuclear safety standards recognised in EU

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

Undergraduate Organic Chemistry Laboratory Safety

Science.gov (United States)

Luckenbaugh, Raymond W.

1996-11-01

Each organic chemistry student should become familiar with the educational and governmental laboratory safety requirements. One method for teaching laboratory safety is to assign each student to locate safety resources for a specific class laboratory experiment. The student should obtain toxicity and hazardous information for all chemicals used or produced during the assigned experiment. For example, what is the LD50 or LC50 for each chemical? Are there any specific hazards for these chemicals, carcinogen, mutagen, teratogen, neurotixin, chronic toxin, corrosive, flammable, or explosive agent? The school's "Chemical Hygiene Plan", "Prudent Practices for Handling Hazardous Chemicals in the Laboratory" (National Academy Press), and "Laboratory Standards, Part 1910 - Occupational Safety and Health Standards" (Fed. Register 1/31/90, 55, 3227-3335) should be reviewed for laboratory safety requirements for the assigned experiment. For example, what are the procedures for safe handling of vacuum systems, if a vacuum distillation is used in the assigned experiment? The literature survey must be submitted to the laboratory instructor one week prior to the laboratory session for review and approval. The student should then give a short presentation to the class on the chemicals' toxicity and hazards and describe the safety precautions that must be followed. This procedure gives the student first-hand knowledge on how to find and evaluate information to meet laboartory safety requirements.

NASA's Software Safety Standard

Science.gov (United States)

Ramsay, Christopher M.

2007-01-01

NASA relies more and more on software to control, monitor, and verify its safety critical systems, facilities and operations. Since the 1960's there has hardly been a spacecraft launched that does not have a computer on board that will provide command and control services. There have been recent incidents where software has played a role in high-profile mission failures and hazardous incidents. For example, the Mars Orbiter, Mars Polar Lander, the DART (Demonstration of Autonomous Rendezvous Technology), and MER (Mars Exploration Rover) Spirit anomalies were all caused or contributed to by software. The Mission Control Centers for the Shuttle, ISS, and unmanned programs are highly dependant on software for data displays, analysis, and mission planning. Despite this growing dependence on software control and monitoring, there has been little to no consistent application of software safety practices and methodology to NASA's projects with safety critical software. Meanwhile, academia and private industry have been stepping forward with procedures and standards for safety critical systems and software, for example Dr. Nancy Leveson's book Safeware: System Safety and Computers. The NASA Software Safety Standard, originally published in 1997, was widely ignored due to its complexity and poor organization. It also focused on concepts rather than definite procedural requirements organized around a software project lifecycle. Led by NASA Headquarters Office of Safety and Mission Assurance, the NASA Software Safety Standard has recently undergone a significant update. This new standard provides the procedures and guidelines for evaluating a project for safety criticality and then lays out the minimum project lifecycle requirements to assure the software is created, operated, and maintained in the safest possible manner. This update of the standard clearly delineates the minimum set of software safety requirements for a project without detailing the implementation for those

Procedure for Application of Software Reliability Growth Models to NPP PSA

International Nuclear Information System (INIS)

Son, Han Seong; Kang, Hyun Gook; Chang, Seung Cheol

2009-01-01

As the use of software increases at nuclear power plants (NPPs), the necessity for including software reliability and/or safety into the NPP Probabilistic Safety Assessment (PSA) rises. This work proposes an application procedure of software reliability growth models (RGMs), which are most widely used to quantify software reliability, to NPP PSA. Through the proposed procedure, it can be determined if a software reliability growth model can be applied to the NPP PSA before its real application. The procedure proposed in this work is expected to be very helpful for incorporating software into NPP PSA

Software quality assurance procedures for radioactive waste risk assessment codes

International Nuclear Information System (INIS)

Hill, I.; Mayer, J.

1990-01-01

This support study for the evaluation of the safety of geological disposal systems is aimed at identifying the requirements for software quality assurance procedures for radioactive waste risk assessment codes, and to recommend appropriate procedures. The research covers: (i) the analysis of existing procedures and definition of requirements; (ii) a case study of the use of some existing procedures; (iii) the definition and the implementation of procedures. The report is supported by appendices that give more detail on the procedures recommended. It is intended to provide ideas on the steps that should be taken to ensure the quality of the programs used for assessment of the safety case for radioactive waste repositories, and does not represent the introduction of wholly new ideas or techniques. The emphasis throughout is on procedures that will be easily implemented, rather than on the fully rigorous procedures that are required for some application areas. The study has concentrated on measures that will increase the confidence in repository performance assessments among the wider scientific/engineering community, and the lay public

Stereotactic body radiotherapy (SBRT) for multiple pulmonary oligometastases: Analysis of number and timing of repeat SBRT as impact factors on treatment safety and efficacy.

Science.gov (United States)

Klement, R J; Hoerner-Rieber, J; Adebahr, S; Andratschke, N; Blanck, O; Boda-Heggemann, J; Duma, M; Eble, M J; Eich, H C; Flentje, M; Gerum, S; Hass, P; Henkenberens, C; Hildebrandt, G; Imhoff, D; Kahl, K H; Klass, N D; Krempien, R; Lohaus, F; Petersen, C; Schrade, E; Wendt, T G; Wittig, A; Guckenberger, M

2018-03-03

Stereotactic body radiotherapy (SBRT) for oligometastatic disease is characterized by an excellent safety profile; however, experiences are mostly based on treatment of one single metastasis. It was the aim of this study to evaluate safety and efficacy of SBRT for multiple pulmonary metastases. This study is based on a retrospective database of the DEGRO stereotactic working group, consisting of 637 patients with 858 treatments. Cox regression and logistic regression were used to analyze the association between the number of SBRT treatments or the number and the timing of repeat SBRT courses with overall survival (OS) and the risk of early death. Out of 637 patients, 145 patients were treated for multiple pulmonary metastases; 88 patients received all SBRT treatments within one month whereas 57 patients were treated with repeat SBRT separated by at least one month. Median OS for the total patient population was 23.5 months and OS was not significantly influenced by the overall number of SBRT treatments or the number and timing of repeat SBRT courses. The risk of early death within 3 and 6 months was not increased in patients treated with multiple SBRT treatments, and no grade 4 or grade 5 toxicity was observed in these patients. In appropriately selected patients, synchronous SBRT for multiple pulmonary oligometastases and repeat SBRT may have a comparable safety and efficacy profile compared to SBRT for one single oligometastasis. Copyright © 2018 Elsevier B.V. All rights reserved.

Assessment of procedural skills in residents working in a research and training institute: An effort to ensure patient safety and quality control.

Science.gov (United States)

Kumari, Kamlesh; Samra, Tanvir; Naik, B Naveen; Saini, Vikas

2018-01-01

To ensure patient safety, it is important to regularly assess the knowledge and practical skills of anesthesia trainees. This study was conducted to evaluate the competency of the residents and the impact of various corrective measures in the form of didactic lectures and clinical skill demonstrations on the conduct of various procedural skills by the residents. Ninety-five junior residents were enrolled in this study. Assessment of competency of 1 st , 2 nd , and 3 rd year residents in performing various procedure skills of anesthesia was done in two stages using procedure specific checklist (PSC) and Global Rating Scales (GRSs). Preliminary results of the first assessment (Score 1) were discussed with the residents; deficiencies were identified and corrective measures suggested by didactic lectures and clinical skill demonstrations which were followed by a subsequent assessment after 3 months (Score 2). There was a statistically significant improvement in the PSC and GRS scores after corrective measures for all the procedural interventions studied. Percentage increase in scores was maximum in 1 st year (42.98 ± 6.62) followed by 2 nd year (34.62 ± 5.49) and minimum in 3 rd year residents (18.06 ± 3.69). The percentage increase of scores was almost similar for all subset of procedural skills; low, intermediate, and high skill anesthetic procedures. For assessment of procedural skills of residents, use of PSC and GRS scores should be incorporated and the same should be used to monitor the impact of various corrective measures (didactic lectures and clinical skill demonstrations) on the conduct of various procedural skills by the resident.

Empirical Analysis of Construction Safety Climate - A Study

OpenAIRE

S.V.S.RAJA PRASAD; K.P.REGHUNATH

2010-01-01

Safety in the construction industry has always been a major issue. Though much improvement in construction safety has been achieved, the industry still continues to lag behind most other industries with regard to safety. The safety climate of any organization consists of employee’s attitudes towards and perceptions of, health and safety behavior. Construction workers attitudes towards safety are influenced by their perceptions of risk, management, safety rulesand procedures. A measure of safe...

The use of living PSA in safety management, a procedure developed in the nordic project ''safety evaluation, NKS/SIK-1''

International Nuclear Information System (INIS)

Johanson, G.; Holmberg, J.

1994-01-01

The essential objective with the development of a living PSA concept is to bring the use of the plant specific PSA model out to the daily safety work to allow operational risk experience feedback and to increase the risk awareness of the intended users. This paper will present results of the Nordic project ''Safety Evaluation, NKS/SIK-1''. The SIK-1 project has defined and demonstrated the practical use of living PSA for safety evaluation and for identification of possible improvements in operational safety. Subjects discussed in this paper are dealing with the practical implementation and use of PSA to make proper safety related decisions and evaluation. (author). 24 refs, 1 fig., 1 tab

Development of PSA procedure for a criticality in reprocessing facilities

International Nuclear Information System (INIS)

Endo, Shigeki; Takanashi, Mitsuhiro; Ueda, Yoshinori

2012-08-01

Utilization of risk information for the nuclear safety regulation is being discussed in Japan. The development of probabilistic safety assessment (PSA) procedure is indispensable for the utilization of risk information. The Japan Nuclear Energy Safety Organization (JNES) has been conducting trial PSA to a model plant for major events, i.e. hydrogen explosion, solution boiling, rapid decomposition of TBP complexes, criticality, solvent fire, leakage of molten glass, leakage of high active concentrated liquid waste, loss of all AC electricity, drop of a fuel assembly, for the purpose of developing the PSA procedure for reprocessing facilities. For criticality events results of trial PSA were summarized as a report in which how to evaluate an amount of radioactive materials released from a facility and a health effect on the public were emphasized. Therefore, for criticality events the results of trial PSA were summarized in this report to emphasize procedures from making event progression scenarios to quantifying event sequences, which were not handled in the previous report, in a style of a document describing PSA procedures. (author)

Health and Safety First

CERN Document Server

2013-01-01

At CERN, health and safety underpin everything we do. We have strict operational procedures in place, as well as health, safety and environment (HSE) requirements to make our working environment as safe as possible. It’s everyone’s responsibility to follow these procedures and requirements to keep ourselves, and our colleagues, safe. We have a very good safety and operational record at CERN stretching back almost 60 years, but there is never room for complacency.   With this very much in mind, we have developed a robust plan for implementation if something unforeseen goes wrong.  Because however careful we all are, accidents do happen, and the mark of any organisation that aspires to be among the best in the world is how quickly and efficiently it acts when they do. A small team made up of people from several departments at CERN has produced a strategic crisis management plan that we can put into action should a major incident occur.  This plan focuses on...

Management of the Bohunice RPVs annealing procedures

International Nuclear Information System (INIS)

Repka, M.

1994-01-01

The program of annealing regeneration procedure of RPVs units 1 and 2 of NPP V-1 (EBO) realization in the year 1993, is the topic of this paper. In the paper the following steps are described in detail: the preparation works, the annealing procedure realization schedule and safety management: starting with zero conditions, assembling of annealing apparatus, annealing procedure, cooling down and disassembling procedure of annealing apparatus. At the end the programs of annealing of both RPVs including the dosimetry measurements are discussed and evaluated. (author). 3 figs

Audit of data and code use in the SR-Can safety assessment

Energy Technology Data Exchange (ETDEWEB)

Hicks, T.W.; Baldwin, T.D. [Galson Sciences Ltd, 5 Grosvenor House, Melton R oad, Oakham, Rutland LE15 6AX (United Kingdom)

2008-03-15

Building on the findings of previous studies on data and code quality assurance (QA) in safety assessments, this report provides a review of data and code QA in the SR-Can safety assessment. The data quality audit aimed to check that the selection and use of data in the SR-Can safety assessment was appropriate, focusing on the data that underpin representations of and assumptions about canister, insert, buffer, and backfill behaviour. The SR-Can Data Report provided the initial focus for examining the traceability and reliability of data used in the safety assessment; the Data Report is one of the series of SR-Can safety assessment reports and, in this review, it was anticipated that it would provide the primary source of data on the canister, insert, buffer, and backfill. However, other safety assessment reports (the SR-Can Main Report, the Initial State Report, the Fuel and Canister Process Report, and the Buffer and Backfill Process Report) were found to provide key information on data used in the safety assessment. The quality audit of codes aimed to check that code use in the SR-Can safety assessment has been justified through a transparent and traceable process of code development and selection. The Model Summary Report provided the focus for reviewing the QA status of the codes used in the safety assessment. As well as highlighting a number of concerns regarding QA aspects of specific data sets, parameter values, and codes used in the SR-Can safety assessment (which are presented in the report), the review has led to several general observations on data and code QA that should be considered by SKB in the development and implementation of a QA system for the SR-Site safety assessment: - The SR-Site safety assessment and associated QA records should include information that demonstrates that a full QA system has been implemented in order to build confidence in the validity of the assessment. - The data and parameter values used directly in the safety

47 CFR 80.1135 - Transmission of maritime safety information.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 5 2010-10-01 2010-10-01 false Transmission of maritime safety information. 80... RADIO SERVICES STATIONS IN THE MARITIME SERVICES Global Maritime Distress and Safety System (GMDSS) Operating Procedures for Distress and Safety Communications § 80.1135 Transmission of maritime safety...

Safety organization

International Nuclear Information System (INIS)

Lutz, M.

1984-06-01

After a rapid definition of a nuclear basis installation, the national organization of nuclear safety in France is presented, as also the main organizations concerned and their functions. This report shows how the licensing procedure leading to the construction and exploitation of such installations is applied in the case of nuclear laboratories of research and development: examinations of nuclear safety problems are carried out at different levels: - centralized to define the frame out of which the installation has not to operate, - decentralized to follow in a more detailed manner its evolution [fr

An independent safety assessment of Department of Energy nuclear reactor facilities: Procedures, operations and maintenance

International Nuclear Information System (INIS)

Toto, G.; Lindgren, A.J.

1981-02-01

The 1979 accident at the Three Mile Island commercial nuclear power plant has led to a number of studies of nuclear reactors, in both the public and private sectors. One of these is that of the Department of Energy's (DOE) Nuclear Facilities Personnel Qualification and Training (NFPQT) Committee, which has outlined tasks for assessment of 13 reactors owned by DOE and operated by contractors. This report covers one of the tasks, the assessment of procedures, operations, and maintenance at the DOE reactor facilities, based on a review of actual documents used at the reactor sites

9 CFR 354.244 - Temperatures and cooling and freezing procedures.

Science.gov (United States)

2010-01-01

... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Temperatures and cooling and freezing procedures. 354.244 Section 354.244 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE... and cooling and freezing procedures. Temperatures and procedures which are necessary for cooling and...

Laser safety tools and training

CERN Document Server

Barat, Ken

2008-01-01

Lasers perform many unique functions in a plethora of applications, but there are many inherent risks with this continually burgeoning technology. Laser Safety: Tools and Training presents simple, effective ways for users in a variety of facilities to evaluate the hazards of any laser procedure and ensure they are following documented laser safety standards.Designed for use as either a stand-alone volume or a supplement to Laser Safety Management, this text includes fundamental laser and laser safety information and critical laser use information rarely found in a single source. The first lase

Promoting participatory behavior on safety

International Nuclear Information System (INIS)

Martinez Corcoles, M.

2012-01-01

Are two types of safety behaviors: On the one hand, the fulfillment of the essential procedures for safe operation, and secondly, those voluntary behaviors that contribute equally to enhance plant safety. During the last three decades, the focus on strict compliance has limited any behavior beyond what is required by the regulations.

The nuclear law: safety. 2006-2010

International Nuclear Information System (INIS)

Bringuier, P.

2010-01-01

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

Safety margins in deterministic safety analysis

International Nuclear Information System (INIS)

Viktorov, A.

2011-01-01

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

The Public Safety Zones around Small and Medium Airports

Directory of Open Access Journals (Sweden)

Paola Di Mascio

2018-04-01

Full Text Available Proper planning around airports safeguards the surrounding territory from risks of air accidents. Many countries have defined Public Safety Zones (PSZs beyond the runway thresholds as a result of targeted risk assessment methods. Therefore, national aviation Authorities could limit building construction and industrial development in order to contain the risk for dwellers to be involved in aircraft accidents. The number of people who live, work or congregate in these areas should be limited. The procedure to set Public Safety Zones is based on advanced technical analyses for major infrastructures. For smaller airports, simplified schemes are used, but, sometimes, they are not as effective when considering the actual safety conditions. This article aims to identify the shape and size of the Public Safety Zones for small and medium one-runway airports. The influence of the volume and mix of traffic on the PSZ geometry has been evaluated using the program named SARA (Sapienza Airport Risk Analysis; the results are correlated with the current Risk Plans generally adopted in Italy. According to the air traffic, the Risk Plans are characterized by a dynamic definition and fit the results obtained from risk assessment.

Review of cause-based decision tree approach for the development of domestic standard human reliability analysis procedure in low power/shutdown operation probabilistic safety assessment

International Nuclear Information System (INIS)

Kang, D. I.; Jung, W. D.

2003-01-01

We review the Cause-Based Decision Tree (CBDT) approach to decide whether we incorporate it or not for the development of domestic standard Human Reliability Analysis (HRA) procedure in low power/shutdown operation Probabilistic Safety Assessment (PSA). In this paper, we introduce the cause based decision tree approach, quantify human errors using it, and identify merits and demerits of it in comparision with previously used THERP. The review results show that it is difficult to incorporate the CBDT method for the development of domestic standard HRA procedure in low power/shutdown PSA because the CBDT method need for the subjective judgment of HRA analyst like as THERP. However, it is expected that the incorporation of the CBDT method into the development of domestic standard HRA procedure only for the comparision of quantitative HRA results will relieve the burden of development of detailed HRA procedure and will help maintain consistent quantitative HRA results

9 CFR 113.33 - Mouse safety tests.

Science.gov (United States)

2010-01-01

... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Mouse safety tests. 113.33 Section 113.33 Animals and Animal Products ANIMAL AND PLANT HEALTH INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE... Procedures § 113.33 Mouse safety tests. One of the mouse safety tests provided in this section shall be...

Dam safety operating guidelines

International Nuclear Information System (INIS)

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

1990-01-01

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

Space station pressurized laboratory safety guidelines

Science.gov (United States)

Mcgonigal, Les

1990-01-01

Before technical safety guidelines and requirements are established, a common understanding of their origin and importance must be shared between Space Station Program Management, the User Community, and the Safety organizations involved. Safety guidelines and requirements are driven by the nature of the experiments, and the degree of crew interaction. Hazard identification; development of technical safety requirements; operating procedures and constraints; provision of training and education; conduct of reviews and evaluations; and emergency preplanning are briefly discussed.

Evaluation of aviation-based safety team training in a hospital in The Netherlands.

Science.gov (United States)

De Korne, Dirk F; Van Wijngaarden, Jeroen D H; Van Dyck, Cathy; Hiddema, U Francis; Klazinga, Niek S

2014-01-01

The purpose of this paper is to evaluate the implementation of a broad-scale team resource management (TRM) program on safety culture in a Dutch eye hospital, detailing the program's content and procedures. Aviation-based TRM training is recognized as a useful approach to increase patient safety, but little is known about how it affects safety culture. Pre- and post-assessments of the hospitals' safety culture was based on interviews with ophthalmologists, anesthesiologists, residents, nurses, and support staff. Interim observations were made at training sessions and in daily hospital practice. The program consisted of safety audits of processes and (team) activities, interactive classroom training sessions by aviation experts, a flight simulator session, and video recording of team activities with subsequent feedback. Medical professionals considered aviation experts inspiring role models and respected their non-hierarchical external perspective and focus on medical-technical issues. The post-assessment showed that ophthalmologists and other hospital staff had become increasingly aware of safety issues. The multidisciplinary approach promoted social (team) orientation that replaced the former functionally-oriented culture. The number of reported near-incidents greatly increased; the number of wrong-side surgeries stabilized to a minimum after an initial substantial reduction. The study was observational and the hospital's variety of efforts to improve safety culture prevented us from establishing a causal relation between improvement and any one specific intervention. Aviation-based TRM training can be a useful to stimulate safety culture in hospitals. Safety and quality improvements are not single treatment interventions but complex socio-technical interventions. A multidisciplinary system approach and focus on "team" instead of "profession" seems both necessary and difficult in hospital care.

Patient safety in thoracic surgery and European Society of Thoracic Surgeons checklist.

Science.gov (United States)

Novoa, Nuria M

2015-04-01

Improving patient safety seems to be a new interesting clinical subject but, in fact, it is no new. It has to do with one of the oldest ethical principles of our profession: curing and not harming. The important research that has been done in a short period of time has brought in new insight to this complex area that is fast developing. The creation of safety managing systems will allow coordinating efforts from very different, although complementary, areas to create real safety culture and safety climate in every organization. In the surgical settings, teamwork is basic to provide good quality of care. Safety leaders in every team have an important role in establishing priorities, summarizing proposals, coordinating efforts, launching new initiatives and transmitting that safety efforts are worth taken. Preparedness and anticipation are key points for avoiding most of the diverse types of patient harm that can occur. As has been published, a great number of errors can be avoided simply using crosscheck based on specialized checklist that reviews every important detail of the procedure. This strategy has been demonstrated very useful at other high risk industries such as aviation, nuclear or food management. The Safe Surgery Saves Lives program launched in 2002 by the WHO has taught us that improvement is possible using a simple checklist. More complex and detail checklist can be more adequate for more complex procedures and settings. The proposed ESTS checklist reviews different areas of possible error in deeper detail allowing the finest adjustment of the patient before the skin incision. It has been recently released to the general thoracic community and monitors its use and usefulness has to be warrantied.

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

International Nuclear Information System (INIS)

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

1991-01-01

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

16 CFR 1209.7 - Test procedures for smoldering combustion.

Science.gov (United States)

2010-01-01

... 16 Commercial Practices 2 2010-01-01 2010-01-01 false Test procedures for smoldering combustion. 1209.7 Section 1209.7 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION CONSUMER PRODUCT SAFETY... for smoldering combustion. This section provides the test method for determining smoldering combustion...

Safety advice sheets

CERN Multimedia

HSE Unit

2013-01-01

You never know when you might be faced with questions such as: when/how should I dispose of a gas canister? Where can I find an inspection report? How should I handle/store/dispose of a chemical substance…?   The SI section of the DGS/SEE Group is primarily responsible for safety inspections, evaluating the safety conditions of equipment items, premises and facilities. On top of this core task, it also regularly issues “Safety Advice Sheets” on various topics, designed to be of assistance to users but also to recall and reinforce safety rules and procedures. These clear and concise sheets, complete with illustrations, are easy to display in the appropriate areas. The following safety advice sheets have been issued so far: Other sheets will be published shortly. Suggestions are welcome and should be sent to the SI section of the DGS/SEE Group. Please send enquiries to general-safety-visits.service@cern.ch.

Perceptions of safety in the workplace

International Nuclear Information System (INIS)

Voelz, G.L.

1980-01-01

The concept of safety in the workplace is changing. Safety First was a slogan generated at a time when life and limb were at significant risk in many industries. Now much more subtle effects, such as late health effects due to industrial exposure and trauma, including mental stress, have become a concern to the safety specialists. Despite the changes in the concepts of safety today, the principles of safety in the workplace remain the same. They are management leadership, procedures, safe work conditions, safety training for supervisors and employees, medical surveillance, and careful accident reporting, investigation and record keeping

Postearthquake safety evaluation of buildings at DOE (Department of Energy) facilities

International Nuclear Information System (INIS)

Gallagher, R.

1989-01-01

New postearthquake building safety evaluation procedures have been developed. The procedures cover inspection and safety assessment of the principal types of building construction found in the US, including wood, masonry, tilt-up, concrete, and steel frame structures. Guidelines are also provided for appraising the structural safety significance of ground movements resulting from geologic hazards and for the inspection of nonstructural elements for falling and other hazards

AFROSAFE Championing Radiation Safety in Africa

International Nuclear Information System (INIS)

Nyabanda, R.

2015-01-01

AFRASAFE is a campaign that was formed by Pan African congress of Radiology and imaging (PACOR) and other radiation health workers in Africa in Feb 2015. Its main objective is to unite with a common goal to identify and address issues arising from radiation protection in medicine in Africa. Through this campaign, we state that we shall promote adherence to policies, strategies and activities for the promotion of radiation safety and for maximization of benefits from radiological medical procedures. The campaign strengthens the overall radiation protection of patients, health workers and public. It promotes safe and appropriate use of ionizing radiation in medicine and enhances global information to help improve the benefit/risk dialogue with patients and the public. It enhances the safety and quality of radiological procedures in medicine, and encourages safety in diagnostic and therapeutic equipment and facilities. The issue of research in radiation protection and safety needs to be promoted. This presentation will outline the six strategic objectives and the implementation tools for radiation safety in medicine in Kenya, the challenges and way forward to achieve our goal. (Author)

Safety culture of nuclear power plant

International Nuclear Information System (INIS)

Zheng Beixin

2008-01-01

This paper is a summary on the basis of DNMC safety culture training material for managerial personnel. It intends to explain the basic contents of safety, design, management, enterprise culture, safety culture of nuclear power plant and the relationship among them. It explains especially the constituent elements of safety culture system, the basic requirements for the three levels of commitments: policy level, management level and employee level. It also makes some analyses and judgments for some typical safety culture cases, for example, transparent culture and habitual violation of procedure. (authors)

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

Directory of Open Access Journals (Sweden)

N. A. Suponeva

2017-01-01

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

9 CFR 381.66 - Temperatures and chilling and freezing procedures.

Science.gov (United States)

2010-01-01

... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Temperatures and chilling and freezing procedures. 381.66 Section 381.66 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT... Procedures § 381.66 Temperatures and chilling and freezing procedures. (a) General. Temperatures and...

Safety Improvements on Wood Chippers Currently in Use: A Study on Feasibility in the Italian Context

Directory of Open Access Journals (Sweden)

Giorgia Bagagiolo

2017-12-01

Full Text Available Following formal opposition by France, the harmonized safety standards regarding manually-loaded wood chippers (EN 13525:2005+A2:2009 which presumed compliance with the Essential Health and Safety Requirements (EHSR required by the Machine Directive (Directive 2006/42/EC, have recently been withdrawn, and a new draft of the standard is currently under revision. In order to assess the potential impact of the expected future harmonized standards within the Italian context, this study has examined the main issues in implementing EHSRs on wood chippers already being used. Safety issues regarding wood chippers already in use were identified in an analysis of the draft standard, through the observation of a number of case studies, and qualitative analysis of the essential technical interventions. A number of agricultural and forestry operators and companies participated in the study, pointing out the technical and economic obstacle facing the safety features requested by the pending new standard. It emerged that the main safety issues concerned the implementation of the reverse function, the stop bar, and the protective devices, the infeed chute dimension, the emergency stop function, and the designated feeding area. The possibility of adopting such solutions mainly depends on technical feasibility and costs, but an important role is also played by the attitude towards safety and a lack of adequate information regarding safety obligations and procedures among users.

Methods for safety culture improvement

International Nuclear Information System (INIS)

Sivintsev, Yu.V.

1998-01-01

New IAEA publication concerning the problems of safety assurance covering different aspects beginning from terminology applied and up to concrete examples of well and poor safety culture development at nuclear facilities is discussed. The safety culture is defined as such set of characteristics and specific activities of institutions and individual persons which states that safety problems of a nuclear facility are given the attention determined by their importance as being of highest priority. The statements of the new document have recommended, not mandatory character. It is emphasized that the process of safety culture improvement at nuclear facilities should be integral component of management procedure, not a bolt on extra

Safety research for evolutionary light water reactors

International Nuclear Information System (INIS)

Cacuci, D.G.

1996-01-01

The development of nuclear energy has been characterized by a continuous evolution of the technological and philosophical underpinnings of reactor safety to enable operation of the plant without causing harm to either the plant operators or the public. Currently, the safety of a nuclear plant is assured through the combined use of procedures and engineered safety features together with a system of multiple protective barriers against the release of radioactivity. This approach is embodied in the concept of Design-Basis Accidents (DBA), which requires the designers to demonstrate that all credible accidents have been identified and that all safety equipment and procedures perform their functions extremely reliably. Particularly important functions are the automatic protection to shut the reactor down and to remove the decay heat while ensuring the integrity of the containment structure. Within the DBA concept, the so-called severe accidents were conveniently defined to be those accidents that lie beyond the DBA envelope; hence, they did not form part of the safety case. (author)

Safety research for evolutionary light water reactors

Energy Technology Data Exchange (ETDEWEB)

Cacuci, D G [Karlsruhe Univ. (T.H.) (Germany). Universitaetsbibliothek

1996-12-01

The development of nuclear energy has been characterized by a continuous evolution of the technological and philosophical underpinnings of reactor safety to enable operation of the plant without causing harm to either the plant operators or the public. Currently, the safety of a nuclear plant is assured through the combined use of procedures and engineered safety features together with a system of multiple protective barriers against the release of radioactivity. This approach is embodied in the concept of Design-Basis Accidents (DBA), which requires the designers to demonstrate that all credible accidents have been identified and that all safety equipment and procedures perform their functions extremely reliably. Particularly important functions are the automatic protection to shut the reactor down and to remove the decay heat while ensuring the integrity of the containment structure. Within the DBA concept, the so-called severe accidents were conveniently defined to be those accidents that lie beyond the DBA envelope; hence, they did not form part of the safety case. (author).

Estimate of Bariatric Surgery Numbers, 2011-2015

Science.gov (United States)

... Meetings of Interest Online Education Job Board CME Policies CBN Fellowship Certificate Research Grant Program Resources All Resources Approved Procedures Patient Safety Vignettes Dr. Mason Historical Library Governing Documents Guidelines Access and Insurance Position and ...

Development on inspection and recognition procedure of clearance level of radioactivity in metal wastes, to secure social safety for reused metals

International Nuclear Information System (INIS)

Hattori, Takatoshi

2002-01-01

The Central Research Institute of Electric Power Industry developed a new procedure automatically measurable on radioactivity level in metal wastes in high precision by using the newest three-dimensional (3D) shape measuring technology and 3D Monte-Carlo computing technology (a code to probabilistically compute formation and movement of gamma-ray from metal wastes to detectors) to contribute to inspection and recognition of clearance level of radioactivity. This procedure can prove no super micro amount of radioactivity of 250 Bq in metal wastes of testing objects. As this proof is an evaluation of conservative safety side showing no pollution at any 100 sq cm of surface of the metal wastes on considering for taking-out reference on matters, for its price, the procedure cancelled all of labors to test all of metal wastes surfaces by survey meter, and so on, and feasibility of overlook of pollution at places difficult to measure by using survey meters can perfectly excluded. Its practical tester is planned to produce at 2002 fiscal year, and testing performance against actual metal wastes is planned to confirm by its proof-test on 2003 to 2004 fiscal years. (G.K.)

16 CFR 1027.8 - Procedures for salary offset.

Science.gov (United States)

2010-01-01

... 16 Commercial Practices 2 2010-01-01 2010-01-01 false Procedures for salary offset. 1027.8 Section 1027.8 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION GENERAL SALARY OFFSET § 1027.8 Procedures for salary offset. (a) Deductions to liquidate an employee's debt will be by the method and in the...

Procedures manual for the Oak Ridge Electron Linear Accelerator

International Nuclear Information System (INIS)

Todd, H.A.

1979-01-01

The Procedures Manual for the Oak Ridge Electron Linear Accelerator contains specific information pertaining to operation and safety of the facility. Items such as the interlock system, radiation monitoring, emergency procedures, night shift and weekend operation, and maintenance are discussed in detail

Nuclear power plant's safety and risk (requirements of safety and reliability)

International Nuclear Information System (INIS)

Franzen, L.F.

1977-01-01

Starting out from the given safety objectives as they have evolved during the past few years and from the present legal and regulatory provisions for the construction and operation of nuclear power plants, the hazards involved in regular operation, accidents and emergency situations are discussed. In compliance with the positive safety balance of nuclear power plants in the FRG, special attention is focused on the preventive safety analysis within the frame of the nuclear licensing procedure. Reference is made to the beginnings of a comprehensive hazard concept for an unbiased plant assessment. Emergency situations are discussed from the point of view of general hazard comparisons. (orig.) [de

OIE philosophy, policy and procedures for the development of food safety standards.

Science.gov (United States)

Droppers, W F G L

2006-08-01

Food safety was identified as a high priority area in the 2001-2005 World Organisation for Animal Health (OIE) Strategic Plan. Member Countries of the OIE considered that the organisation should be more active in issues of public health and consumer protection and that this should include more involvement in the area of diseases or pathogens transmissible through food, whether or not animals are affected by such diseases or pathogens. A permanent Working Group on Animal Production Food Safety was established in 2002 to coordinate the OIE's activities in food safety. The Working Group was requested to focus on food safety measures applicable at farm level and to monitor the ongoing cooperation between the OIE and Codex Alimentarius. More emphasis is now placed on the public health aspects of a disease when OIE standards are developed or revised. For example, the revised chapter on bovine tuberculosis in the Terrestrial Animal Health Code includes food safety recommendations for meat and meat products and for milk and milk products. The revised chapter was approved by the OIE International Committee of Member Countries at their 73rd General Session in May 2005. More chapters will follow, beginning with a chapter addressing bovine brucellosis.

KIT safety management. Annual report 2012

International Nuclear Information System (INIS)

Frank, Gerhard

2013-01-01

The KIT Safety Management Service Unit (KSM) guarantees radiological and conventional technical safety and security of Karlsruhe Institute of Technology and controls the implementation and observation of legal environmental protection requirements. KSM is responsible for - licensing procedures, - industrial safety organization, - control of environmental protection measures, - planning and implementation of emergency preparedness and response, - operation of radiological laboratories and measurement stations, - extensive radiation protection support and the - the execution of security tasks in and for all organizational units of KIT. Moreover, KSM is in charge of wastewater and environmental monitoring for all facilities and nuclear installations all over the KIT campus. KSM is headed by the Safety Commissioner of KIT, who is appointed by the Presidential Committee. Within his scope of procedure for KIT, the Safety Commissioner controls the implementation of and compliance with safety-relevant requirements. The KIT Safety Management is certified according to DIN EN ISO 9001, its industrial safety management is certified by the VBG as ''AMS-Arbeitsschutz mit System'' and, hence, fulfills the requirements of NLF / ISO-OSH 2001. KSM laboratories are accredited according to DIN EN ISO/IEC 17025. To the extent possible, KSM is committed to maintaining competence in radiation protection and to supporting research and teaching activities. The present reports lists the individual tasks of the KIT Safety Management and informs about the results achieved in 2012. Status figures in principle reflect the status at the end of the year 2012. The processes described cover the areas of competence of KSM.

9 CFR 113.40 - Dog safety tests.

Science.gov (United States)

2010-01-01

... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Dog safety tests. 113.40 Section 113... Procedures § 113.40 Dog safety tests. The safety tests provided in this section shall be conducted when... recommended for use in dogs. Serials which are not found to be satisfactory when tested pursuant to the...

Microbial ecology laboratory procedures manual NASA/MSFC

Science.gov (United States)

Huff, Timothy L.

1990-01-01

An essential part of the efficient operation of any microbiology laboratory involved in sample analysis is a standard procedures manual. The purpose of this manual is to provide concise and well defined instructions on routine technical procedures involving sample analysis and methods for monitoring and maintaining quality control within the laboratory. Of equal importance is the safe operation of the laboratory. This manual outlines detailed procedures to be followed in the microbial ecology laboratory to assure safety, analytical control, and validity of results.

Radiation Exposure from Medical Exams and Procedures

Science.gov (United States)

Fact Sheet Adopted: January 2010 Health Physics Society Specialists in Radiation Safety Radiation Exposure from Medical Exams and Procedures Ionizing radiation is used daily in hospitals and clinics ...

Procedural sedation analgesia

OpenAIRE

Sheta, Saad A

2010-01-01

The number of noninvasive and minimally invasive procedures performed outside of the operating room has grown exponentially over the last several decades. Sedation, analgesia, or both may be needed for many of these interventional or diagnostic procedures. Individualized care is important when determining if a patient requires procedural sedation analgesia (PSA). The patient might need an anti-anxiety drug, pain medicine, immobilization, simple reassurance, or a combination of these interve...

Structural safety - Is the safety margin measurable

International Nuclear Information System (INIS)

Rintamaa, R.

1992-01-01

In ensuring the structural safety of the nuclear components one must be aware of the uncertainties related to the material deorientation, loadings and other operational conditions, geometrical dimensions as well as the service environment. Furthermore, the validation of the analysis tools and procedures is of great importance in overall safety assessment of a pressure retaining component. In order to identify and quantify the concerns and risks arising from the uncertainties in the safety related issue intensive research is being carried out all over the world, in particular, on the ageing, plant life extension and management of old nuclear power plants. The presentation includes a general survey of the factors relevant to the assessment of safe and reliable operation of a nuclear component throughout its planned service life. Certain aspects are outlined based on the research work being carried out at the Technical Research Centre of Finland (VTT)(orig.)

49 CFR 385.313 - Who will conduct the safety audit?

Science.gov (United States)

2010-10-01

... FITNESS PROCEDURES New Entrant Safety Assurance Program § 385.313 Who will conduct the safety audit? An individual certified under the FMCSA regulations to perform safety audits will conduct the safety audit. ... 49 Transportation 5 2010-10-01 2010-10-01 false Who will conduct the safety audit? 385.313 Section...

Fusion Imaging for Procedural Guidance.

Science.gov (United States)

Wiley, Brandon M; Eleid, Mackram F; Thaden, Jeremy J

2018-05-01

The field of percutaneous structural heart interventions has grown tremendously in recent years. This growth has fueled the development of new imaging protocols and technologies in parallel to help facilitate these minimally-invasive procedures. Fusion imaging is an exciting new technology that combines the strength of 2 imaging modalities and has the potential to improve procedural planning and the safety of many commonly performed transcatheter procedures. In this review we discuss the basic concepts of fusion imaging along with the relative strengths and weaknesses of static vs dynamic fusion imaging modalities. This review will focus primarily on echocardiographic-fluoroscopic fusion imaging and its application in commonly performed transcatheter structural heart procedures. Copyright © 2017 Sociedad Española de Cardiología. Published by Elsevier España, S.L.U. All rights reserved.

Occupational risk perception, safety training, and injury prevention: testing a model in the Italian printing industry.

Science.gov (United States)

Leiter, Michael P; Zanaletti, William; Argentero, Piergiorgio

2009-01-01

This study examined occupational risk perception in relation to safety training and injuries. In a printing industry, 350 workers from 6 departments completed a survey. Data analysis showed significant differences in risk perceptions among departments. Differences in risk perception reflected the type of work and the injury incidents in the departments. A structural equation analysis confirmed a model of risk perception on the basis of employees' evaluation of the prevalence and lethalness of hazards as well as the control over hazards they gain from training. The number of injuries sustained was positively related to the perception of risk exposure and negatively related to evaluations about the safety training. The results highlight the importance of training interventions in increasing workers' adoption of safety procedures and prevention of injuries.

12 CFR 1731.5 - Internal controls, procedures, and training.

Science.gov (United States)

2010-01-01

... 12 Banks and Banking 7 2010-01-01 2010-01-01 false Internal controls, procedures, and training... HOUSING AND URBAN DEVELOPMENT SAFETY AND SOUNDNESS MORTGAGE FRAUD REPORTING § 1731.5 Internal controls, procedures, and training. An Enterprise shall establish adequate and efficient internal controls and...

French regulatory approach to establishing the safety case for ageing NPP's

International Nuclear Information System (INIS)

Delage, M.

1994-06-01

The French regulatory procedures make provision for three main stages in the safety assessment of nuclear power plants. The first stage ends up with the construction licence and focuses on the assessment of the preliminary safety report. The second stage makes it possible to issue the fuel loading approval following evaluation of the provisional safety report. The third stage permits to declare the start of normal operation of the installation. The procedure, the tests and the assessment forming the overall strategy for safety regulations are described in detail. (R.P.)

Coagulation management in patients undergoing neurosurgical procedures.

Science.gov (United States)

Robba, Chiara; Bertuetti, Rita; Rasulo, Frank; Bertuccio, Alessando; Matta, Basil

2017-10-01

Management of coagulation in neurosurgical procedures is challenging. In this contest, it is imperative to avoid further intracranial bleeding. Perioperative bleeding can be associated with a number of factors, including anticoagulant drugs and coagulation status but is also linked to the characteristic and the site of the intracranial disorder. The aim of this review will be to focus primarily on the new evidence regarding the management of coagulation in patients undergoing craniotomy for neurosurgical procedures. Antihemostatic and anticoagulant drugs have shown to be associated with perioperative bleeding. On the other hand, an increased risk of venous thromboembolism and hypercoagulative state after elective and emergency neurosurgery, in particular after brain tumor surgery, has been described in several patients. To balance the risk between thrombosis and bleeding, it is important to be familiar with the perioperative changes in coagulation and with the recent management guidelines for anticoagulated patients undergoing neurosurgical procedures, in particular for those taking new direct anticoagulants. We have considered the current clinical trials and literature regarding both safety and efficacy of deep venous thrombosis prophylaxis in the neurosurgical population. These were mainly trials concerning both elective surgical and intensive care patients with a poor grade intracranial bleed or multiple traumas with an associated severe traumatic brain injury (TBI). Coagulation management remains a major issue in patients undergoing neurosurgical procedures. However, in this field of research, literature quality is poor and further studies are necessary to identify the best strategies to minimize risks in this group of patients.

Plant air systems safety study: Portsmouth Gaseous Diffusion Plant

International Nuclear Information System (INIS)

1982-05-01

The Portsmouth Gaseous Diffusion Plant Air System facilities and operations are reviewed for potential safety problems not covered by standard industrial safety procedures. Information is presented under the following section headings: facility and process description (general); air plant equipment; air distribution system; safety systems; accident analysis; plant air system safety overview; and conclusion

TU-FG-201-12: Designing a Risk-Based Quality Assurance Program for a Newly Implemented Y-90 Microspheres Procedure

Energy Technology Data Exchange (ETDEWEB)

Vile, D; Zhang, L; Cuttino, L; Kim, S; Palta, J [Virginia Commonwealth University, Richmond, VA (United States)

2016-06-15

Purpose: To create a quality assurance program based upon a risk-based assessment of a newly implemented SirSpheres Y-90 procedure. Methods: A process map was created for a newly implemented SirSpheres procedure at a community hospital. The process map documented each step of this collaborative procedure, as well as the roles and responsibilities of each member. From the process map, different potential failure modes were determined as well as any current controls in place. From this list, a full failure mode and effects analysis (FMEA) was performed by grading each failure mode’s likelihood of occurrence, likelihood of detection, and potential severity. These numbers were then multiplied to compute the risk priority number (RPN) for each potential failure mode. Failure modes were then ranked based on their RPN. Additional controls were then added, with failure modes corresponding to the highest RPNs taking priority. Results: A process map was created that succinctly outlined each step in the SirSpheres procedure in its current implementation. From this, 72 potential failure modes were identified and ranked according to their associated RPN. Quality assurance controls and safety barriers were then added for failure modes associated with the highest risk being addressed first. Conclusion: A quality assurance program was created from a risk-based assessment of the SirSpheres process. Process mapping and FMEA were effective in identifying potential high-risk failure modes for this new procedure, which were prioritized for new quality assurance controls. TG 100 recommends the fault tree analysis methodology to design a comprehensive and effective QC/QM program, yet we found that by simply introducing additional safety barriers to address high RPN failure modes makes the whole process simpler and safer.

TU-FG-201-12: Designing a Risk-Based Quality Assurance Program for a Newly Implemented Y-90 Microspheres Procedure

International Nuclear Information System (INIS)

Vile, D; Zhang, L; Cuttino, L; Kim, S; Palta, J

2016-01-01

Purpose: To create a quality assurance program based upon a risk-based assessment of a newly implemented SirSpheres Y-90 procedure. Methods: A process map was created for a newly implemented SirSpheres procedure at a community hospital. The process map documented each step of this collaborative procedure, as well as the roles and responsibilities of each member. From the process map, different potential failure modes were determined as well as any current controls in place. From this list, a full failure mode and effects analysis (FMEA) was performed by grading each failure mode’s likelihood of occurrence, likelihood of detection, and potential severity. These numbers were then multiplied to compute the risk priority number (RPN) for each potential failure mode. Failure modes were then ranked based on their RPN. Additional controls were then added, with failure modes corresponding to the highest RPNs taking priority. Results: A process map was created that succinctly outlined each step in the SirSpheres procedure in its current implementation. From this, 72 potential failure modes were identified and ranked according to their associated RPN. Quality assurance controls and safety barriers were then added for failure modes associated with the highest risk being addressed first. Conclusion: A quality assurance program was created from a risk-based assessment of the SirSpheres process. Process mapping and FMEA were effective in identifying potential high-risk failure modes for this new procedure, which were prioritized for new quality assurance controls. TG 100 recommends the fault tree analysis methodology to design a comprehensive and effective QC/QM program, yet we found that by simply introducing additional safety barriers to address high RPN failure modes makes the whole process simpler and safer.

Safety prediction technique for nuclear power plants

International Nuclear Information System (INIS)

Henry, C.D. III; Anderson, R.T.

1985-01-01

This paper presents a safety prediction technique (SPT) developed by Reliability Technology Associates (RTA) for nuclear power plants. It is based on a technique applied by RTA to assess the flight safety of US Air Force aircraft. The purpose of SPT is to provide a computerized technique for objective measurement of the effect on nuclear plant safety of component failure or procedural, software, or human error. A quantification is determined, called criticality, which is proportional to the probability that a given component or procedural-human action will cause the plant to operate in a hazardous mode. A hazardous mode is characterized by the fact that there has been a failure/error and the plant, its operating crew, and the public are exposed to danger. Whether the event results in an accident, an incident, or merely the exposure to danger is dependent on the skill and reaction of the operating crew as well as external influences. There are three major uses of SPT: (a) to predict unsafe situations so that corrective action can be taken before accidents occur, (b) to quantify the impact of equipment malfunction or procedural, software, or human error on safety and thereby establish priorities for proposed modifications, and (c) to provide a means of evaluating proposed changes for their impact on safety prior to implementation and to provide a method of tracking implemented changes

Analytical Chemistry Laboratory (ACL) procedure compendium

International Nuclear Information System (INIS)

1993-01-01

This volume contains the interim change notice for the safety operation procedure for hot cell. It covers the master-slave manipulators, dry waste removal, cell transfers, hoists, cask handling, liquid waste system, and physical characterization of fluids

Safety inspections to TRIGA reactors

International Nuclear Information System (INIS)

Byszewski, W.

1988-01-01

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

Safety Management at PUSPATI TRIGA Reactor (RTP)

International Nuclear Information System (INIS)

Ligam, A.S.; Zarina Masood; Ahmad Nabil Abdul Rahim

2011-01-01

Adequate safety measures and precautions, which follow relevant safety standards and procedures, should be in place so that personnel safety is assured. Nevertheless, the public, visitor, contractor or anyone who wishes to enter or be in the reactor building should be well informed with the safety measures applied. Furthermore, these same elements of safety are also applied to other irradiation facilities within the premises of Nuclear Malaysia. This paper will describes and explains current safety management system being enforced especially in the TRIGA PUSPATI Reactor (RTP) namely radiation monitoring system, safety equipment, safe work instruction, and interconnected internal and external health, safety and security related departments. (author)

Safety analyses for high-temperature reactors

International Nuclear Information System (INIS)

Mueller, A.

1978-01-01

The safety evaluation of HTRs may be based on the three methods presented here: The licensing procedure, the probabilistic risk analysis, and the damage extent analysis. Thereby all safety aspects - from normal operation to the extreme (hypothetical) accidents - of the HTR are covered. The analyses within the licensing procedure of the HTR-1160 have shown that for normal operation and for the design basis accidents the radiation exposures remain clearly below the maximum permissible levels as prescribed by the radiation protection ordinance, so that no real hazard for the population will avise from them. (orig./RW) [de

The complexity of patient safety reporting systems in UK dentistry.

Science.gov (United States)

Renton, T; Master, S

2016-10-21

Since the 'Francis Report', UK regulation focusing on patient safety has significantly changed. Healthcare workers are increasingly involved in NHS England patient safety initiatives aimed at improving reporting and learning from patient safety incidents (PSIs). Unfortunately, dentistry remains 'isolated' from these main events and continues to have a poor record for reporting and learning from PSIs and other events, thus limiting improvement of patient safety in dentistry. The reasons for this situation are complex.This paper provides a review of the complexities of the existing systems and procedures in relation to patient safety in dentistry. It highlights the conflicting advice which is available and which further complicates an overly burdensome process. Recommendations are made to address these problems with systems and procedures supporting patient safety development in dentistry.

Development of a safety parameter supervision system for Angra-1

International Nuclear Information System (INIS)

Silva, R.A. da; Thome Filho, Z.D.; Schirru, R.; Martinez, A.S.; Oliveira, L.F.S. de

1986-01-01

The Safety Parameter Supervision System (SSPS) which is a computerized system for monitoring essential parameters in real time, determining the safety status and emergency procedures for returning normal reactor operation, in case of an anomaly occurrence, is presented. The SSPS consists of three sub-systems: Integrated parameter monitoring system which gives to operators an integrated vision of values of a parameter set, able to detect any deviation of normal reactor operation; safety critical function system which evaluates safety status in terms of a safety critical function set appointed in advance, and in case of violation of any critical function, it initiates the adequate emergency procedure to return normal operation; and safety parameter computer system which carries out the arquirement of analogic and digital control signals of nuclear power plant. (M.C.K.) [pt