Benchmarking road safety performance: Identifying a meaningful reference (best-in-class).

Science.gov (United States)

Chen, Faan; Wu, Jiaorong; Chen, Xiaohong; Wang, Jianjun; Wang, Di

2016-01-01

For road safety improvement, comparing and benchmarking performance are widely advocated as the emerging and preferred approaches. However, there is currently no universally agreed upon approach for the process of road safety benchmarking, and performing the practice successfully is by no means easy. This is especially true for the two core activities of which: (1) developing a set of road safety performance indicators (SPIs) and combining them into a composite index; and (2) identifying a meaningful reference (best-in-class), one which has already obtained outstanding road safety practices. To this end, a scientific technique that can combine the multi-dimensional safety performance indicators (SPIs) into an overall index, and subsequently can identify the 'best-in-class' is urgently required. In this paper, the Entropy-embedded RSR (Rank-sum ratio), an innovative, scientific and systematic methodology is investigated with the aim of conducting the above two core tasks in an integrative and concise procedure, more specifically in a 'one-stop' way. Using a combination of results from other methods (e.g. the SUNflower approach) and other measures (e.g. Human Development Index) as a relevant reference, a given set of European countries are robustly ranked and grouped into several classes based on the composite Road Safety Index. Within each class the 'best-in-class' is then identified. By benchmarking road safety performance, the results serve to promote best practice, encourage the adoption of successful road safety strategies and measures and, more importantly, inspire the kind of political leadership needed to create a road transport system that maximizes safety. Copyright © 2015 Elsevier Ltd. All rights reserved.

Safety regulations concerning instrumentation and control systems for research reactors

International Nuclear Information System (INIS)

El-Shanshoury, A.I.

2009-01-01

A brief study on the safety and reliability issues related to instrumentation and control systems in nuclear reactor plants is performed. In response, technical and strategic issues are used to accomplish instrumentation and control systems safety. For technical issues there are ; systems aspects of digital I and C technology, software quality assurance, common-mode software, failure potential, safety and reliability assessment methods, and human factors and human machine interfaces. The strategic issues are the case-by-case licensing process and the adequacy of the technical infrastructure. The purpose of this work was to review the reliability of the safety systems related to these technical issues for research reactors

Standardization and improvement of safety for radioisotope equipped instruments

International Nuclear Information System (INIS)

Sumi, Tetsuo

1980-01-01

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

Design review report for modifications to RMCS safety class equipment

International Nuclear Information System (INIS)

Corbett, J.E.

1997-01-01

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

Design review report for modifications to RMCS safety class equipment

Energy Technology Data Exchange (ETDEWEB)

Corbett, J.E.

1997-05-30

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

Automatic creation of Markov models for reliability assessment of safety instrumented systems

International Nuclear Information System (INIS)

Guo Haitao; Yang Xianhui

2008-01-01

After the release of new international functional safety standards like IEC 61508, people care more for the safety and availability of safety instrumented systems. Markov analysis is a powerful and flexible technique to assess the reliability measurements of safety instrumented systems, but it is fallible and time-consuming to create Markov models manually. This paper presents a new technique to automatically create Markov models for reliability assessment of safety instrumented systems. Many safety related factors, such as failure modes, self-diagnostic, restorations, common cause and voting, are included in Markov models. A framework is generated first based on voting, failure modes and self-diagnostic. Then, repairs and common-cause failures are incorporated into the framework to build a complete Markov model. Eventual simplification of Markov models can be done by state merging. Examples given in this paper show how explosively the size of Markov model increases as the system becomes a little more complicated as well as the advancement of automatic creation of Markov models

Performance Monitoring for Nuclear Safety Related Instrumentation at PUSPATI TRIGA Reactor (RTP)

International Nuclear Information System (INIS)

Zareen Khan Abdul Jalil Khan; Ridzuan Abdul Mutalib; Mohd Sabri Minhat

2015-01-01

The Reactor TRIGA PUSPATI (RTP) at Malaysia Nuclear Agency is a TRIGA Mark II type reactor and pool type cooled by natural circulation of light water. This paper describe on performance monitoring for nuclear safety related instrumentation in TRIGA PUSPATI Reactor (RTP) of based on various parameter of reactor safety instrument channel such as log power, linear power, Fuel temperature, coolant temperature will take into consideration. Methodology of performance on estimation and monitoring is to evaluate and analysis of reactor parameters which is important of reactor safety and control. And also to estimate power measurement, differential of log and linear power and fuel temperature during reactor start-up, operation and shutdown .This study also focus on neutron power fluctuation from fission chamber during reactor start-up and operation. This work will present result of performance monitoring from RTP which indicated the safety parameter identification and initiate safety action on crossing the threshold set point trip. Conclude that performance of nuclear safety related instrumentation will improved the reactor control and safety parameter during reactor start-up, operation and shutdown. (author)

Construction and Validation of an Instrument to Measure Taiwanese Elementary Students' Attitudes toward Their Science Class

Science.gov (United States)

Wang, Tzu-Ling; Berlin, Donna

2010-12-01

The main purpose of this study is to develop a valid and reliable instrument for measuring the attitudes toward science class of fourth- and fifth-grade students in an Asian school culture. Specifically, the development focused on three science attitude constructs-science enjoyment, science confidence, and importance of science as related to science class experiences. A total of 265 elementary school students in Taiwan responded to the instrument developed. Data analysis indicated that the instrument exhibited satisfactory validity and reliability with the Taiwan population used. The Cronbach's alpha coefficient was 0.93 for the entire instrument indicating a satisfactory level of internal consistency. However, both principal component analysis and parallel analysis showed that the three attitude scales were not unique and should be combined and used as a general "attitudes toward science class" scale. The analysis also showed that there were no gender or grade-level differences in students' overall attitudes toward science class.

Value of preapproval safety data in predicting postapproval hepatic safety and assessing the legitimacy of class warning.

Science.gov (United States)

Lin, Yeong-Liang; Wu, Ya-Chi; Gau, Churn-Shiouh; Lin, Min-Shung

2012-02-01

The objective of this study was to systematically evaluate whether preapproval safety data for nonhepatotoxic drugs and hepatotoxic drugs can be compared to improve preapproval prediction of postapproval hepatic safety and to assess the legitimacy of applying class warnings. Drugs within a therapeutic class that included at least one drug that had been withdrawn from the market because of liver toxicity or had a warning of potential liver toxicity issued by major regulatory agencies, and at least one drug free from such regulatory action, were identified and divided into two groups: drugs with and drugs without regulatory action. Preapproval clinical data [including the elevation rates of alanine aminotransferse (ALT) and withdrawal due to liver toxicity, the number of patients with combined elevation of ALT and bilirubin, and liver failure] and nonclinical data (including chemical structures, metabolic pathways, and other significant findings in animal studies) were compared between the two groups. Six drug classes were assessed in this study: thiazolidinediones, cyclooxygenase-2 inhibitors, fluoroquinolones, catechol-O-methyltransferase (COMT) inhibitors, leukotriene receptor inhibitors, and endothelin receptor antagonists. In two classes (COMT inhibitors and endothelin receptor antagonists), drugs with regulatory action had significantly higher rates of ALT elevation of more than threefold and greater numbers of patients with combined elevation of ALT and bilirubin than drugs without regulatory action. Drugs with regulatory action also had chemical structures or metabolic pathways associated with the toxicity. The legitimacy of class warnings was refuted in all six classes of drugs. Preapproval safety data may help predict postapproval hepatic safety and can be used to assess the legitimacy of applying class warnings.

Structural evaluation of safety class components to natural phenomena loadings

International Nuclear Information System (INIS)

Conrads, T.J.

1989-01-01

This paper addresses the efforts completed at the US Department of Energy Hanford Site near Richland, Washington, to qualify structurally a number of existing safety class components in the Plutonium Finishing Plant complex. Design, fabrication, and installation of the facility occurred in the 1950s and 1960s and were based on the Uniform Building Code criteria for wind and earthquake loads. Recently the buildings were qualified to site-specific wind and seismic hazards. The methodology employed to qualify seismically the safety class components is discussed

Review of design criteria and safety analysis of safety class electric building for fuel test loop

Energy Technology Data Exchange (ETDEWEB)

Kim, J. Y.

1998-02-01

Steady state fuel test loop will be equipped in HANARO to obtain the development and betterment of advanced fuel and materials through the irradiation tests. HANARO fuel test loop was designed for CANDU and PWR fuel testing. Safety related system of Fuel Test Loop such as emergency cooling water system, component cooling water system, safety ventilation system, high energy line break mitigation system and remote control room was required 1E class electric supply to meet the safety operation in accordance with related code. Therefore, FTL electric building was designed to construction and install the related equipment based on seismic category I. The objective of this study is to review the design criteria and analysis the safety function of safety class electric building for fuel test loop, and this results will become guidance for the irradiation testing in future. (author). 10 refs., 6 tabs., 30 figs.

Discussion map and cooking classes: testing the effectiveness of teaching food safety to immigrants and refugees.

Science.gov (United States)

Gold, Abby; Yu, Nan; Buro, Brandy; Garden-Robinson, Julie

2014-01-01

To evaluate the effectiveness of a food safety map as an educational method with English language learners. English language learner community members (n = 73) were assigned randomly to participate in 1 of 3 experimental conditions: food safety map, cooking class, and control. Participants in the food safety map and cooking class conditions completed a pre-education demographic and cooking history questionnaire, a post-education knowledge and intention questionnaire, and a 2-week post-cooking and food safety habits assessment. Participants in the control group received no educational training but completed the pre- and 2-week post-education assessments. The cooking class and the map class were both effective in increasing food safety knowledge. Specifically, by comparing with the control group, they significantly increased participants' knowledge of safely cooking large meat (χ² [df = 2, n = 66] = 40.87; P effects on boosting food safety behavioral intention (measured right after the class). The data collected 2 weeks after the classes suggested that individuals who took the classes followed the suggested food behaviors more closely than those in the control group (P < .01). The food safety map is simple to use and prepare, beneficial for oral and visual learners, and inexpensive. Compared with a food safety cooking class, the map produces similar learning and behavioral outcomes. Copyright © 2014 Society for Nutrition Education and Behavior. Published by Elsevier Inc. All rights reserved.

Research and design of hanger and support series of nuclear safety class process piping

International Nuclear Information System (INIS)

Mao Chengzhang; Shi Jiemin

1995-12-01

Hangers and supports of nuclear safety class piping are an important part of primary system piping in a nuclear power plant. They will directly affect the reliability of operation, the period at construction and the investment for a nuclear power plant. It is an absolutely necessary job for Pakistan Chashma Nuclear Power Plant Project to research and design a series of piping supports in accordance with ASME-III NF. It is also an important designing for developing nuclear power plant later in China. After working over two years, a series of piping supports of nuclear safety class which have 57 types and more than 2460 specifications have been designed. This series is perfect, and can satisfy the requirements of piping final designing for nuclear power plant. This series of hangers and supports is mainly used in the process piping of nuclear safety class 1,2,3. They can also be used in other piping of nuclear safety class and piping with aseismic requirement of non-nuclear safety class

Project W-030 safety class upgrade summary report

International Nuclear Information System (INIS)

Kriskovich, J.R.

1998-01-01

This document presents a summary of safety class criteria for the 241-AY/AZ Tank Farm primary ventilation system upgrade under Project W-030, and recommends acceptance of the system as constructed, based on a review of supporting documentation

New trends in pile safety instrumentation; Les tendances nouvelles dans l'instrumentation de securite des piles

Energy Technology Data Exchange (ETDEWEB)

Furet, J.

1961-04-19

This report addresses the protection of nuclear piles against damages due to operation incidents. The author discusses the current trends in the philosophy of safety of atomic power piles, identifies the parameters which define safety systems, presents tests to be performed on safety chains, comments the relationship between safety and the decrease of the number of pile inadvertent shutdowns, discusses the issues of instrument failures and chain multiplicity, comments the possible improvement of the operation of elements which build up safety chains (design simplification, development of semiconductors, replacement of electromechanical relays by static relays), the role of safety logical computers and the development of automatics in pile safety, presents automatic control as a safety factor (example of automatic start-up), and finally comments the use of fuses.

Audit Report The Procurement of Safety Class/Safety-Significant Items at the Savannah River Site

International Nuclear Information System (INIS)

2009-01-01

The Department of Energy operates several nuclear facilities at its Savannah River Site, and several additional facilities are under construction. This includes the National Nuclear Security Administration's Tritium Extraction Facility (TEF) which is designated to help maintain the reliability of the U.S. nuclear stockpile. The Mixed Oxide Fuel Fabrication Facility (MOX Facility) is being constructed to manufacture commercial nuclear reactor fuel assemblies from weapon-grade plutonium oxide and depleted uranium. The Interim Salt Processing (ISP) project, managed by the Office of Environmental Management, will treat radioactive waste. The Department has committed to procuring products and services for nuclear-related activities that meet or exceed recognized quality assurance standards. Such standards help to ensure the safety and performance of these facilities. To that end, it issued Departmental Order 414.1C, Quality Assurance (QA Order). The QA Order requires the application of Quality Assurance Requirements for Nuclear Facility Applications (NQA-1) for nuclear-related activities. The NQA-1 standard provides requirements and guidelines for the establishment and execution of quality assurance programs during the siting, design, construction, operation, and decommissioning of nuclear facilities. These requirements, promulgated by the American Society of Mechanical Engineers, must be applied to 'safety-class' and 'safety-significant' structures, systems and components (SSCs). Safety-class SSCs are defined as those necessary to prevent exposure off site and to protect the public. Safety-significant SSCs are those whose failure could irreversibly impact worker safety such as a fatality, serious injury, or significant radiological or chemical exposure. Due to the importance of protecting the public, workers, and environment, we initiated an audit to determine whether the Department of Energy procured safety-class and safety-significant SSCs that met NQA-1 standards at

78 FR 48294 - Amendment of Class E Airspace; Mason, TX

Science.gov (United States)

2013-08-08

...-1141; Airspace Docket No. 12-ASW-12] Amendment of Class E Airspace; Mason, TX AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Final rule. SUMMARY: This action amends Class E airspace at Mason, TX... Approach Procedures at Mason County Airport. This action enhances the safety and management of Instrument...

77 FR 16783 - Proposed Amendment of Class E Airspace; Orlando, FL

Science.gov (United States)

2012-03-22

...-0503; Airspace Docket No. 11-ASO-19] Proposed Amendment of Class E Airspace; Orlando, FL AGENCY... action proposes to amend Class E Airspace at Orlando, FL, as new Standard Instrument Approach Procedures have been developed at Orlando Executive Airport. This action would enhance the safety and airspace...

OASIS: An automotive analysis and safety engineering instrument

International Nuclear Information System (INIS)

Mader, Roland; Armengaud, Eric; Grießnig, Gerhard; Kreiner, Christian; Steger, Christian; Weiß, Reinhold

2013-01-01

In this paper, we describe a novel software tool named OASIS (AutOmotive Analysis and Safety EngIneering InStrument). OASIS supports automotive safety engineering with features allowing the creation of consistent and complete work products and to simplify and automate workflow steps from early analysis through system development to software development. More precisely, it provides support for (a) model creation and reuse, (b) analysis and documentation and (c) configuration and code generation. We present OASIS as a part of a tool chain supporting the application of a safety engineering workflow aligned with the automotive safety standard ISO 26262. In particular, we focus on OASIS' (1) support for property checking and model correction as well as its (2) support for fault tree generation and FMEA (Failure Modes and Effects Analysis) table generation. Finally, based on the case study of hybrid electric vehicle development, we demonstrate that (1) and (2) are able to strongly support FTA (Fault Tree Analysis) and FMEA

75 FR 6592 - Proposed Amendment of Class E Airspace; Emmetsburg, IA

Science.gov (United States)

2010-02-10

...-1153; Airspace Docket No. 09-ACE-13] Proposed Amendment of Class E Airspace; Emmetsburg, IA AGENCY... action proposes to amend Class E airspace at Emmetsburg, IA. Additional controlled airspace is necessary..., Emmetsburg, IA. The FAA is taking this action to enhance the safety and management of Instrument Flight Rules...

75 FR 6595 - Proposed Amendment of Class E Airspace; Mapleton, IA

Science.gov (United States)

2010-02-10

...-1155; Airspace Docket No. 09-ACE-14] Proposed Amendment of Class E Airspace; Mapleton, IA AGENCY... action proposes to amend Class E airspace at Mapleton, IA. Additional controlled airspace is necessary to..., Mapleton, IA. The FAA is taking this action to enhance the safety and management of Instrument Flight Rules...

Design and installation of advanced computer safety related instrumentation

International Nuclear Information System (INIS)

Koch, S.; Andolina, K.; Ruether, J.

1993-01-01

The rapidly developing area of computer systems creates new opportunities for commercial utilities operating nuclear reactors to improve plant operation and efficiency. Two of the main obstacles to utilizing the new technology in safety-related applications is the current policy of the licensing agencies and the fear of decision making managers to introduce new technologies. Once these obstacles are overcome, advanced diagnostic systems, CRT-based displays, and advanced communication channels can improve plant operation considerably. The article discusses outstanding issues in the area of designing, qualifying, and licensing of computer-based instrumentation and control systems. The authors describe the experience gained in designing three safety-related systems, that include a Programmable Logic Controller (PLC) based Safeguard Load Sequencer for NSP Prairie Island, a digital Containment Isolation monitoring system for TVA Browns Ferry, and a study that was conducted for EPRI/NSP regarding a PLC-based Reactor Protection system. This article presents the benefits to be gained in replacing existing, outdated equipment with new advanced instrumentation

Instrumental variable methods in comparative safety and effectiveness research.

Science.gov (United States)

Brookhart, M Alan; Rassen, Jeremy A; Schneeweiss, Sebastian

2010-06-01

Instrumental variable (IV) methods have been proposed as a potential approach to the common problem of uncontrolled confounding in comparative studies of medical interventions, but IV methods are unfamiliar to many researchers. The goal of this article is to provide a non-technical, practical introduction to IV methods for comparative safety and effectiveness research. We outline the principles and basic assumptions necessary for valid IV estimation, discuss how to interpret the results of an IV study, provide a review of instruments that have been used in comparative effectiveness research, and suggest some minimal reporting standards for an IV analysis. Finally, we offer our perspective of the role of IV estimation vis-à-vis more traditional approaches based on statistical modeling of the exposure or outcome. We anticipate that IV methods will be often underpowered for drug safety studies of very rare outcomes, but may be potentially useful in studies of intended effects where uncontrolled confounding may be substantial.

Instrumental variable methods in comparative safety and effectiveness research†

Science.gov (United States)

Brookhart, M. Alan; Rassen, Jeremy A.; Schneeweiss, Sebastian

2010-01-01

Summary Instrumental variable (IV) methods have been proposed as a potential approach to the common problem of uncontrolled confounding in comparative studies of medical interventions, but IV methods are unfamiliar to many researchers. The goal of this article is to provide a non-technical, practical introduction to IV methods for comparative safety and effectiveness research. We outline the principles and basic assumptions necessary for valid IV estimation, discuss how to interpret the results of an IV study, provide a review of instruments that have been used in comparative effectiveness research, and suggest some minimal reporting standards for an IV analysis. Finally, we offer our perspective of the role of IV estimation vis-à-vis more traditional approaches based on statistical modeling of the exposure or outcome. We anticipate that IV methods will be often underpowered for drug safety studies of very rare outcomes, but may be potentially useful in studies of intended effects where uncontrolled confounding may be substantial. PMID:20354968

On safety classification of instrumentation and control systems and their components

International Nuclear Information System (INIS)

Yastrebenetskij, M.A.; Rozen, Yu.V.

2004-01-01

Safety classification of instrumentation and control systems (I and C) and their components (hardware, software, software-hardware complexes) is described: - evaluation of classification principles and criteria in Ukrainian standards and rules; comparison between Ukrainian and international principles and criteria; possibility and ways of coordination of Ukrainian and international standards related to (I and C) safety classification

Creation and Support of the State of Psychological Safety of Pupils of Cadet Classes

Directory of Open Access Journals (Sweden)

Baeva I.A.,

2017-01-01

Full Text Available The author's approach to the support of psychological safety in the educational process. As cadet classes make high demands to the capabilities and resources of the child, the task of tracking these educational programs in terms of psychological safety of children is particularly relevant. The study tested the assumption that the program support the state of psychological safety, implementing a risk-resource approach and aimed at updating / generation components of psychological safety (satisfaction, protection, reference, subjective well-being of the child in the Cadet educational environment, activity, will be effective when accompanied by cadet training programs. Testing of the developed program was carried out with students of third cadet classes (53 people in the experimental group and 26 in the control group. components and criteria of psychological safety of the younger schoolboy were determined on the basis of theoretical analysis. The methods of interrogation (questioning, testing, projective method examined the children, parents and teachers in the cadet classes to identify the initial and final levels of psychological safety of younger students. Statistical analysis were used cluster and discriminant analysis, chi-square test for contingency tables, sign test G. The article describes the features of the program, aimed at the formation and maintenance of psychological safety of younger pupils, pupils of cadet classes. The efficiency of it on all the selected criteria with a level of significance of not more than p <0,005. Ideas forming program can be used in the practice of psychological work in schools, as well as for further research of psychological safety of children in the educational environment of schools of different types and species.

Regulatory instrument review: Management of aging of LWR [light water reactor] major safety-related components

International Nuclear Information System (INIS)

Werry, E.V.

1990-10-01

This report comprises Volume 1 of a review of US nuclear plant regulatory instruments to determine the amount and kind of information they contain on managing the aging of safety-related components in US nuclear power plants. The review was conducted for the US Nuclear Regulatory Commission (NRC) by the Pacific Northwest Laboratory (PNL) under the NRC Nuclear Plant Aging Research (NPAR) Program. Eight selected regulatory instruments, e.g., NRC Regulatory Guides and the Code of Federal Regulations, were reviewed for safety-related information on five selected components: reactor pressure vessels, steam generators, primary piping, pressurizers, and emergency diesel generators. Volume 2 will be concluded in FY 1991 and will also cover selected major safety-related components, e.g., pumps, valves and cables. The focus of the review was on 26 NPAR-defined safety-related aging issues, including examination, inspection, and maintenance and repair; excessive/harsh testing; and irradiation embrittlement. The major conclusion of the review is that safety-related regulatory instruments do provide implicit guidance for aging management, but include little explicit guidance. The major recommendation is that the instruments be revised or augmented to explicitly address the management of aging

Validity of instruments to assess students' travel and pedestrian safety.

Science.gov (United States)

Mendoza, Jason A; Watson, Kathy; Baranowski, Tom; Nicklas, Theresa A; Uscanga, Doris K; Hanfling, Marcus J

2010-05-18

Safe Routes to School (SRTS) programs are designed to make walking and bicycling to school safe and accessible for children. Despite their growing popularity, few validated measures exist for assessing important outcomes such as type of student transport or pedestrian safety behaviors. This research validated the SRTS school travel survey and a pedestrian safety behavior checklist. Fourth grade students completed a brief written survey on how they got to school that day with set responses. Test-retest reliability was obtained 3-4 hours apart. Convergent validity of the SRTS travel survey was assessed by comparison to parents' report. For the measure of pedestrian safety behavior, 10 research assistants observed 29 students at a school intersection for completion of 8 selected pedestrian safety behaviors. Reliability was determined in two ways: correlations between the research assistants' ratings to that of the Principal Investigator (PI) and intraclass correlations (ICC) across research assistant ratings. The SRTS travel survey had high test-retest reliability (kappa = 0.97, n = 96, p < 0.001) and convergent validity (kappa = 0.87, n = 81, p < 0.001). The pedestrian safety behavior checklist had moderate reliability across research assistants' ratings (ICC = 0.48) and moderate correlation with the PI (r = 0.55, p = < 0.01). When two raters simultaneously used the instrument, the ICC increased to 0.65. Overall percent agreement (91%), sensitivity (85%) and specificity (83%) were acceptable. These validated instruments can be used to assess SRTS programs. The pedestrian safety behavior checklist may benefit from further formative work.

Computer Security of NPP Instrumentation and Control Systems: Cyber Threats

International Nuclear Information System (INIS)

Klevtsov, A.L.; Trubchaninov, S.A.

2015-01-01

The paper is devoted to cyber threats, as one of the aspects in computer security of instrumentation and control systems for nuclear power plants (NPP). The basic concepts, terms and definitions are shortly addressed. The paper presents a detailed analysis of potential cyber threats during the design and operation of NPP instrumentation and control systems. Eleven major types of threats are considered, including: the malicious software and hardware Trojans (in particular, in commercial-off-the-shelf software and hardware), computer attacks through data networks and intrusion of malicious software from an external storage media and portable devices. Particular attention is paid to the potential use of lower safety class software as a way of harmful effects (including the intrusion of malicious fragments of code) on higher safety class software. The examples of actual incidents at various nuclear facilities caused by intentional cyber attacks or unintentional computer errors during the operation of software of systems important to NPP safety.

75 FR 68558 - Proposed Establishment of Class E Airspace; New Hampton, IA

Science.gov (United States)

2010-11-08

...-1035; Airspace Docket No. 10-ACE-12] Proposed Establishment of Class E Airspace; New Hampton, IA AGENCY... action proposes to establish Class E airspace at New Hampton, IA, to accommodate new Standard Instrument... Mercy Medical Center Heliport, New Hampton, IA. Controlled airspace is needed for the safety and...

Impact of proof test interval and coverage on probability of failure of safety instrumented function

International Nuclear Information System (INIS)

Jin, Jianghong; Pang, Lei; Hu, Bin; Wang, Xiaodong

2016-01-01

Highlights: • Introduction of proof test coverage makes the calculation of the probability of failure for SIF more accurate. • The probability of failure undetected by proof test is independently defined as P TIF and calculated. • P TIF is quantified using reliability block diagram and simple formula of PFD avg . • Improving proof test coverage and adopting reasonable test period can reduce the probability of failure for SIF. - Abstract: Imperfection of proof test can result in the safety function failure of safety instrumented system (SIS) at any time in its life period. IEC61508 and other references ignored or only elementarily analyzed the imperfection of proof test. In order to further study the impact of the imperfection of proof test on the probability of failure for safety instrumented function (SIF), the necessity of proof test and influence of its imperfection on system performance was first analyzed theoretically. The probability of failure for safety instrumented function resulted from the imperfection of proof test was defined as probability of test independent failures (P TIF ), and P TIF was separately calculated by introducing proof test coverage and adopting reliability block diagram, with reference to the simplified calculation formula of average probability of failure on demand (PFD avg ). Research results show that: the shorter proof test period and the higher proof test coverage indicate the smaller probability of failure for safety instrumented function. The probability of failure for safety instrumented function which is calculated by introducing proof test coverage will be more accurate.

Safety critical FPGA-based NPP instrumentation and control systems: assessment, development and implementation

International Nuclear Information System (INIS)

Bakhmach, E. S.; Siora, A. A.; Tokarev, V. I.; Kharchenko, V. S.; Sklyar, V. V.; Andrashov, A. A.

2010-10-01

The stages of development, production, verification, licensing and implementation methods and technologies of safety critical instrumentation and control systems for nuclear power plants (NPP) based on FPGA (Field Programmable Gates Arrays) technologies are described. A life cycle model and multi-version technologies of dependability and safety assurance of FPGA-based instrumentation and control systems are discussed. An analysis of NPP instrumentation and control systems construction principles developed by Research and Production Corporation Radiy using FPGA-technologies and results of these systems implementation and operation at Ukrainian and Bulgarian NPP are presented. The RADIY TM platform has been designed and developed by Research and Production Corporation Radiy, Ukraine. The main peculiarity of the RADIY TM platform is the use of FPGA as programmable components for logic control operation. The FPGA-based RADIY TM platform used for NPP instrumentation and control systems development ensures sca lability of system functions types, volume and peculiarities (by changing quantity and quality of sensors, actuators, input/output signals and control algorithms); sca lability of dependability (safety integrity) (by changing a number of redundant channel, tiers, diagnostic and reconfiguration procedures); sca lability of diversity (by changing types, depth and method of diversity selection). (Author)

Safety learning from drugs of the same class

DEFF Research Database (Denmark)

Stefansdottir, G; Knol, M J; Arnardottir, A H

2012-01-01

This study was aimed at assessing the extent of safety learning from data pertaining to other drugs of the same class. We studied drug classes for which the first and second drugs were centrally registered in the European Union from 1995 to 2008. We assessed whether adverse drug reactions (ADRs......) associated with one of the drugs also appeared in the Summary of Product Characteristics (SPC) of the other drug, either initially or during the postmarketing phase. We identified 977 ADRs from 19 drug pairs, of which 393 ADRs (40.2%) were listed in the SPCs of both drugs of a pair. Of these 393 that were...... present in both SPCs of a drug pair, 241 (61.3%) were present when the drug entered the market and 152 (30.7%) appeared in the postmarketing phase. The mention of ADRs in the SPCs of both same-class drugs in the postmarketing phase was associated with type A ADRs, marketing in the same regulator country...

Analysis on typical illegal events for nuclear safety class 1 valve

International Nuclear Information System (INIS)

Tian Dongqing; Gao Runsheng; Jiao Dianhui; Yang Lili; Chen Peng

2014-01-01

Illegal welding events of nuclear safety class l valve forging occurred to the manufacturer, while the valve was returned to be repaired. Illegal nondestructive test event of nuclear safety class valve occurred also to the manufacturer in the manufacturing process. The two events have resulted in quality incipient fault for the installed valves and the valves in the manufacturing process. It was reflected that operation of the factory quality assurance system isn't activated, and nuclear power engineering and operating company have insufficient supervision. The event-related parties should strengthen quality management and process control, get rid of the quality incipient fault, and experience feedback should be done well to guarantee quality of equipment in nuclear power plant. (authors)

The Designing Bus for Nuclear Safety Class Controller

Energy Technology Data Exchange (ETDEWEB)

Lee, Dongil; Lee, Myeongkyun; Yun, Donghwa [PONUTech Co,. Ltd., Research Institute, Ulsan (Korea, Republic of); Ryoo, Kwangki [Hanbat National Univ., Daejeon (Korea, Republic of)

2013-10-15

EtherCAT (Ethernet for Control Automation Technology) is based on the IEEE 802.3 standard as one of the communication which is the I/O (Input/Output), sensors and communication function of PLC (Programmable Logic Controller) in industry and factory environment use is increasing. The Nuclear Safety Class Controller implemented by the EtherCAT applied bus can be shown the improving performance of data transmission in the controller.

The Designing Bus for Nuclear Safety Class Controller

International Nuclear Information System (INIS)

Lee, Dongil; Lee, Myeongkyun; Yun, Donghwa; Ryoo, Kwangki

2013-01-01

EtherCAT (Ethernet for Control Automation Technology) is based on the IEEE 802.3 standard as one of the communication which is the I/O (Input/Output), sensors and communication function of PLC (Programmable Logic Controller) in industry and factory environment use is increasing. The Nuclear Safety Class Controller implemented by the EtherCAT applied bus can be shown the improving performance of data transmission in the controller

Safety critical FPGA-based NPP instrumentation and control systems: assessment, development and implementation

Energy Technology Data Exchange (ETDEWEB)

Bakhmach, E. S.; Siora, A. A.; Tokarev, V. I. [Research and Production Corporation Radiy, 29 Geroev Stalingrada Str., Kirovograd 25006 (Ukraine); Kharchenko, V. S.; Sklyar, V. V.; Andrashov, A. A., E-mail: marketing@radiy.co [Center for Safety Infrastructure-Oriented Research and Analysis, 37 Astronomicheskaya Str., Kharkiv 61085 (Ukraine)

2010-10-15

The stages of development, production, verification, licensing and implementation methods and technologies of safety critical instrumentation and control systems for nuclear power plants (NPP) based on FPGA (Field Programmable Gates Arrays) technologies are described. A life cycle model and multi-version technologies of dependability and safety assurance of FPGA-based instrumentation and control systems are discussed. An analysis of NPP instrumentation and control systems construction principles developed by Research and Production Corporation Radiy using FPGA-technologies and results of these systems implementation and operation at Ukrainian and Bulgarian NPP are presented. The RADIY{sup TM} platform has been designed and developed by Research and Production Corporation Radiy, Ukraine. The main peculiarity of the RADIY{sup TM} platform is the use of FPGA as programmable components for logic control operation. The FPGA-based RADIY{sup TM} platform used for NPP instrumentation and control systems development ensures sca lability of system functions types, volume and peculiarities (by changing quantity and quality of sensors, actuators, input/output signals and control algorithms); sca lability of dependability (safety integrity) (by changing a number of redundant channel, tiers, diagnostic and reconfiguration procedures); sca lability of diversity (by changing types, depth and method of diversity selection). (Author)

Research on conceptual design of simplified nuclear safety instrument and control system

International Nuclear Information System (INIS)

Huang Jie

2015-01-01

The Nuclear safety instrument and control system is directly related to the safety of the reactor. So redundant and diversity design is used to ensure the system's security and reliability. This make the traditional safety system large, more cabinets and wiring complexity. To solve these problem, we can adopt new technology to make the design more simple. The simplify conceptual design can make the system less cabinets, less wiring, but high security, strong reliability. (author)

Fatigue check of nuclear safety class 1 reactor coolant pipe

International Nuclear Information System (INIS)

Wang Qing; Fang Yonggang; Chu Qibao; Xu Yu; Li Hailong

2015-01-01

Fatigue and thermal ratcheting analyses of nuclear safety Class 1 reactor coolant pipe in a nuclear power plant were independently carried out in this paper. The software used for calculation is ROCOCO, which is based on RCC-M code. The difference of nuclear safety Class 1 pipe fatigue evaluation between RCC-M code and ASME code was compared. The main aspects of comparison include the calculation scoping of fatigue design, the calculation method of primary plus secondary stress intensity, the elastic-plastic correction coefficient calculation, and the dynamic load combination method etc. By correcting inconsistent algorithm of ASME code within ROCOCO, the fatigue usage factor and thermal ratcheting design margin of 65 mm and 55 mm wall thickness of the pipe were obtained. The results show that the minimum wall thickness of the pipe must exceed 55 mm and the design value of the thermal ratcheting of 55 mm wall thickness reaches 95% of the allowable value. (authors)

Dedication for Safety-Related Fuses used in Class-1E Power System

International Nuclear Information System (INIS)

Hong, Younghee

2014-01-01

The safety-related fuses used in class-1E power system provide overcurrent protection for electrical system and isolate the class 1E circuit from a fault or overload condition. These days, the number of nuclear grade suppliers has been reduced. Accordingly, commercial grade, instead of safety-related, fuses are procured and used in the utilities through the dedication process. Therefore, this paper introduces the commercial grade fuse dedication process/engineering and how to assure the quality requirements with this process and engineering. The fuses used in class-1E power system are to protect overcurrent and to isolate fault. Therefore the fuse for acceptance in order to improve the quality and reliability for commercial grade fuses shall be dedicated. The fuse resistance value may be useful as an indicator of acceptance. The current carrying capacity test can change the fuse performance properties. Therefore these critical characteristics are needed for additional review and analysis with fuse manufactures

75 FR 68416 - Establishment of Class E Airspace; Berryville, AR

Science.gov (United States)

2010-11-08

...-0690; Airspace Docket No. 10-ASW-2] Establishment of Class E Airspace; Berryville, AR AGENCY: Federal... for Berryville, AR, to accommodate Area Navigation (RNAV) Standard Instrument Approach Procedures (SIAP) at Carroll County Airport, Berryville, AR. The FAA is taking this action to enhance the safety...

Application of Safety Instrumented System (SIS) approach in older nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Nasimi, Elnara; Gabbar, Hossam A., E-mail: hossam.gabbar@uoit.ca

2016-05-15

Highlights: • Study Safety Instrumented System (SIS) design for older nuclear power plant. • Apply SIS on Reheater Drains (RD) system. • Apply IEC 61508/61511 to design safety system. • Evaluate risk reduction based on proposed SIS design. - Abstract: In order to remain economically effective and financially profitable, the modern industries have to take their safety culture to a higher level and consider production losses in addition to simple accident prevention techniques. Ideally, compliance with safety requirements start during early design stages, but in some older facilities provisions for Safety Instrumented Systems (SIS) may not have been originally included. In this paper, a case study of a Reheater Drains (RD) system is used to illustrate such an example. Frequent failures of tank level controller lead to transients where the operation of shutting down RD pumps requires operators to manually isolate the quenching water and to close the main steam admission valves. Water in this system is at saturation temperature for the reheater steam side pressure, and any manual operation of the system is highly undesirable due to hazards of working with wet steam at approximately 758 kPa(g) pressure, preheated to 237 °C. Additionally, losses of inventory are highly undesirable as well and challenge other systems in the plant. In this paper, it is suggested that RD system can benefit from installation of an independent SIS system in order to address current challenges. This idea is being explored using IEC 61508 framework for “Functional safety of electrical/electronic/programmable electronic safety-related systems” to provide assurance that the SIS will offer the necessary risk reduction required to achieve required safety for the equipment.

75 FR 37292 - Amendment of Class E Airspace; Cherokee, IA

Science.gov (United States)

2010-06-29

...-0085; Airspace Docket No. 10-ACE-1] Amendment of Class E Airspace; Cherokee, IA AGENCY: Federal... Cherokee, IA. Decommissioning of the Pilot Rock non-directional beacon (NDB) at Cherokee County Regional Airport, Cherokee, IA has made this action necessary to enhance the safety and management of Instrument...

76 FR 75446 - Amendment of Class E Airspace; Mercury, NV

Science.gov (United States)

2011-12-02

...-0894; Airspace Docket No. 11-AWP-14] Amendment of Class E Airspace; Mercury, NV AGENCY: Federal... Mercury, Desert Rock Airport, Mercury, NV. Decommissioning of the Mercury Non-Directional Beacon (NDB) at Mercury, Desert Rock Airport has made this action necessary for the safety and management of Instrument...

76 FR 43576 - Amendment of Class E Airspace; Hannibal, MO

Science.gov (United States)

2011-07-21

...-0046; Airspace Docket No. 11-ACE-1] Amendment of Class E Airspace; Hannibal, MO AGENCY: Federal... Hannibal, MO. Decommissioning of the Hannibal non-directional beacon (NDB) at Hannibal Regional Airport, Hannibal, MO, has made this action necessary to enhance the safety and management of Instrument Flight Rule...

Acceptance Test Procedure for New Pumping Instrumentation and Control Skid ''P''

International Nuclear Information System (INIS)

KOCH, M.R.

2000-01-01

This Test Plan provides a test method to dedicate the leak detection relays used on the new Pumping Instrumentation and Control (PIC) skids. The new skids are fabricated on-site. The leak detection system is a safety class system per the Authorization Basis

Acceptance Test Procedure for New Pumping Instrumentation and Control Skid Q

International Nuclear Information System (INIS)

KOCH, M.R.

2000-01-01

This Test Plan provides a test method to dedicate the leak detection relays used on the new Pumping Instrumentation and Control (PIC) skids. The new skids are fabricated on-site. The leak detection system is a safety class system per the Authorization Basis

Instrumentation and control systems important to safety in nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

This Safety Guide was prepared under the IAEA programme for establishing safety standards for nuclear power plants. It supplements Safety Standards Series No. NS-R-1: Safety of Nuclear Power Plants: Design (the Requirements for Design), which establishes the design requirements for ensuring the safety of nuclear power plants. This Safety Guide describes how the requirements should be met for instrumentation and control (I and C) systems important to safety. This publication is a revision and combination of two previous Safety Guides: Safety Series Nos 50-SG-D3 and 50-SG-D8, which are superseded by this new Safety Guide. The revision takes account of developments in I and C systems important to safety since the earlier Safety Guides were published in 1980 and 1984, respectively. The objective of this Safety Guide is to provide guidance on the design of I and C systems important to safety in nuclear power plants, including all I and C components, from the sensors allocated to the mechanical systems to the actuated equipment, operator interfaces and auxiliary equipment. This Safety Guide deals mainly with design requirements for those I and C systems that are important to safety. It expands on paragraphs of Ref in the area of I and C systems important to safety. This publication is intended for use primarily by designers of nuclear power plants and also by owners and/or operators and regulators of nuclear power plants. This Safety Guide provides general guidance on I and C systems important to safety which is broadly applicable to many nuclear power plants. More detailed requirements and limitations for safe operation specific to a particular plant type should be established as part of the design process. The present guidance is focused on the design principles for systems important to safety that warrant particular attention, and should be applied to both the design of new I and C systems and the modernization of existing systems. Guidance is provided on how design

Requirements and analysis of electromagnetic compatibility of safety-related instrumentation and control system in nuclear power plants

International Nuclear Information System (INIS)

Liu Sujuan

2002-01-01

The state-of-the-art instrumentation and control system and the influence of their application to the electromagnetic compatibility is analyzed. Based on the present situation of nuclear safety in China and relevant experiences from other countries, the author tries to probe into the requirements and test methods about how safety-related instrument and control system to accommodate electromagnetic interference, radio-frequency interference and power surges in the environments of nuclear power plant so as to develop Chinese safety standards

76 FR 73501 - Amendment of Class E Airspace; Carroll, IA

Science.gov (United States)

2011-11-29

...-0845; Airspace Docket No. 11-ACE-19] Amendment of Class E Airspace; Carroll, IA AGENCY: Federal... Carroll, IA. Decommissioning of the Carroll non-directional beacon (NDB) at Arthur N. Neu Airport, Carroll, IA, has made this action necessary to enhance the safety and management of Instrument Flight Rule...

Administering Spatial and Cognitive Instruments In-class and On-line: Are These Equivalent?

Science.gov (United States)

Williamson, Kenneth C.; Williamson, Vickie M.; Hinze, Scott R.

2017-02-01

Standardized, well-established paper-and-pencil tests, which measure spatial abilities or which measure reasoning abilities, have long been found to be predictive of success in the STEM (science, technology, engineering, and mathematics) fields. Instructors can use these tests for prediction of success and to inform instruction. A comparative administration of spatial visualization and cognitive reasoning tests, between in-class (proctored paper and pencil) and on-line (unproctored Internet) ( N = 457), was used to investigate and to determine whether the differing instrument formats yielded equal measures of spatial ability and reasoning ability in large first-semester general chemistry sections. Although some gender differences were found, findings suggest that some differences across administration formats, but that on-line administration had similar properties of predicting chemistry performance as the in-class version. Therefore, on-line administration is a viable option for instructors to consider especially when dealing with large classes.

Design of Instrumentation and Control Systems for Nuclear Power Plants. Specific Safety Guide

International Nuclear Information System (INIS)

2016-01-01

This publication is a revision and combination of two Safety Guides, IAEA Safety Standards Series No. NS-G-1.1 and No. NS-G-1.3. The revision takes into account developments in instrumentation and control (I&C) systems since the publication of the earlier Safety Guides. The main changes relate to the continuing development of computer applications and the evolution of the methods necessary for their safe, secure and practical use. In addition, account is taken of developments in human factors engineering and the need for computer security. This Safety Guide references and takes into account other IAEA Safety Standards and Nuclear Security Series publications that provide guidance relating to I&C design

Validity of instruments to assess students' travel and pedestrian safety

Directory of Open Access Journals (Sweden)

Baranowski Tom

2010-05-01

Full Text Available Abstract Background Safe Routes to School (SRTS programs are designed to make walking and bicycling to school safe and accessible for children. Despite their growing popularity, few validated measures exist for assessing important outcomes such as type of student transport or pedestrian safety behaviors. This research validated the SRTS school travel survey and a pedestrian safety behavior checklist. Methods Fourth grade students completed a brief written survey on how they got to school that day with set responses. Test-retest reliability was obtained 3-4 hours apart. Convergent validity of the SRTS travel survey was assessed by comparison to parents' report. For the measure of pedestrian safety behavior, 10 research assistants observed 29 students at a school intersection for completion of 8 selected pedestrian safety behaviors. Reliability was determined in two ways: correlations between the research assistants' ratings to that of the Principal Investigator (PI and intraclass correlations (ICC across research assistant ratings. Results The SRTS travel survey had high test-retest reliability (κ = 0.97, n = 96, p Conclusions These validated instruments can be used to assess SRTS programs. The pedestrian safety behavior checklist may benefit from further formative work.

Seismic and environmental qualification of class IE equipment manufactured in Spain

International Nuclear Information System (INIS)

Gerini, P.; Lumbreras, A.; Naredo, F.

1978-01-01

Nuclear power plant instrumentation and control design is affected by several factors such as various plant operating conditions, transient response capability, safety requirements and changes in IEEE standards. Recent upgraded IEEE standards that call for Qualification of all Safety related I anc C equipment, namely IEEE 323 (Qualifying Class IE Electric Equipment for nuclear power generating stations) and its daughter Standard IEEE 344 (Recommended Practices for Seismic Qualification of Class IE Equipment for nuclear power generating stations) have been endorsed by the United States Nuclear Regulatory Commission through the issuance of corresponding Regulatory Guides. The author describes the Qualification requirements applicable to the Class IE I and C Components made in Spain for the different vintages of plants, and the programs implemented or plans established by Westinghouse to fulfill those requirements. (author)

Procedure for getting safety classed concrete structures approved by Finnish Radiation and Nuclear Safety Authority

International Nuclear Information System (INIS)

Halme, Ville-Juhani

2015-01-01

Posiva is preparing geological final disposal in the Finnish bedrock in Olkiluoto, Eurajoki. The final disposal facility includes encapsulation plant and underground repository. Most of the main civil structures are concrete structures. STUK is the supervising authority in civil structures. The National Building Code of Finland and STUK's Regulatory Guide on nuclear safety (YVL) are the most important instructions when constructing concrete structures into nuclear installation. Posiva has classified concrete structures in two classes according STUK's YVL-guidance: EYT (non-nuclear) and Safety Class 3 (SC 3, nuclear safety significance). When building SC 3 concrete structures, specific protocol must be followed. Protocol includes planned routines for design, construction, supervision, quality control (QC) and quality assurance (QA) activities. Documents relating concrete structures must be approved by Posiva and STUK before construction work. After structures have been designed and actual building is ongoing, there are two main steps. Before concreting, readiness inspection for concreting must be arranged. Readiness inspection will be arranged according to a specific plan and the date must be informed to STUK. After establishing readiness for concreting, casting work can begin. Once concrete structures are done, inspected and approved, final documentation according to a quality control plan will be reviewed by Posiva. After Posiva's approval, final documentation will be sent for STUK's approval. In the end STUK will give the permission for commissioning of the concrete structures after approved commissioning inspection. The document is made up of an abstract and a poster

The qualification of electrical components and instrumentations relevant to safety

CERN Document Server

Zambardi, F

1989-01-01

Systems and components relevant to safety of nuclear power plants must maintain their functional integrity in order to assure accident prevention and mitigation. Redundancy is utilized against random failures, nevertheless care must be taken to avoid common failures in redundant components. Main sources of degradation and common cause failures consist in the aging effects and in the changes of environmental conditions which occur during the plant life and the postulated accidents. These causes of degradation are expected to be especially significant for instrumentation and electrical equipment, which can have a primary role in safety systems. The qualification is the methodology by which component safety requirements can be met against the above mentioned causes of degradation. In this report the connection between the possible, plant conditions and the resulting degradation effects on components is preliminarily addressed. A general characterization of the qualification is then presented. Basis, methods and ...

75 FR 13668 - Amendment of Class E Airspace; Cedar Rapids, IA

Science.gov (United States)

2010-03-23

...-0916; Airspace Docket No. 09-ACE-12] Amendment of Class E Airspace; Cedar Rapids, IA AGENCY: Federal... Cedar Rapids, IA, to accommodate Area Navigation (RNAV) Standard Instrument Approach Procedures (SIAPs) at The Eastern Iowa Airport, Cedar Rapids, IA. The FAA is taking this action to enhance the safety...

76 FR 22009 - Amendment of Class E Airspace; Terre Haute, IN

Science.gov (United States)

2011-04-20

...-1034; Airspace Docket No. 10-AGL-22] Amendment of Class E Airspace; Terre Haute, IN AGENCY: Federal... Terre Haute, IN, to accommodate new Area Navigation (RNAV) Standard Instrument Approach Procedures at Union Hospital Heliport, Terre Haute, IN. The FAA is taking this action to enhance the safety and...

77 FR 61248 - Establishment of Class E Airspace; Deer Lodge, MT

Science.gov (United States)

2012-10-09

...-0379; Airspace Docket No. 12-ANM-7 Establishment of Class E Airspace; Deer Lodge, MT AGENCY: Federal... at Deer Lodge-City- County Airport, Deer Lodge, MT. Controlled airspace is necessary to accommodate... procedures at Deer Lodge-City-County Airport. This improves the safety and management of Instrument Flight...

Safety Assessment of Two Hybrid Instrumentation Techniques in a Dental Student Endodontic Clinic: A Retrospective Study.

Science.gov (United States)

Coelho, Marcelo Santos; Card, Steven John; Tawil, Peter Zahi

2017-03-01

The aim of this study was to retrospectively assess the safety potential of a hybrid technique combining nickel-titanium (NiTi) reciprocating and rotary instruments by third- and fourth-year dental students in the predoctoral endodontics clinic at one U.S. dental school. For the study, 3,194 root canal treatments performed by 317 dental students from 2012 through 2015 were evaluated for incidence of ledge creation and instrument separation. The hybrid reciprocating and rotary technique (RRT) consisted of a glide path creation with stainless steel hand files up to size 15/02, a crown down preparation with a NiTi reciprocating instrument, and an apical preparation with NiTi rotary instruments. The control was a traditional rotary and hand technique (RHT) that consisted of the same glide path procedure followed by a crown down preparation with NiTi rotary instruments and an apical preparation with NiTi hand instruments. The results showed that the RHT technique presented a rate of ledge creation of 1.4% per root and the RRT technique was 0.5% per root (protary technique for root canal instrumentation by these dental students provided good safety. This hybrid technique offered a low rate of ledge creation along with no NiTi instrument separation.

Probabilistic safety assessment for instrumentation and control systems in nuclear power plants: an overview

International Nuclear Information System (INIS)

Lu, Lixuan; Jiang, Jin

2004-01-01

Deregulation in the electricity market has resulted in a number of challenges in the nuclear power industry. Nuclear power plants must find innovative ways to remain competitive by reducing operating costs without jeopardizing safety. Instrumentation and Control (I and C) systems not only play important roles in plant operation, but also in reducing the cost of power generation while maintaining and/or enhancing safety. Therefore, it is extremely important that I and C systems are managed efficiently and economically. With the increasing use of digital technologies, new methods are needed to solve problems associated with various aspects of digital I and C systems. Probabilistic Safety Assessment (PSA) has proved to be an effective method for safety analysis and risk-based decisions, even though challenges are still present. This paper provides an overview of PSA applications in three areas of digital I and C systems in nuclear power plants. These areas are Graded Quality Assurance, Surveillance Testing, and Instrumentation and Control System Design. In addition, PSA application in the regulation of nuclear power plants that adopt digital I and C systems is also investigated. (author)

Safety concepts and their implications with respect to systems, instrumentation (automatic) control and hardware

International Nuclear Information System (INIS)

Paziaud, A.; Walther, M.

1982-01-01

This overview of instrumentation and control in the French Nuclear Power Plants sets out the importance of safety requirements. As a matter of fact, the amount of equipment increases proportionally to the increase in safety requirements, resulting in higher costs in spite of the decrease in the prices of each component owing to the advance in electronics. However the improved reliability should improve the plant capacity factor and, as a consequence, improve both the power output and the safety which is often endangered by minor failures starting severe accidents. (orig.)

Safety and function of a new clinical intracerebral microinjection instrument for stem cells and therapeutics examined in the Göttingen minipig

DEFF Research Database (Denmark)

Bjarkam, Carsten R; GLUD, AN; Margolin, Lee

2010-01-01

Safety and function of a new clinical intracerebral microinjection instrument for stem cells and therapeutics examined in the Göttingen minipig......Safety and function of a new clinical intracerebral microinjection instrument for stem cells and therapeutics examined in the Göttingen minipig...

Development of the safety PLC for plant protection system

Energy Technology Data Exchange (ETDEWEB)

Kim, Chang Hwoi; Lee, Dong Young [Korea Atomic Energy Research Institute, Taejeon (Korea, Republic of)

2005-11-15

The safety PLC (POSAFE-Q) is developing in the Korea Nuclear Instrumentation and Control System (KNICS) R and D project. The PLC satisfies Safety Class 1E, Quality Class 1, and Seismic Category I. The software such as RTOS and firmware are developed according to safety critical software life cycle. Especially, the formal method is applied to design SRS (Software Requirement Spec.) and SDS (Software Design Specification.) for error-free. The developed software according to software life cycle is verified by independent software V and V team. The overall response time from an input to the outputs shall be 50ms or less. The prototype for the POSAFE-Q was developed and functional testing and equipment qualification tests have been underway.

Emergency Diesel: Safety-related instrumentation and control with programmable logic controllers

International Nuclear Information System (INIS)

Breidenich, G.; Luedtke, M.

2004-01-01

This report presents a new concept for the design of emergency diesel equipment protection circuits as a part of the safety related instrumentation in the nuclear power plant Biblis, units A and B. The concept was implemented with state of the art SIMATIC S7/316 programmable logic controllers (PLCs) and can be adapted to any system with high availability requirements (e.g. power plant turbines, aircraft engines, mining pumps etc). (orig.)

Surveillance of instrumentation channels at nuclear power plants

International Nuclear Information System (INIS)

Thie, J.A.

1989-06-01

Surveillance activities at nuclear plants, involving-calibrations, functional tests, and simple checks, have many associated problems. These problems are of the following four types: administrative, equipment, human, and systemic. An extensive search of the literature has led to 63 generic classes of problems falling within these types and involving instrumentation department activities. The classification system is that which writers of incidents are essentially using, based on historical traditions, in naming their problems' causes. An interesting finding in the search was the strong correlation of this project to many aspects of industrial safety; technology transfer opportunities from the latter are identified. A survey of plant instrumentation experts was conducted to obtain a ranking of the most important problems. Classes of solutions to these problems are listed and discussed. Outlined is a possible methodology of matching these solutions to problems. Finally applications of this study are listed, and include extensions to training, operations, and maintenance departments of power plants. Appendices give several general examples for each problem class and many specific suggestions from experts on addressing the problems felt to be more important. 15 refs., 2 figs., 6 tabs

The qualification of electrical components and instrumentations relevant to safety

International Nuclear Information System (INIS)

Zambardi, F.

1989-03-01

Systems and components relevant to safety of nuclear power plants must maintain their functional integrity in order to assure accident prevention and mitigation. Redundancy is utilized against random failures, nevertheless care must be taken to avoid common failures in redundant components. Main sources of degradation and common cause failures consist in the aging effects and in the changes of environmental conditions which occur during the plant life and the postulated accidents. These causes of degradation are expected to be especially significant for instrumentation and electrical equipment, which can have a primary role in safety systems. The qualification is the methodology by which component safety requirements can be met against the above mentioned causes of degradation. In this report the connection between the possible, plant conditions and the resulting degradation effects on components is preliminarily addressed. A general characterization of the qualification is then presented. Basis, methods and peculiar aspects are discussed and the qualification by testing is taken into special account. Technical and organizational aspects related to a plant qualification program are also focused. The report ends with a look to the most significant research and development activities. (author)

Development of FPGA-based safety-related instrumentation and control systems

Energy Technology Data Exchange (ETDEWEB)

Oda, N.; Tanaka, A.; Izumi, M.; Tarumi, T.; Sato, T. [Toshiba Corporation, Isogo Nuclear Engineering Center, Yokohama (Japan)

2004-07-01

Toshiba has developed systems which perform signal processing by field programmable gate arrays (FPGA) for safety-related instrumentation and control systems. FPGA is a device which consists only of defined digital circuit: hardware, which performs defined processing. FPGA-based system solves issues existing both in the conventional systems operated by analog circuits (analog-based system) and the systems operated by central processing units (CPU-based system). The advantages of applying FPGA are to keep the long-life supply of products, improving testability (verification), and to reduce the drift which may occur in analog-based system. Considering application to safety-related systems, nonvolatile and non rewritable FPGA which is impossible to be changed after once manufactured has been adopted in Toshiba FPGA-based system. The systems which Toshiba developed this time are Power range Monitor (PRM) and Trip Module (TM). These systems are compatible with the conventional analog-based systems and the CPU-based systems. Therefore, requested cost for upgrading will be minimized. Toshiba is planning to expand application of FPGA-based technology by adopting this development method to the other safety-related systems from now on. (authors)

Functional verification of a safety class controller for NPPs using a UVM register Model

Energy Technology Data Exchange (ETDEWEB)

Kim, Kyu Chull [Dept. of Applied Computer Engineering, Dankook University, Cheonan (Korea, Republic of)

2014-06-15

A highly reliable safety class controller for NPPs (Nuclear Power Plants) is mandatory as even a minor malfunction can lead to disastrous consequences for people, the environment or the facility. In order to enhance the reliability of a safety class digital controller for NPPs, we employed a diversity approach, in which a PLC-type controller and a PLD-type controller are to be operated in parallel. We built and used structured testbenches based on the classes supported by UVM for functional verification of the PLD-type controller designed for NPPs. We incorporated a UVM register model into the testbenches in order to increase the controllability and the observability of the DUT(Device Under Test). With the increased testability, we could easily verify the datapaths between I/O ports and the register sets of the DUT, otherwise we had to perform black box tests for the datapaths, which is very cumbersome and time consuming. We were also able to perform constrained random verification very easily and systematically. From the study, we confirmed the various advantages of using the UVM register model in verification such as scalability, reusability and interoperability, and set some design guidelines for verification of the NPP controllers.

Safety integrity requirements for computer based I ampersand C systems

International Nuclear Information System (INIS)

Thuy, N.N.Q.; Ficheux-Vapne, F.

1997-01-01

In order to take into account increasingly demanding functional requirements, many instrumentation and control (I ampersand C) systems in nuclear power plants are implemented with computers. In order to ensure the required safety integrity of such equipment, i.e., to ensure that they satisfactorily perform the required safety functions under all stated conditions and within stated periods of time, requirements applicable to these equipment and to their life cycle need to be expressed and followed. On the other hand, the experience of the last years has led EDF (Electricite de France) and its partners to consider three classes of systems and equipment, according to their importance to safety. In the EPR project (European Pressurized water Reactor), these classes are labeled E1A, E1B and E2. The objective of this paper is to present the outline of the work currently done in the framework of the ETC-I (EPR Technical Code for I ampersand C) regarding safety integrity requirements applicable to each of the three classes. 4 refs., 2 figs

The 5th questionnaire report of safety control on instrument in nuclear medicine laboratory

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-08-01

The questionnaire was done every three years from 1986 for the ultimate purpose of safe medical examinations and this 5th one was performed in May, 1998 for the period of April, 1995-March, 1998. Subjects were 1,258 nuclear medicine facilities and answers were obtained in 81.6%. Questionnaire concerned the personnel involved in nuclear medical examinations, instruments, accidents occurred, matters possibly leading to accident, improvement in safety control, serious trouble and breakage of the instrument, request for the instrument manufacturers and so on. Summaries were: numbers of medical radiology technicians were increased, in vitro tests were decreased, SPECT instruments came into wide use, in accident and improvement cases, examination beds were arousing much interest, concerns to examine were further required, communication with the manufacturers was insufficient, and problems for Y2K were pointed out to be resolved. (K.H.)

Safety evaluation for instrumentation and control system upgrading project of Malaysian TRIGA MARK II PUSPATI Research reactor

International Nuclear Information System (INIS)

Ridha Roslan; Nik Mohd Faiz Khairuddin

2013-01-01

Full-text: Malaysian TRIGA MARK II research reactor has been in safe operation since its first criticality in 1982. The reactor is licensed to be operated by Malaysian Nuclear Agency to perform training and research development related activities. Due to its extensive operation since last three decades, the option of modifications for safety and safety-related item and component become a necessary to replace the outdated equipment to a stat-of-art, reliable technologies. This paper will present the current regulatory activities performed by Atomic Energy Licensing Board (AELB) to ensure the upgrading of analogue to digital instrumentation and control system is implemented in safe manner. The review activity includes documentation review, manufacturer quality audit and on-site inspection for commissioning. The review performed by AELB is based on The International Atomic Energy Agency (IAEA) Safety Requirements NS-R-4, entitled Safety of Research Reactors. During this endeavour, AELB seeks technical cooperation from Korea Institute of Nuclear Safety (KINS), the nuclear experts organization of the country of origin of the instrumentation and control technology. The regulatory activity is still on-going and is expected to be completed by issuance of Authorization for Restart on December 2013. (author)

Modernization of Safety and Control Instrumentation of the IEA-R1 Research Reactor

Energy Technology Data Exchange (ETDEWEB)

De Carvalho, P.V., E-mail: paulov@ien.gov.br [Institute of Nuclear Engineering (IEN), National Nuclear Energy Commission (CNEN), Rio de Janeiro (Brazil)

2014-08-15

The research reactor IEA-R1 located in the Institute of Energy and Nuclear Research (IPEN), São Paulo, Brazil, obtained its first criticality on 16 September 1957 and since then has served the scientific and medical community in the performance of experiments in applied nuclear physics, as well as the provision of radioisotopes for production of radiopharmaceuticals. The reactor produces radioisotopes {sup 82}Br and {sup 41}Ar for special processes in industrial inspection and {sup 192}Ir and {sup 198}Au as sources of radiation used in brachytherapy, {sup 153}Sm for pain relief in patients with bone metastasis, and calibrated sources of {sup 133}Ba, {sup 137}Cs, {sup 57}Co, {sup 60}Co, {sup 241}Am and {sup 152}Eu used in medical clinics and hospitals practicing nuclear medicine and research laboratories. Services are offered in regular non-destructive testing by neutron radiography, neutron irradiation of silicon for phosphorous doping and other various irradiations with neutrons. The reactor is responsible for producing approximately 70% of radiopharmaceutical {sup 131}I used in Brazil, which saves about US$ 800 000 annually for the country. After more than 50 years of use, most of its equipment and systems have been modernized, and recently the reactor power was increased to 5 MW in order to enhance radioisotope production capability. However, the control room and nuclear instrumentation system used for reactor safety have operated more than 30 years and require constant maintenance. Many equipment and electronic components are obsolete, and replacements are not available in the market. The modernization of the nuclear safety and control instrumentation systems of IEA-R1 is being carried out with consideration for the internationally recognized criteria for safety and reliable reactor operations and the latest developments in nuclear electronic technology. The project for the new reactor instrumentation system specifies three wide range neutron monitoring

Instrumental and statistical methods for the comparison of class evidence

Science.gov (United States)

Liszewski, Elisa Anne

Trace evidence is a major field within forensic science. Association of trace evidence samples can be problematic due to sample heterogeneity and a lack of quantitative criteria for comparing spectra or chromatograms. The aim of this study is to evaluate different types of instrumentation for their ability to discriminate among samples of various types of trace evidence. Chemometric analysis, including techniques such as Agglomerative Hierarchical Clustering, Principal Components Analysis, and Discriminant Analysis, was employed to evaluate instrumental data. First, automotive clear coats were analyzed by using microspectrophotometry to collect UV absorption data. In total, 71 samples were analyzed with classification accuracy of 91.61%. An external validation was performed, resulting in a prediction accuracy of 81.11%. Next, fiber dyes were analyzed using UV-Visible microspectrophotometry. While several physical characteristics of cotton fiber can be identified and compared, fiber color is considered to be an excellent source of variation, and thus was examined in this study. Twelve dyes were employed, some being visually indistinguishable. Several different analyses and comparisons were done, including an inter-laboratory comparison and external validations. Lastly, common plastic samples and other polymers were analyzed using pyrolysis-gas chromatography/mass spectrometry, and their pyrolysis products were then analyzed using multivariate statistics. The classification accuracy varied dependent upon the number of classes chosen, but the plastics were grouped based on composition. The polymers were used as an external validation and misclassifications occurred with chlorinated samples all being placed into the category containing PVC.

Reliability analysis and computation of computer-based safety instrumentation and control used in German nuclear power plant. Final report

International Nuclear Information System (INIS)

Ding, Yongjian; Krause, Ulrich; Gu, Chunlei

2014-01-01

The trend of technological advancement in the field of safety instrumentation and control (I and C) leads to increasingly frequent use of computer-based (digital) control systems which consisting of distributed, connected bus communications computers and their functionalities are freely programmable by qualified software. The advantages of the new I and C system over the old I and C system with hard-wired technology are e.g. in the higher flexibility, cost-effective procurement of spare parts, higher hardware reliability (through higher integration density, intelligent self-monitoring mechanisms, etc.). On the other hand, skeptics see the new technology with the computer-based I and C a higher potential by influences of common cause failures (CCF), and the easier manipulation by sabotage (IT Security). In this joint research project funded by the Federal Ministry for Economical Affaires and Energy (BMWi) (2011-2014, FJZ 1501405) the Otto-von-Guericke-University Magdeburg and Magdeburg-Stendal University of Applied Sciences are therefore trying to develop suitable methods for the demonstration of the reliability of the new instrumentation and control systems with the focus on the investigation of CCF. This expertise of both houses shall be extended to this area and a scientific contribution to the sound reliability judgments of the digital safety I and C in domestic and foreign nuclear power plants. First, the state of science and technology will be worked out through the study of national and international standards in the field of functional safety of electrical and I and C systems and accompanying literature. On the basis of the existing nuclear Standards the deterministic requirements on the structure of the new digital I and C system will be determined. The possible methods of reliability modeling will be analyzed and compared. A suitable method called multi class binomial failure rate (MCFBR) which was successfully used in safety valve applications will be

Development of Safety Grade PLC (POSAFE-Q) and Performance Test Results

International Nuclear Information System (INIS)

Kim, Chang Hwoi; Park, Won Man; Choi, Jong Gyun; Lee, Dong Young; No, Young Hun; Song, Seung Hwan

2006-01-01

The safety grade PLC (POSAFE-Q) is being developed in the Korea Nuclear Instrumentation and Control System (KNICS) R and D project. The PLC satisfies Safety Class 1E, Quality Class 1, and Seismic Category I. The software such as the RTOS and firmware are being developed according to the safety critical software life cycle. Especially, the formal method is applied to design the SRS (Software Requirement Spec.) and the SDS (Software Design Specification.) to be error-free. The POSAFE-Q has several modules such as processor module, input and output modules, communication modules, redundant processor module, redundant power modules, etc,. To verify the function and performance, several tests such as CT, IT and ST were performed. And also, the equipment qualification test for environment, EMI and EMC, and seismic ware performed. All tests are satisfied with the requirements and specification for safety grade PLC, and the criteria for safety system in nuclear power plants

Development of Safety Grade PLC (POSAFE-Q) and Performance Test Results

Energy Technology Data Exchange (ETDEWEB)

Kim, Chang Hwoi; Park, Won Man; Choi, Jong Gyun; Lee, Dong Young [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); No, Young Hun; Song, Seung Hwan [POSCON, Seoul (Korea, Republic of)

2006-07-01

The safety grade PLC (POSAFE-Q) is being developed in the Korea Nuclear Instrumentation and Control System (KNICS) R and D project. The PLC satisfies Safety Class 1E, Quality Class 1, and Seismic Category I. The software such as the RTOS and firmware are being developed according to the safety critical software life cycle. Especially, the formal method is applied to design the SRS (Software Requirement Spec.) and the SDS (Software Design Specification.) to be error-free. The POSAFE-Q has several modules such as processor module, input and output modules, communication modules, redundant processor module, redundant power modules, etc,. To verify the function and performance, several tests such as CT, IT and ST were performed. And also, the equipment qualification test for environment, EMI and EMC, and seismic ware performed. All tests are satisfied with the requirements and specification for safety grade PLC, and the criteria for safety system in nuclear power plants.

A toolbox for safety instrumented system evaluation based on improved continuous-time Markov chain

Science.gov (United States)

Wardana, Awang N. I.; Kurniady, Rahman; Pambudi, Galih; Purnama, Jaka; Suryopratomo, Kutut

2017-08-01

Safety instrumented system (SIS) is designed to restore a plant into a safe condition when pre-hazardous event is occur. It has a vital role especially in process industries. A SIS shall be meet with safety requirement specifications. To confirm it, SIS shall be evaluated. Typically, the evaluation is calculated by hand. This paper presents a toolbox for SIS evaluation. It is developed based on improved continuous-time Markov chain. The toolbox supports to detailed approach of evaluation. This paper also illustrates an industrial application of the toolbox to evaluate arch burner safety system of primary reformer. The results of the case study demonstrates that the toolbox can be used to evaluate industrial SIS in detail and to plan the maintenance strategy.

New instruments for soil physics class: Improving the laboratory and field seminars

Science.gov (United States)

Klipa, Vladimir; Jankovec, Jakub; Snehota, Michal

2014-05-01

Teaching soil science and soil physics is an important part of the curriculum of many programs with focus on technical and natural sciences. Courses of soil science and namely soil physics have a long tradition at the faculty of Civil Engineering of the Czech Technical University in Prague. Students receive the theoretical foundations about soil classification, soil physics, soil chemistry and soil hydraulic characteristics in the course. In practical seminars students perform measurements of physical, hydraulic and chemical characteristics of soils, thus a comprehensive survey of soil is done in the given site. So far, students had the opportunity to use old, manually operated instrumentation. The project aims to improve the attractiveness of soil physics course and to extend the practical skills of students by introducing new tasks and by involving modern automated equipment. New instruments were purchased with the support of the Ministry of Education, Youth and Sports of the Czech Republic under the project FRVS No. 1162/2013 G1. Specifically, two tensiometers T8 with multi-functional handheld read-out unit (UMS, GmbH) and manual Mini Disk Infiltrometer (Decagon Devices, Inc.) were purchased and incorporated into the course. In addition, newly designed MultiDisk the automated mini disk Infiltrometer (CTU in Prague) and combined temperature and soil moisture TDT sensor TMS 2 (TOMST®, s.r.o.), were made freely available for soil physics classes and included into the courses. Online tutorials and instructional videos were developed. Detailed multimedia teaching materials were introduced so that students are able to work more independently. Students will practice operating the digital tensiometer T8 with integrated temperature sensor and manual Mini Disk Infiltrometer (diameter disk: 4.4 cm, suction range: 0.5 to 7.0 cm of suction) and MultiDisk the automated mini disk Infiltrometer (see Klipa et al., EGU2014-7230) and combined temperature and soil moisture TDT

Autonomous optical navigation using nanosatellite-class instruments: a Mars approach case study

Science.gov (United States)

Enright, John; Jovanovic, Ilija; Kazemi, Laila; Zhang, Harry; Dzamba, Tom

2018-02-01

This paper examines the effectiveness of small star trackers for orbital estimation. Autonomous optical navigation has been used for some time to provide local estimates of orbital parameters during close approach to celestial bodies. These techniques have been used extensively on spacecraft dating back to the Voyager missions, but often rely on long exposures and large instrument apertures. Using a hyperbolic Mars approach as a reference mission, we present an EKF-based navigation filter suitable for nanosatellite missions. Observations of Mars and its moons allow the estimator to correct initial errors in both position and velocity. Our results show that nanosatellite-class star trackers can produce good quality navigation solutions with low position (<300 {m}) and velocity (<0.15 {m/s}) errors as the spacecraft approaches periapse.

Instrumentation for mine safety: fire and smoke problems and solutions

International Nuclear Information System (INIS)

Stevens, R.B.

1982-01-01

Underground fires continue to be one of the most serious hazards to life and property in the mining industry. Although underground mines are analogous to high-rise buildings where persons are isolated from immediate escape or rescue, application of technology to locate and control fire hazards while still in their controllable state is slow to be implemented in underground mines. This paper describes several USBM (Bureau of Mines) safety programs which included in-mine testing with mine fire and smoke sensors, telemetry and instrumentation to develop recommendations for improving mine fire safety. It is hoped that the technology developed during these programs can be added to other programs to provide the mining industry with the necessary fire safety facts. By recognizing fire potentials and being provided with cost-effective, proven components that will perform reliably under the poor environmental conditions of mining, mine operators can provide protection for their working life and property equal to that which they provide for themselves and their families at home. The basis of this report is two USBM programs for fire protection in metal and nonmetal mines and one coal program. The data was collected beginning in May 1974 and continuing through the present with underground tests of a South African fire system installed at Magma Mine in Superior, Arizona, and a computer-assisted, experimental system at Peabody Coal Mine in Pawnee, Illinois

Probable variations of a passive safety containment for a 1700 MWe class PWR with passive safety systems

International Nuclear Information System (INIS)

Sato, Takashi; Fujiki, Yasunobu; Oikawa, Hirohide; Ofstun, Richard P.

2009-01-01

The paper presents probable variations of a passive safety containment for a PWR. The passive safety containment is named Mark P containment tentatively. It is a pressure suppression type containment for a large scale PWR with a BWR type passive containment cooling system (PCCS). More than 3-day grace period can be achieved even for a 1700 MWe class large scale PWR owing to the PCCS. The containment is a reinforced concrete containment vessel (RCCV). The design pressure of the RCCV can be low owing to the suppression pool (S/P) and no prestressed tendon is necessary. It is a single barrier CV that can withstand a large airplane crash by itself. This simple configuration results in good economy and short construction term. The BWR type passive safety systems also include the Passive Cooling and Depressurization System (PCDS). The PCDS has 3-day grace period for the SBO induced by a giant earthquake and can practically eliminate the residual risk of a giant earthquake beyond the design basis earthquake of Ss. It also has a safety function to automatically depressurize the primary system at accidents such as SGTR and eliminate the need for operator actions. It is a large 1700 MWe passive safety PWR that has more than 3-day grace period for extremely severe natural disasters including a giant earthquake, a mega hurricane, tsunami and so on; no containment failure at a SA establishing a no evacuation plant; protection for a large airplane crash with the RCCV single barrier; good economy and short construction term. (author)

JACoW Safety instrumented systems and the AWAKE plasma control as a use case

CERN Document Server

Blanco Viñuela, Enrique; Fernández Adiego, Borja; Speroni, Roberto

2018-01-01

Safety is likely the most critical concern in many process industries, yet there is a general uncertainty on the proper engineering to reduce the risks and ensure the safety of persons or material at the same time as providing the process control system. Some of the reasons for this misperception are unclear requirements, lack of functional safety engineering knowledge or incorrect protection functionalities attributed to the BPCS (Basic Process Control System). Occasionally the control engineers are not aware of the hazards inherent to an industrial process and this causes an incorrect design of the overall controls. This paper illustrates the engineering of the SIS (Safety Instrumented System) and the BPCS of the plasma vapour controls of the AWAKE R&D; project, the first proton-driven plasma wakefield acceleration experiment in the world. The controls design and implementation refers to the IEC61511/ISA84 standard, including technological choices, design, operation and maintenance. Finally, the publica...

Prevalence Estimation and Validation of New Instruments in Psychiatric Research: An Application of Latent Class Analysis and Sensitivity Analysis

Science.gov (United States)

Pence, Brian Wells; Miller, William C.; Gaynes, Bradley N.

2009-01-01

Prevalence and validation studies rely on imperfect reference standard (RS) diagnostic instruments that can bias prevalence and test characteristic estimates. The authors illustrate 2 methods to account for RS misclassification. Latent class analysis (LCA) combines information from multiple imperfect measures of an unmeasurable latent condition to…

Seismic analysis of safety class 1 incinerator glovebox in building 232-Z 200 W Area

International Nuclear Information System (INIS)

Ocoma, E.C.

1994-09-01

This report documents the seismic evaluation for the existing safety class 1 incinerator glovebox in 232Z Building. The glovebox is no longer in use and most of the internal mechanical equipment have been removed. However, the insulation firebricks are still in the glovebox for proper disposal

Proof-testing strategies induced by dangerous detected failures of safety-instrumented systems

International Nuclear Information System (INIS)

Liu, Yiliu; Rausand, Marvin

2016-01-01

Some dangerous failures of safety-instrumented systems (SISs) are detected almost immediately by diagnostic self-testing as dangerous detected (DD) failures, whereas other dangerous failures can only be detected by proof-testing, and are therefore called dangerous undetected (DU) failures. Some items may have a DU- and a DD-failure at the same time. After the repair of a DD-failure is completed, the maintenance team has two options: to perform an insert proof test for DU-failure or not. If an insert proof test is performed, it is necessary to decide whether the next scheduled proof test should be postponed or performed at the scheduled time. This paper analyzes the effects of different testing strategies on the safety performance of a single channel of a SIS. The safety performance is analyzed by Petri nets and by approximation formulas and the results obtained by the two approaches are compared. It is shown that insert testing improves the safety performance of the channel, but the feasibility and cost of the strategy may be a hindrance to recommend insert testing. - Highlights: • Identify the tests induced by detected failures. • Model the testing strategies following DD-failures. • Propose analytical formulas for effects of strategies. • Simulate and verify the proposed models.

RBMK nuclear reactors: Proposals for instrumentation and control improvements to enhanced safety and availability. IEC technical report of type 3. Working material

International Nuclear Information System (INIS)

1995-01-01

The present material presents a CD+V draft report ''RBMK nuclear reactors: Proposals for instrumentation and control improvements to enhance safety and availability'' prepared by the Joint IEC/IAEA team during 1993-1995. Experience has demonstrated the need to improve the safety instrumentation of the RBMK type reactors using well proven modern technology. The working group identified the upgrades and changes of the highest priority based on the evaluation of the RBMK systems and the events where the instrumentation was found to be inadequate for safe operation. The subjects discussed in this document were not selected on a systematic basis but were selected by the IEC and IAEA experts as considered to be appropriate to the activities of the IEC and for which technical experience was available. The items identified therefore do not reflect any ranking of the safety issues or any priority or impact on safety of any of the measures were they to be implemented. Many important safety issued and areas where physical measures are required to improve safety have been omitted and indeed not even acknowledged in this document. The recommendations presented in the document differ from those normally produced by the IEC in the form of standards as they are of a transitory nature and some have already been overtaken by the continuing process of improvements to plant safety. Figs and tabs

77 FR 9839 - Amendment of Class D and Class E Airspace, and Establishment of Class E Airspace; Bozeman, MT

Science.gov (United States)

2012-02-21

..., to accommodate aircraft using Instrument Landing System (ILS) Localizer (LOC) standard instrument... 6005 Class E airspace areas extending upward from 700 feet or more above the surface of the earth...

2H Evaporator CP class instrumentation uncertainties evaluations

International Nuclear Information System (INIS)

Hwang, E.

1994-01-01

The Evaporator Pot Temperature Instrumentations and the Steam Condensate Gamma Monitors are two instrumentation systems in the 2H Evaporator facilities that are classified as the critical protection. The temperature high alarm and interlock circuit and the temperature recorder circuit of the pot temperature instrumentation loop are described. From the gamma monitor loop, the high gamma alarm and interlock circuit, failure alarm and interlock circuit, cesium activity recorder circuit, and americium activity recorder circuit are described

2H Evaporator CP class instrumentation uncertainties evaluations

Energy Technology Data Exchange (ETDEWEB)

Hwang, E.

1994-02-10

The Evaporator Pot Temperature Instrumentations and the Steam Condensate Gamma Monitors are two instrumentation systems in the 2H Evaporator facilities that are classified as the critical protection. The temperature high alarm and interlock circuit and the temperature recorder circuit of the pot temperature instrumentation loop are described. From the gamma monitor loop, the high gamma alarm and interlock circuit, failure alarm and interlock circuit, cesium activity recorder circuit, and americium activity recorder circuit are described. (GHH)

Analysis of fuel handling system for fuel bundle safety during station blackout in 500 MWe PHWR unit of India

International Nuclear Information System (INIS)

Madhuresh, R.; Nagarajan, R.; Jit, I.; Sanatkumar, A.

1996-01-01

Situations of Station Blackout (SBO) i.e. postulated concurrent unavailability of Class Ill and Class IV power, could arise for a long period, while on-power refuelling or other fuel handling operations are in progress with the hot irradiated fuel bundles being anywhere in the system from the Reactor Building to the Spent Fuel Storage Bay. The cooling provisions for these fuel bundles are diverse and specific to the various stages of fuel handling operations and are either on Class Ill or on Class II power with particular requirements of instrument air. Therefore, during SBO, due to the limited availability of Class II power and instrument air, it becomes difficult to maintain cooling to these fuel bundles. However, some minimal cooling is essential, to ensure the safety of the bundles. As discussed in the paper, safety of these fuel bundles in the system and/or for those lying in the liner tube region of the reactor end fitting is ensured, during SBO, by resorting to passive means like 'stay-put', 'gravity- fill', 'D 2 0- steaming' etc. for cooling the bundles. The paper also describes various consequences emanating from these cooling schemes. (author). 6 refs., 2 tabs., 8 figs

Method to classify the safety class of Structure, System and Components in a Defueled Condition of Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Kim, Dong-Hak; Jeon, Dang-Hee [KHNP CRI, Daejeon (Korea, Republic of)

2016-10-15

During pre-decommissioning phase, licensing and engineering work need to change the design basis of the plant such as safety analysis report, downgrade of systems, technical specifications and program and procedures to change of NPP condition from in an operation condition to in a defueled condition. The many systems to need to operate in an operational condition will not be operated during in a defueled condition and the function of systems will be changed from in an operation condition to in a defueled condition. So a downgrade of systems may be needed and reclassifying the safety class of structure, system and component (SSC) may be conducted. By the reclassification of SSC, activity related with quality assurance and maintenance of SSC is affected. In this paper, the method to reclassify SSC in a defueled condition is studied. The many systems to need to operate in an operational condition will not be operated during in a defueled condition and the function of systems will be changed from in an operation condition to in a defueled condition. The operation of NPP during a defueled condition need to conduct licensing and engineering work need to change the design basis of the plant optimize by downgrading systems and reclassifying the safety class of SSC. In this paper, the method to reclassify safety class for a defueled condition is studied.

Instrumentation, Control, and Intelligent Systems

International Nuclear Information System (INIS)

Not Available

2005-01-01

Abundant and affordable energy is required for U.S. economic stability and national security. Advanced nuclear power plants offer the best near-term potential to generate abundant, affordable, and sustainable electricity and hydrogen without appreciable generation of greenhouse gases. To that end, Idaho National Laboratory (INL) has been charged with leading the revitalization of nuclear power in the U.S. The INL vision is to become the preeminent nuclear energy laboratory with synergistic, world-class, multi-program capabilities and partnerships by 2015. The vision focuses on four essential destinations: (1) Be the preeminent internationally-recognized nuclear energy research, development, and demonstration laboratory; (2) Be a major center for national security technology development and demonstration; (3) Be a multi-program national laboratory with world-class capabilities; (4) Foster academic, industry, government, and international collaborations to produce the needed investment, programs, and expertise. Crucial to that effort is the inclusion of research in advanced instrumentation, control, and intelligent systems (ICIS) for use in current and advanced power and energy security systems to enable increased performance, reliability, security, and safety. For nuclear energy plants, ICIS will extend the lifetime of power plant systems, increase performance and power output, and ensure reliable operation within the system's safety margin; for national security applications, ICIS will enable increased protection of our nation's critical infrastructure. In general, ICIS will cost-effectively increase performance for all energy security systems

An overview of process instrumentation, protective safety interlocks and alarm system at the JET facilities active gas handling system

International Nuclear Information System (INIS)

Skinner, N.; Brennan, P.; Brown, K.; Gibbons, C.; Jones, G.; Knipe, S.; Manning, C.; Perevezentsev, A.; Stagg, R.; Thomas, R.; Yorkshades, J.

2003-01-01

The Joint European Torus (JET) Facilities Active Gas Handling System (AGHS) comprises ten interconnected processing sub-systems that supply, process and recover tritium from gases used in the JET Machine. Operations require a diverse range of process instrumentation to carry out a multiplicity of monitoring and control tasks and approximately 500 process variables are measured. The different types and application of process instruments are presented with specially adapted or custom-built versions highlighted. Forming part of the Safety Case for tritium operations, a dedicated hardwired interlock and alarm system provides an essential safety function. In the event of failure modes, each hardwired interlock will back-up software interlocks and shutdown areas of plant to a failsafe condition. Design of the interlock and alarm system is outlined and general methodology described. Practical experience gained during plant operations is summarised and the methods employed for routine functional testing of essential instrument systems explained

Software qualification in safety applications

International Nuclear Information System (INIS)

Lawrence, J.D.

2000-01-01

The developers of safety-critical instrumentation and control systems must qualify the design of the components used, including the software in the embedded computer systems, in order to ensure that the component can be trusted to perform its safety function under the full range of operating conditions. There are well known ways to qualify analog systems using the facts that: (1) they are built from standard modules with known properties; (2) design documents are available and described in a well understood language; (3) the performance of the component is constrained by physics; and (4) physics models exist to predict the performance. These properties are not generally available for qualifying software, and one must fall back on extensive testing and qualification of the design process. Neither of these is completely satisfactory. The research reported here is exploring an alternative approach that is intended to permit qualification for an important subset of instrumentation software. The research goal is to determine if a combination of static analysis and limited testing can be used to qualify a class of simple, but practical, computer-based instrumentation components for safety application. These components are of roughly the complexity of a motion detector alarm controller. This goal is accomplished by identifying design constraints that enable meaningful analysis and testing. Once such design constraints are identified, digital systems can be designed to allow for analysis and testing, or existing systems may be tested for conformance to the design constraints as a first step in a qualification process. This will considerably reduce the cost and monetary risk involved in qualifying commercial components for safety-critical service

Code coverage measurement methodology for MMI software of safety-class I and C system

Energy Technology Data Exchange (ETDEWEB)

Lee, Eun Hyung; Jung, Beom Young; Choi, Seok Joo [Suresofttech, Seoul (Korea, Republic of)

2016-10-15

MMI (Man-Machine Interface) software of the safety instrumentation and control system used in nuclear power plants carry out an important functions, such as displaying and transmitting the commend to another system, and change setpoints the safety-related information. Yet, this has been recognized reliability of the MMI software plays an important role in enhancing nuclear power plants are operating, regulatory standards have been strengthened with it. Strengthening of regulatory standards has affected even perform software testing soon, and accordingly, the current regulatory require the measurement of code coverage with legal standard. In this paper, it poses a problem of the conventional method used for measuring the above-mentioned code coverage, presents a new coverage measuring method for solving the exposed problems. In this paper, we checked the problems such as limit and the low efficiency of the existing test coverage measuring method on the MMI software using in nuclear power instrumentation and control systems, and it proposed a new test coverage measuring method as a solution for this. If you apply a new method of Top-Down approach, can mitigate all of the problems of existing test coverage measurement methods and possible coverage achievement of the desired objectives. Of course, it is still necessary to secure more cases, and the methodology should be systematization based on the cases. Thus, if later the efficient and reliable are ensured through the application in many cases, as well as nuclear power instrumentation and control, may be used to ensure code coverage of software of the many areas where the GUI is utilized.

Development of nuclear safety class filter elements with long life and high quality

International Nuclear Information System (INIS)

Zhang Jinghua

2009-04-01

This paper describes the development on nuclear safety class filter elements with long life and high quality used for collecting radioactive contaminants, fragments of resin and impurities in primary systems of NPPs. The filter elements made of glass fibre elements are used for PWR, and of paper elements are used for PHWR. During the research, a series of tests for optimization were performed for selection of filter material and the improvement of binder. The flow rate and comprehensive performance have been measured in simulated conditions. The result shows that the application requirements for operational NPPs can be met, and the reliability and safety of the frame are also be verified. The comprehensive performance of the filter elements is equivalent to that of oversea similar products. The products have been used in NPPs in operation. (authors)

Instrumentation of fuel safety test rods of the PWR system in the Phebus reactor

International Nuclear Information System (INIS)

Schley, Robert; Leveque, J.P.; Aujollet, J.M.; Dutraive, Pierre; Colome, Jean; Bouly, J.C.

1979-01-01

The tests were performed in an experimental cell centred in the core of the PHEBUS water reactor of 50 MW. The CEA make two types of apparatus for testing the safety of PWR fuel. One is for testing a single fuel stick and the other a bunch of 25 sticks. The instrumentation described enables the main parameters of the test to be known: temperatures of the fuel - central temperature of the UO 2 - cladding surface temperatures; temperature of the cooling circuits - thermal balance - temperatures of the structures, etc.; coolant pressure; internal pressure of the fuel sticks; direction and flow rate of the fluid. This instrumentation and the technological problems to be overcome are described and the results of the first tests carried out are given [fr

Outline of the requirements of application of computer based instrumentation and control systems in the systems important to safety on Bohunice NPPs

International Nuclear Information System (INIS)

Bacurik, J.

1997-01-01

The most important regulatory requirements and issues are described related to the review, evaluation and assessment of computer-based safety-related IandC systems, with emphasis on safety instrumentation and control. These aspects include safety classification and categorization of IandC, ranking of applicable codes and standards, design evaluation on the system level, and software assessment. (author)

Analysis of fuel handling system for fuel bundle safety during station blackout in 500 MWe PHWR unit of India

Energy Technology Data Exchange (ETDEWEB)

Madhuresh, R; Nagarajan, R; Jit, I; Sanatkumar, A [Nuclear Power Corporation of India Ltd., Mumbai (India)

1997-12-31

Situations of Station Blackout (SBO) i.e. postulated concurrent unavailability of Class Ill and Class IV power, could arise for a long period, while on-power refuelling or other fuel handling operations are in progress with the hot irradiated fuel bundles being anywhere in the system from the Reactor Building to the Spent Fuel Storage Bay. The cooling provisions for these fuel bundles are diverse and specific to the various stages of fuel handling operations and are either on Class Ill or on Class II power with particular requirements of instrument air. Therefore, during SBO, due to the limited availability of Class II power and instrument air, it becomes difficult to maintain cooling to these fuel bundles. However, some minimal cooling is essential, to ensure the safety of the bundles. As discussed in the paper, safety of these fuel bundles in the system and/or for those lying in the liner tube region of the reactor end fitting is ensured, during SBO, by resorting to passive means like `stay-put`, `gravity- fill`, `D{sub 2}0- steaming` etc. for cooling the bundles. The paper also describes various consequences emanating from these cooling schemes. (author). 6 refs., 2 tabs., 8 figs.

Discussion on the safety classification of nuclear safety mechanical equipment

International Nuclear Information System (INIS)

Shen Wei

2010-01-01

The purpose and definition of the equipment safety classification in nuclear plant are introduced. The differences of several safety classification criterions are compared, and the object of safety classification is determined. According to the regulation, the definition and category of the safety functions are represented. The safety classification method, safety classification process, safety class interface, and the requirement for the safety class mechanical equipment are explored. At last, the relation of the safety classification between the mechanical and electrical equipment is presented, and the relation of the safety classification between mechanical equipment and system is also presented. (author)

The Development of the Safety Related Valve Class 1E Electrical Motor, the Target and the Results

International Nuclear Information System (INIS)

Saban, I.; Grgic, D.; Fancev, T.; Flegar, Lj.; Novosel, N.

1996-01-01

The development of the safety related valves class 1E electric motor is described. The design implemented in order to satisfy the 1E requirements, and a way in which related 1E standards are addressed, are shown. The development was realized in three stages. In the first stage eight motorettes were made and the insulation system was tested. In the second stage the motor was produced in accordance with producer's prototype QA program. In the third stage part of the testing of the produced motor was made. The results of the testing, finished until now, show that produced motor, as well as similarly produced motors, is able to perform its safety function in the design bases accident conditions as requested by class 1E requirements. The rest of the testing (LOCA test) can be made on the same or similar motor in the future. (author)

Instrumentation

International Nuclear Information System (INIS)

Umminger, K.

2008-01-01

A proper measurement of the relevant single and two-phase flow parameters is the basis for the understanding of many complex thermal-hydraulic processes. Reliable instrumentation is therefore necessary for the interaction between analysis and experiment especially in the field of nuclear safety research where postulated accident scenarios have to be simulated in experimental facilities and predicted by complex computer code systems. The so-called conventional instrumentation for the measurement of e. g. pressures, temperatures, pressure differences and single phase flow velocities is still a solid basis for the investigation and interpretation of many phenomena and especially for the understanding of the overall system behavior. Measurement data from such instrumentation still serves in many cases as a database for thermal-hydraulic system codes. However some special instrumentation such as online concentration measurement for boric acid in the water phase or for non-condensibles in steam atmosphere as well as flow visualization techniques were further developed and successfully applied during the recent years. Concerning the modeling needs for advanced thermal-hydraulic codes, significant advances have been accomplished in the last few years in the local instrumentation technology for two-phase flow by the application of new sensor techniques, optical or beam methods and electronic technology. This paper will give insight into the current state of instrumentation technology for safety-related thermohydraulic experiments. Advantages and limitations of some measurement processes and systems will be indicated as well as trends and possibilities for further development. Aspects of instrumentation in operating reactors will also be mentioned.

Instrumentation, Control, and Intelligent Systems

Energy Technology Data Exchange (ETDEWEB)

2005-09-01

Abundant and affordable energy is required for U.S. economic stability and national security. Advanced nuclear power plants offer the best near-term potential to generate abundant, affordable, and sustainable electricity and hydrogen without appreciable generation of greenhouse gases. To that end, Idaho National Laboratory (INL) has been charged with leading the revitalization of nuclear power in the U.S. The INL vision is to become the preeminent nuclear energy laboratory with synergistic, world-class, multi-program capabilities and partnerships by 2015. The vision focuses on four essential destinations: (1) Be the preeminent internationally-recognized nuclear energy research, development, and demonstration laboratory; (2) Be a major center for national security technology development and demonstration; (3) Be a multi-program national laboratory with world-class capabilities; (4) Foster academic, industry, government, and international collaborations to produce the needed investment, programs, and expertise. Crucial to that effort is the inclusion of research in advanced instrumentation, control, and intelligent systems (ICIS) for use in current and advanced power and energy security systems to enable increased performance, reliability, security, and safety. For nuclear energy plants, ICIS will extend the lifetime of power plant systems, increase performance and power output, and ensure reliable operation within the system's safety margin; for national security applications, ICIS will enable increased protection of our nation's critical infrastructure. In general, ICIS will cost-effectively increase performance for all energy security systems.

Tests on instrumentation and control systems important to safety in nuclear power stations. Systempruefung der leittechnischen Einrichtungen des Sicherheitssystems in Kernkraftwerken

Energy Technology Data Exchange (ETDEWEB)

1985-01-01

The rule applies to the reactor protection system, to the protection and state boundaries, to control devices important to safety, and to danger alarms of the classes S and I. The system inspection of the control devices of the safety system comprises in-service testing and recurrent testing.

Impact of state-of-the-art instrumentation on safety-related experimental studies proposed in containment studies facility (CSF)

International Nuclear Information System (INIS)

Gole, N.V.; Markandeya, S.G.; Subramaniam, K.; Ghosh, A.K.

2002-01-01

Full text: Conducting an experimental program for safety related studies for nuclear power plants (NPPs) is an extremely laborious and time-consuming task due to several reasons. Requirement for frequent replacements, testing and recalibration of a large number of instruments is one of them. Off-line analysis leading to identification of errors is another. A particular test may have to be abandoned based on such analysis. Following the rapid advances in instrumentation, a larger number of options are now available, which make experimentation easy. CSF is one of the upcoming facilities wherein deployment of state-of-the art became inevitable. This paper discusses in detail the design intent of instrumentation, the state-of-the-art instrumentation provisions made to fulfill it the overall impact of this on successful experimentation

Upgrading instrumentation and control systems for plant safety and operation

International Nuclear Information System (INIS)

Martin, M.; Prehler, H.J.; Schramm, W.

1997-01-01

Upgrading the electrical systems and instrumentation and control systems has become increasingly more important in the past few years for nuclear power plants currently in operation. As the requirements to be met in terms of plant safety and availability have become more stringent in the past few years, Western plants built in the sixties and seventies have been the subject of manifold backfitting and upgrading measures in the past. In the meantime, however, various nuclear power plants are facing much more thorough upgrading phases because of the difficulties in obtaining spare parts for older equipment systems. As digital technology has become widespread in many areas because of its advantages, and as applications are continuously expanding, conventional equipment and systems are losing more and more ground as a consequence of decreasing demand. Merely because of the pronounced decline in demand for conventional electronic components it is possible for equipment manufacturers to guarantee spare parts deliveries for older systems only for specific future periods of time. In addition, one-off manufacture entails high costs in purchases of spare parts. As a consequence of current thinking more and more focusing on availability and economy, upgrading of electrical systems and instrumentation and control systems is becoming a more and more topical question, for older plants even to ensure completion of full service life. (orig.) [de

Laboratory Safety Awareness Among General Physics Undergraduate Students

Directory of Open Access Journals (Sweden)

C. O. Ponferrada

2017-12-01

Full Text Available Safety awareness in the laboratory is essential to reduce occupational risks. This study was conducted to determine the students’ safety awareness in a Physics laboratory. This study determined the student perception towards safety awareness by factors of gender and college from which students are enrolled. A sum of 324 students enrolled in Physics10 (Mechanics and Heat and Physics11 (Electricity and Magnetism in the Mindanao University of Science and Technology (MUST were randomly selected as survey respondents. A modified survey questionnaire was used as research instrument. The results show that the students had positive level of safety awareness and perceived positively on the preventive measures to reduce laboratory risk. Further, regardless of gender students enrolled in Physics 10 were more positively aware towards safety awareness than students enrolled in Physics 11. Similarly, a variation among the students perception towards safety awareness from the College of Engineering and Architecture (CEA and College of Industrial and Information Technology (CIIT occurred. Overall, present findings indicate a need to introduce laboratory safety awareness in Physics classes.

International legal instruments promoting synergy's in nuclear safety, security and safeguards: myth of reality?

International Nuclear Information System (INIS)

Vasmant, A.

2009-01-01

The purpose of this article is to assess the existing synergies between nuclear safety, nuclear security and non-proliferation/safeguards resulting from the adoption of international legal instruments. Keeping in mind that a synergy is the extra success achieved by two or more elements of a system working together instead of on their own, this paper will try to evaluate the possibility of a so-called '3 S' approach to optimize the benefits so defined. to achieve this, Part 1 focuses on the history of the three regimes and their major features, while Part 2, 3 and 4 explore the various benefits of, limits to, synergies between the nuclear safety, nuclear security and safeguards regimes. Part 5 describes the potential '3 S' approach in international nuclear law. (N.C.)

Seismic qualification of safety class components in non-reactor nuclear facilities at Hanford site

International Nuclear Information System (INIS)

Ocoma, E.C.

1989-01-01

This paper presents the methods used during the walkdowns to compile as-built structural information to seismically qualify or verify the seismic adequacy of safety class components in the Plutonium Finishing Plant complex. The Plutonium finishing Plant is a non-reactor nuclear facility built during the 1950's and was designed to the Uniform Building Code criteria for both seismic and wind events. This facility is located at the US Department of Energy Hanford Site near Richland, Washington

A review of the literature pertaining to the efficacy, safety, educational requirements, uses and usage of mechanical adjusting devices

Science.gov (United States)

Taylor, Shane H; Arnold, Nicole D; Biggs, Lesley; Colloca, Christopher J; Mierau, Dale R; Symons, Bruce P; Triano, John J

2004-01-01

Over the past decade, mechanical adjusting devices (MADs) were a major source of debate within the Chiropractors’ Association of Saskatchewan (CAS). Since Saskatchewan was the only jurisdiction in North America to prohibit the use of MADs, the CAS established a committee in 2001 to review the literature on MADs. The committee evaluated the literature on the efficacy, safety, and uses of moving stylus instruments within chiropractic practice, and the educational requirements for chiropractic practice. Following the rating criteria for the evaluation of evidence, as outlined in the Clinical Guidelines for Chiropractic Practice in Canada (1994), the committee reviewed 55 articles – all of which pertained to the Activator. Of the 55 articles, 13 were eliminated from the final study. Of the 42 remaining articles, 6 were rated as class 1 evidence; 11 were rated as class 2 evidence and 25 were rated as class 3 evidence. In this article – the second in a series of two – we review the results of uses and usage, safety and educational requirements. Of the 30 articles designated under the category of usage, 3 were rated as Class 1 evidence; 9 studies were classified as Class 2 evidence and 18 were rated as Class 3 evidence. Overall the committee reached consensus that in clinical practice, there is broad application of these procedures. A minority report was written arguing that the reviewer was unable to reach a conclusion about the use of the Activator Instrument other than it is used as a clinical and research tool. Of the 16 studies that dealt either explicitly or implicitly with safety, 4 were Class 1 evidence; 3 were Class 2 evidence and 9 were Class 3 evidence. Overall the committee reached consensus that the evidence supports that the Activator instrument is safe and has no more relative risk than do manual HVLA procedures. A minority report was written arguing that there is no evidence either to support or refute the view that MAD is safe. Of the 5 studies

Nuclear safety review for qualification of class 1E motor inside containment for nuclear power stations

International Nuclear Information System (INIS)

Li Shixin; Wu Qi; Zhang Yunbo; Wu Caixia

2013-01-01

In nuclear power plants with pressurized water reactors, the review for class 1E motor inside containment qualification process and documents is an important aspect of nuclear safety equipment review, and the reviewers should make evaluations for the qualification test results in terms of the compliance with standard and regulation, and the consistency with inside containment environment. Firstly, this paper introduces the qualification test of class 1E motor inside containment for nuclear power generating stations, such as aging test and design-basis-event test. Second, there is a discussion about typical problems of review. At last, comparison of IEEE334 with RCC-E is conducted and explored. (authors)

Atmospheric effects on laser eye safety and damage to instrumentation

Science.gov (United States)

Zilberman, Arkadi; Kopeika, Natan S.

2017-10-01

Electro-optical sensors as well as unprotected human eyes are extremely sensitive to laser radiation and can be permanently damaged from direct or reflected beams. Laser detector/eye hazard depends on the interaction between the laser beam and the media in which it traverses. The environmental conditions including terrain features, atmospheric particulate and water content, and turbulence, may alter the laser's effect on the detector/eye. It is possible to estimate the performance of an electro-optical system as long as the atmospheric propagation of the laser beam can be adequately modeled. More recent experiments and modeling of atmospheric optics phenomena such as inner scale effect, aperture averaging, atmospheric attenuation in NIR-SWIR, and Cn2 modeling justify an update of previous eye/detector safety modeling. In the present work, the influence of the atmospheric channel on laser safety for personnel and instrumentation is shown on the basis of theoretical and experimental data of laser irradiance statistics for different atmospheric conditions. A method for evaluating the probability of damage and hazard distances associated with the use of laser systems in a turbulent atmosphere operating in the visible and NIR-SWIR portions of the electromagnetic spectrum is presented. It can be used as a performance prediction model for directed energy engagement of ground-based or air-based systems.

Design Review Report for formal review of safety class features of exhauster system for rotary mode core sampling

International Nuclear Information System (INIS)

JANICEK, G.P.

2000-01-01

Report documenting Formal Design Review conducted on portable exhausters used to support rotary mode core sampling of Hanford underground radioactive waste tanks with focus on Safety Class design features and control requirements for flammable gas environment operation and air discharge permitting compliance

Design Review Report for formal review of safety class features of exhauster system for rotary mode core sampling

Energy Technology Data Exchange (ETDEWEB)

JANICEK, G.P.

2000-06-08

Report documenting Formal Design Review conducted on portable exhausters used to support rotary mode core sampling of Hanford underground radioactive waste tanks with focus on Safety Class design features and control requirements for flammable gas environment operation and air discharge permitting compliance.

Microspectrometers: an industry and instrumentation overview

Science.gov (United States)

Neece, Gregory A.

2008-08-01

Microspectrometers, miniature spectrometers, portable spectrometers, or Fiber Optic Spectrometers are some of the names typically given to the class small spectrometers that are derived from simple, fixed optics, and low cost detector arrays. The author will use these terms interchangeably. This class of instrument has been available for over 18 years, gaining industry acceptance with each year. From a very basic optical platform to sophisticated instrumentation for scientific investigation and process control, this class of instrument has evolved substantially since its introduction to the market. For instance it is now possible to cover the range from 200 - 2,500 nm utilizing only two channels of spectrometers with either synchronous or asynchronous channel control. On board processing and memory have enabled the instruments to become fully automated, stand alone sensors communicating with their environment via analog, digital, USB2 and even wireless protocols. New detectors have entered the market enabling solutions "tuned" to the demands of specific applications.

Power station instrumentation

International Nuclear Information System (INIS)

Jervis, M.W.

1993-01-01

Power stations are characterized by a wide variety of mechanical and electrical plant operating with structures, liquids and gases working at high pressures and temperatures and with large mass flows. The voltages and currents are also the highest that occur in most industries. In order to achieve maximum economy, the plant is operated with relatively small margins from conditions that can cause rapid plant damage, safety implications, and very high financial penalties. In common with other process industries, power stations depend heavily on control and instrumentation. These systems have become particularly significant, in the cost-conscious privatized environment, for providing the means to implement the automation implicit in maintaining safety standards, improving generation efficiency and reducing operating manpower costs. This book is for professional instrumentation engineers who need to known about their use in power stations and power station engineers requiring information about the principles and choice of instrumentation available. There are 8 chapters; chapter 4 on instrumentation for nuclear steam supply systems is indexed separately. (Author)

Comprehensive Lifecycle for Assuring System Safety

Science.gov (United States)

Knight, John C.; Rowanhill, Jonathan C.

2017-01-01

CLASS is a novel approach to the enhancement of system safety in which the system safety case becomes the focus of safety engineering throughout the system lifecycle. CLASS also expands the role of the safety case across all phases of the system's lifetime, from concept formation to decommissioning. As CLASS has been developed, the concept has been generalized to a more comprehensive notion of assurance becoming the driving goal, where safety is an important special case. This report summarizes major aspects of CLASS and contains a bibliography of papers that provide additional details.

The ConCom Safety Management Scale: developing and testing a measurement instrument for control-based and commitment-based safety management approaches in hospitals.

Science.gov (United States)

Alingh, Carien W; Strating, Mathilde M H; van Wijngaarden, Jeroen D H; Paauwe, Jaap; Huijsman, Robbert

2018-03-06

Nursing management is considered important for patient safety. Prior research has predominantly focused on charismatic leadership styles, although it is questionable whether these best characterise the role of nurse managers. Managerial control is also relevant. Therefore, we aimed to develop and test a measurement instrument for control-based and commitment-based safety management of nurse managers in clinical hospital departments. A cross-sectional survey design was used to test the newly developed questionnaire in a sample of 2378 nurses working in clinical departments. The nurses were asked about their perceptions of the leadership behaviour and management practices of their direct supervisors. Psychometric properties were evaluated using confirmatory factor analysis and reliability estimates. The final 33-item questionnaire showed acceptable goodness-of-fit indices and internal consistency (Cronbach's α of the subscales range: 0.59-0.90). The factor structure revealed three subdimensions for control-based safety management: (1) stressing the importance of safety rules and regulations; (2) monitoring compliance; and (3) providing employees with feedback. Commitment-based management consisted of four subdimensions: (1) showing role modelling behaviour; (2) creating safety awareness; (3) showing safety commitment; and (4) encouraging participation. Construct validity of the scale was supported by high factor loadings and provided preliminary evidence that control-based and commitment-based safety management are two distinct yet related constructs. The findings were reconfirmed in a cross-validation procedure. The results provide initial support for the construct validity and reliability of our ConCom Safety Management Scale. Both management approaches were found to be relevant for managing patient safety in clinical hospital departments. The scale can be used to deepen our understanding of the influence of patient safety management on healthcare professionals

Reconstruction of instrumentation and control system (SKR)

International Nuclear Information System (INIS)

Wiening, K.-H.

2001-01-01

For the first time extensive upgrades have been performed in all safety related areas of units with WWER 440/230 reactors. One of the most important actions was the replacement of the safety and safety related instrumentation and control. The state of the art digital safety instrumentation and control system TELEPERM XS has been implemented in units 1 and 2 of the Bohunice V1 power plant. The requirements as deduced from safety assessments conducted by commissions of international experts have been fulfilled, so that Bohunice V1 after this gradual reconstruction has been upgraded to an internationally accepted safety level for the remainder of its service life. (author)

Early modern mathematical instruments.

Science.gov (United States)

Bennett, Jim

2011-12-01

In considering the appropriate use of the terms "science" and "scientific instrument," tracing the history of "mathematical instruments" in the early modern period is offered as an illuminating alternative to the historian's natural instinct to follow the guiding lights of originality and innovation, even if the trail transgresses contemporary boundaries. The mathematical instrument was a well-defined category, shared across the academic, artisanal, and commercial aspects of instrumentation, and its narrative from the sixteenth to the eighteenth century was largely independent from other classes of device, in a period when a "scientific" instrument was unheard of.

Digital instrumentation system for nuclear research reactors

International Nuclear Information System (INIS)

Aghina, Mauricio A.C.; Carvalho, Paulo Vitor R.

2002-01-01

This work describes a proposal for a system of nuclear instrumentation and safety totally digital for the Argonauta Reactor. The system divides in the subsystems: channel of pulses, channel of current, conventional instrumentation and safety system. The connection of the subsystems is made through redundant double local net, using the protocol modbus/rtu. So much the channel of pulses, the current channel and safety's system use modules operating in triple redundancy. (author)

Instrumentation development

International Nuclear Information System (INIS)

Ubbes, W.F.; Yow, J.L. Jr.

1988-01-01

Instrumentation is developed for the Civilian Radioactive Waste Management Program to meet several different (and sometimes conflicting) objectives. This paper addresses instrumentation development for data needs that are related either directly or indirectly to a repository site, but does not touch on instrumentation for work with waste forms or other materials. Consequently, this implies a relatively large scale for the measurements, and an in situ setting for instrument performance. In this context, instruments are needed for site characterization to define phenomena, develop models, and obtain parameter values, and for later design and performance confirmation testing in the constructed repository. The former set of applications is more immediate, and is driven by the needs of program design and performance assessment activities. A host of general technical and nontechnical issues have arisen to challenge instrumentation development. Instruments can be classed into geomechanical, geohydrologic, or other specialty categories, but these issues cut across artificial classifications. These issues are outlined. Despite this imposing list of issues, several case histories are cited to evaluate progress in the area

Knowledge and practices about hospital waste disposal and universal safety precautions in class IV employee.

Science.gov (United States)

Megha, Khobragade; Daksha, Pandit

2013-01-01

Norms and guidelines are formed for safe disposal of hospital waste but question is whether these guidelines are being followed and if so, to what extent. Hence, this study was conducted with objective to study the knowledge and practices about hospital waste disposal and universal safety precautions in class IV employee and to study its relationship with education, occupation and training. A cross-sectional study was carried out in a teaching hospital in Mumbai using semi-structured questionnaire in which Class IV employee were included. Questionnaire was filled by face to face interview. Data were analyzed using SPSS. 48.7% Class IV employee were not trained. More than 40% were following correct practices about disinfection of infectious waste. None of the respondents were using protective footwear while handling hospital waste. Only 25.5% were vaccinated for hepatitis B. 16% had done HIV testing due to contact with blood, body fluid, needle stick injury. Knowledge and practices about hospital waste disposal and universal precaution were statistically significant in trained respondents. Training of employees should be given top priority; those already in service should be given on the job training at the earliest.

Methodology and development of instruments for the safety analysis of a nuclear reprocessing plant

International Nuclear Information System (INIS)

Markett, J.

1987-01-01

Characteristics and overlapping aspects in the elaboration of safety analyses for the nuclear and conventional units are presented. The current methods are presented and their limits of applicability characterized. The transferability of individual methods or their elements to the analysis of the reference plant of Wackersdorf is examined and the procedure for the systems analysis is determined. It is of great importance to prove that the essential kinds of incidents and possibilities of release with potential effects in the environment are completely identified. The incidents are divided into basic incidents, which are characterized by superior physical/chemical release mechanisms. An essential objective is to systematize the safety analysis and to summarize the presentation of results. Selection criteria are presented, which allow a limitation of the analysis to essential influencing parameters without removing aspects from the overall safety-relevant statement. Besides the selection criteria, instruments and mathematical models are explained with the help of which the representative and possible incidents covering all potential risks for all areas of the plant, systems and components can be selected. These design-basis accidents (criticality, self-heating, fire, explosion, leakages, earth quakes) are decisive for the determination of potential damaging effects in the environment and thus for the overall statement on the licensability. (orig./HP) [de

Loosely coupled class families

DEFF Research Database (Denmark)

Ernst, Erik

2001-01-01

are expressed using virtual classes seem to be very tightly coupled internally. While clients have achieved the freedom to dynamically use one or the other family, it seems that any given family contains a xed set of classes and we will need to create an entire family of its own just in order to replace one...... of the members with another class. This paper shows how to express class families in such a manner that the classes in these families can be used in many dierent combinations, still enabling family polymorphism and ensuring type safety....

Characteristics of the safety climate in teams with world-class safety ...

African Journals Online (AJOL)

interact to deliver a project successfully in terms of cost .... small-scale accidents occurring at high frequency and from diverse ... the team dynamics of role players in a construction project and .... modified safety pyramid to measure the impact of the safety climate ...... Methodological Centre for Vocational Education and.

Safety climate and attitude as evaluation measures of organizational safety.

Science.gov (United States)

Isla Díaz, R; Díaz Cabrera, D

1997-09-01

The main aim of this research is to develop a set of evaluation measures for safety attitudes and safety climate. Specifically it is intended: (a) to test the instruments; (b) to identify the essential dimensions of the safety climate in the airport ground handling companies; (c) to assess the quality of the differences in the safety climate for each company and its relation to the accident rate; (d) to analyse the relationship between attitudes and safety climate; and (e) to evaluate the influences of situational and personal factors on both safety climate and attitude. The study sample consisted of 166 subjects from three airport companies. Specifically, this research was centered on ground handling departments. The factor analysis of the safety climate instrument resulted in six factors which explained 69.8% of the total variance. We found significant differences in safety attitudes and climate in relation to type of enterprise.

Contribution to the safety assessment of instrumentation and control software for nuclear power plants. Application to spin N4

International Nuclear Information System (INIS)

Soubies, B.; Boulc'h, J.; Elsensohn, O.; Le Meur, M.; Henry, J.Y.

1994-01-01

The process of licensing nuclear power plants for operation consists of mandatory steps featuring detailed examination of the instrumentation and control system. Significant changes were introduced by the operator in the process of designing and producing 1400 MWe pressurized water reactor safety systems and, in particular, in the case of the Digital Integrated Protection System, (French abbreviation SPIN). The methodology applied by the Institute of Protection and Nuclear Safety (IPSN) to examine the software of this system is described. It consists of the methods used by the manufacturer to develop SPIN software for the 1400 MWe PWRs, and the approach adopted by the IPSN to evaluate SPIN safety softwares of the protection system for the N4 series of reactors. (R.P.). 2 refs

Building a World-Class Safety Culture: The National Ignition Facility and the Control of Human and Organizational Error

International Nuclear Information System (INIS)

Bennett, C T; Stalnaker, G

2002-01-01

Accidents in complex systems send us signals. They may be harbingers of a catastrophe. Some even argue that a ''normal'' consequence of operations in a complex organization may not only be the goods it produces, but also accidents and--inevitably--catastrophes. We would like to tell you the story of a large, complex organization, whose history questions the argument ''that accidents just happen.'' Starting from a less than enviable safety record, the National Ignition Facility (NIF) has accumulated over 2.5 million safe hours. The story of NIF is still unfolding. The facility is still being constructed and commissioned. But the steps NIF has taken in achieving its safety record provide a principled blueprint that may be of value to others. Describing that principled blueprint is the purpose of this paper. The first part of this paper is a case study of NIF and its effort to achieve a world-class safety record. This case study will include a description of (1) NIF's complex systems, (2) NIF's early safety history, (3) factors that may have initiated its safety culture change, and (4) the evolution of its safety blueprint. In the last part of the paper, we will compare NIF's safety culture to what safety industry experts, psychologists, and sociologists say about how to shape a culture and control organizational error

Evaluation of temporary non-code repairs in safety class 3 piping systems

International Nuclear Information System (INIS)

Godha, P.C.; Kupinski, M.; Azevedo, N.F.

1996-01-01

Temporary non-ASME Code repairs in safety class 3 pipe and piping components are permissible during plant operation in accordance with Nuclear Regulatory Commission Generic Letter 90-05. However, regulatory acceptance of such repairs requires the licensee to undertake several timely actions. Consistent with the requirements of GL 90-05, this paper presents an overview of the detailed evaluation and relief request process. The technical criteria encompasses both ductile and brittle piping materials. It also lists appropriate evaluation methods that a utility engineer can select to perform a structural integrity assessment for design basis loading conditions to support the use of temporary non-Code repair for degraded piping components. Most use of temporary non-code repairs at a nuclear generating station is in the service water system which is an essential safety related system providing the ultimate heat sink for various plant systems. Depending on the plant siting, the service water system may use fresh water or salt water as the cooling medium. Various degradation mechanisms including general corrosion, erosion/corrosion, pitting, microbiological corrosion, galvanic corrosion, under-deposit corrosion or a combination thereof continually challenge the pressure boundary structural integrity. A good source for description of corrosion degradation in cooling water systems is provided in a cited reference

Euro NCAP, a safety instrument.

NARCIS (Netherlands)

2007-01-01

Since early 1997, in Europe, a cooperation of consumer organizations, European governments, the European Commission, and car organizations have been doing crash tests to judge the safety of cars. This programme is called Euro NCAP. The test programme consists of four tests of new cars to see how

The Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. An instrument to achieve a global safety

International Nuclear Information System (INIS)

Risoluti, P.

2006-01-01

The Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management (the Joint Convention) is the first legally binding international treaty in the area of radioactive material management. It was adopted by a Diplomatic Conference in September 1997 and opened for signature on 29 September 1997. The Convention entered into force on 18 June 1998, and to date (May 2006) has been ratified by 41 countries. The Joint Convention applies to spent fuel and radioactive waste resulting from civilian application. Its principal aim is to achieve and maintain a high degree of safety in their management worldwide. The Convention is an incentive instrument, not designed to ensure fulfilment of obligations through control and sanction, but by a volunteer peer review mechanism. The obligations of the Contracting Parties are mainly based on the international safety standards developed by the IAEA in past decades. The Convention is of interest of all countries generating radioactive waste. Therefore it is relevant not only for those using nuclear power, but for any country where application of nuclear energy in education, agriculture, medicine and industry is currently used. Obligations of Contracting Parties include attending a Review Meeting held every three years and prepare National Reports for review by the other Contracting Parties. In the National Reports basic information on inventory and facilities for management of radioactive materials has to be provided. Countries with small nuclear power and/or research programs or countries having radioactive materials only from nuclear application on medicine, agriculture or conventional industry, can benefit from the exchange of information and the technical knowledge gained by the reporting procedure set up by the Convention. The second Review Meeting is to be held at IAEA headquarters from 15 to 26 May 2006. This paper presents the objectives and the implementation status of the Convention, the

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

International Nuclear Information System (INIS)

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

2015-01-01

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

Safety Assessment in Installation of Precast Concrete

Directory of Open Access Journals (Sweden)

Yashrri S.N.

2014-03-01

Full Text Available This study was carried out to identify the safety aspects and the level of safety during the installation process in construction sites. A questionnaire survey and interviews were done to provide data on safety requirements in precast concrete construction. All of the interviews and the research questionnaire survey were conducted among contractors that are registered as class 1 to class 7 with the Construction Industry Development Board (CIDB and class A to class G with Pusat Khidmat Kontraktor (PKK in Penang. Returned questionnaires were analysed with the use of simple percentages and the Likert Scale analysis method to identify safety aspects of precast construction. The results indicate that the safety aspect implemented by companies involved in the precast construction process is at a good level in the safety aspect during bracing, propping, welding and grouting processes and at a very good level of safety in general aspects and safety aspects during lifting processes.

Design concepts for a nuclear digital instrumentation and control system platform

International Nuclear Information System (INIS)

Ou, T. C.; Chen, C. K.; Chen, P. J.; Shyu, S. S.; Lee, C. L.; Hsieh, S. F.

2010-10-01

The objective of this paper is to present the development results of the nuclear instrumentation and control system in Taiwan. As the Taiwan nuclear power plants age, the need to consider upgrading of both their safety and non-safety-related instrumentation and control systems becomes more urgent. Meanwhile, the digital instrumentation and control system that is based on current fast evolving electronic and information technologies are difficult to maintain effectively. Therefore, Institute of Nuclear Energy Research was made a decision to promote the Taiwan Nuclear Instrumentation and Control System project to collaborate with domestic electronic industry to establish self-reliant capabilities on the design, manufacturing, and application of nuclear instrumentation and control systems with newer technology. In the case of safety-related applications like nuclear instrumentation and control, safety-oriented quality control is required. In order to establish a generic qualified digital platform, the world-wide licensing experience should be considered in the licensing process. This paper describes the qualification and certification tools by IEC 61508 for design and development of safety related equipment and explains the basis for many decisions made while performing the digital upgrade. (Author)

Comparative instrumental evaluation of efficacy and safety between a binary and a ternary system in chemexfoliation.

Science.gov (United States)

Cameli, Norma; Mariano, Maria; Ardigò, Marco; Corato, Cristina; De Paoli, Gianfranco; Berardesca, Enzo

2017-09-20

To instrumentally evaluate the efficacy and the safety of a new ternary system chemo exfoliating formulation (water-dimethyl isosorbide-acid) vs traditional binary systems (water and acid) where the acid is maintained in both the systems at the same concentration. Different peelings (binary system pyruvic acid and trichloroacetic acid-TCA, and ternary system pyruvic acid and TCA) were tested on the volar forearm of 20 volunteers of both sexes between 28 and 50 years old. The outcomes were evaluated at the baseline, 10 minutes, 24 hours, and 1 week after the peeling by means of noninvasive skin diagnosis techniques. In vivo reflectance confocal microscopy was used for stratum corneum evaluation, transepidermal waterloss, and Corneometry for skin barrier and hydration, Laser Doppler velocimetry in association with colorimetry for irritation and erythema analysis. The instrumental data obtained showed that the efficacy and safety of the new ternary system peel compounds were significantly higher compared with the binary system formulations tested. The new formulation peels improved chemexfoliation and reduced complications such as irritation, redness, and postinflammatory pigmentation compared to the traditional aqueous solutions. The study showed that ternary system chemexfoliation, using a controlled delivery technology, was able to provide the same clinical effects in term of stratum corneum reduction with a significantly reduced barrier alteration, water loss, and irritation/erythema compared to traditional binary system peels. © 2017 Wiley Periodicals, Inc.

A Model Proposal and Implementation Concerning Occupational Health and Safety within the Framework of World Class Manufacturing

OpenAIRE

GÜMÜŞOĞLU, Şevkinaz; TEPEKULE, Esin Tuba

2017-01-01

The approach, which aims atbecoming the best in every application and operation realizing every strategythat it has at a perfect level, has been referred to as World ClassManufacturing (WCM).  The synergic effectof WCM inherent in application and strategies will be helpful in takingbusinesses’ strength to the desired level in the current competitiveenvironment. For businesses in applications of Occupational Health and Safety(OHS) to perform at the top level will contribute to become the best,...

24 CFR 232.570 - Endorsement of credit instrument.

Science.gov (United States)

2010-04-01

... 24 Housing and Urban Development 2 2010-04-01 2010-04-01 false Endorsement of credit instrument... of Fire Safety Equipment Eligible Security Instruments § 232.570 Endorsement of credit instrument. The Commissioner shall indicate his insurance of the loan by endorsing the credit instrument and...

Technical Support Section Instrument Support Program for nuclear and nonnuclear facilities with safety requirements

International Nuclear Information System (INIS)

Adkisson, B.P.; Allison, K.L.

1995-01-01

This document describes requirements, procedures, and supervisory responsibilities of the Oak Ridge National Laboratory (ORNL) Instrumentation and Controls (I ampersand C) Division's Technical Support Section (TSS) for instrument surveillance and maintenance in nonreactor nuclear facilities having identified Operational Safety Requirements (OSRs) or Limiting Conditions Document (LCDs). Implementation of requirements comply with the requirements of U.S. Department of Energy (DOE) Orders 5480.5, 5480.22, and 5481.1B; Martin Marietta Energy Systems, Inc. (Energy Systems), Policy Procedure ESS-FS-201; and ORNL SPP X-ESH-15. OSRs and LCDs constitute an agreement or contract between DOE and the facility operating management regarding the safe operation of the facility. One basic difference between OSRs and LCDs is that violation of an OSR is considered a Category II occurrence, whereas violation of an LCD requirement is considered a Category III occurrence (see Energy Systems Standard ESS-OP-301 and ORNL SPP X-GP-13). OSRs are required for high- and moderate-hazard nuclear facilities, whereas the less-rigorous LCDs are required for low-hazard nuclear facilities and selected open-quotes generally acceptedclose quotes operations. Hazard classifications are determined through a hazard screening process, which each division conducts for its facilities

Problems of safety and risk in physical education

Directory of Open Access Journals (Sweden)

Robert Podstawski

2015-10-01

Full Text Available Purpose: One of the methodology issues in Physical Education is providing children with safety. The purpose of this work is to present basic concepts of safety at Physical Education classes. Material & Methods: The issues connected with safety at classes of Physical Education have been discussed in the subsections, each of which focuses on different concepts such as: legal safety regulations, causes of hazards, theoretical models of preventing hazards at P.E. classes, nutrition programs related to exercise’s fulfillment, prevention of heat disorders and dehydration. Results: According to experts’ opinion, the causes of safety hazards at P.E. classes can be divided into three groups: caused by instructor, caused by a student, and finally hazards technical in nature. The number of accidents during P.E. classes is still substantial, and among most common hazards there are the following: fractures of upper and lower limbs, dislocations, contusions, tendonitis, muscle tear and cuts. Curiously, boys experience such injuries more frequently than girls. Conclusions: Even though safety rules at Physical Education classes are defined by specific regulations, children’s absolute safety is never guaranteed. In order to diminish the number of misadventures, instructor is obliged not only to adhere to the norms but also to teach children to safety rules.

New technology in nuclear power plant instrumentation and control

International Nuclear Information System (INIS)

Anon.

1985-01-01

The primary topic of this book is what can be done to improve nuclear power plant operation safety and the economic benefits that can be gained with the utilization of advance instrumentation and control technology. Other topics discussed are the industry's reluctance to accept new designs determining cost effective improvements, and difficulties in meeting regulatory standards with new technology control. The subjects will be useful when considering the area of instrumentation and control for enhancing plant operation and safety. Contents: Advanced Instrumention, Plant Control and Monitoring, Plant Diagnostics and Failure Detection, Human Factors Considerations in Instrumentation and Control, NRC and Industry Perspective on Advanced Instrumentation and Control

Development of Interactive Monitoring System for Neutron Scattering Instrument

Energy Technology Data Exchange (ETDEWEB)

So, Ji Yong [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-10-15

Neutron scattering instruments in HANARO research reactor have been contributed to various fields of basic science and material engineering. These instruments are open to publics and researchers can apply beam-time and do experiments with instrument scientists. In most cases, these instruments run for several weeks without stopping, and therefore instrument scientist wants to see the instrument status and receive information if the instruments have some problem. This is important for the safety. However, it is very hard to get instrument information outside of instruments. Access from external site is strongly forbidden in the institute due to the network safety, I developed another way to send instrument status information using commercial short messaging service(SMS). In this presentation, detailed features of this system will be shown. As a prototype, this system is being developed for the single instrument: Disk-chopper time-of-flight instruments (DC-TOF). I have successfully developed instruments and operate for several years. This information messaging system can be used for other neutron scattering instruments.

Assessment and management of ageing of major nuclear power plant components important to safety: In-containment instrumentation and control cables. Volume I

International Nuclear Information System (INIS)

2000-12-01

At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of major NPP components (e.g. caused by unanticipated phenomena and by operating, maintenance, design or manufacturing error) can jeopardize plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling within acceptable limits the ageing degradation and wear-out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This publication is one in a series of guidance reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers, and technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety, which was issued by the IAEA in 1992. The current practices for the assessment of safety margins (fitness-for-service) and the inspection, monitoring and mitigation of ageing degradation of selected components of Canadian deuterium-uranium (CANDU) reactors, boiling water reactors (BWRs), pressurized water reactors (PWRs), including the Soviet designed 'water moderated and water cooled energy reactors' (WWERs), are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues. The guidance reports are directed at technical experts and managers from NPPs and from regulatory, plant design, manufacturing

Assessment and management of ageing of major nuclear power plant components important to safety: In-containment instrumentation and control cables. Volume II

International Nuclear Information System (INIS)

2000-12-01

At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that ineffective control of the ageing degradation of major NPP components (e.g. caused by unanticipated phenomena and by operating, maintenance, design or manufacturing error) can jeopardize plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling within acceptable limits the ageing degradation and wear-out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This publication is one in a series of guidance reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers, and technical support organizations and a widely accepted Methodology for the Management of Ageing of NPP Components Important to Safety, which was issued by the IAEA in 1992. The current practices for the assessment of safety margins (fitness-for-service) and the inspection, monitoring and mitigation of ageing degradation of selected components of Canadian deuterium-uranium (CANDU) reactors, boiling water reactors (BWRs), pressurized water reactors (PWRs), including the Soviet designed 'water moderated and water cooled energy reactors' (WWERs), are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues. The guidance reports are directed at technical experts and managers from NPPs and from regulatory, plant design, manufacturing

Operational safety

International Nuclear Information System (INIS)

Anon.

1977-01-01

The PNL Safety, Standards and Compliance Program contributed to the development and issuance of safety policies, standards, and criteria; for projects in the nuclear and nonnuclear areas. During 1976 the major emphasis was on developing criteria, instruments and methods to assure that radiation exposure to occupational personnel and to people in the environs of nuclear-related facilities is maintained at the lowest level technically and economically practicable. Progress in 1976 is reported on the preparation of guidelines for radiation exposure; Pu dosimetry studies; the preparation of an environmental monitoring handbook; and emergency instrumentation preparedness

Safety

International Nuclear Information System (INIS)

2001-01-01

This annual report of the Senior Inspector for the Nuclear Safety, analyses the nuclear safety at EDF for the year 1999 and proposes twelve subjects of consideration to progress. Five technical documents are also provided and discussed concerning the nuclear power plants maintenance and safety (thermal fatigue, vibration fatigue, assisted control and instrumentation of the N4 bearing, 1300 MW reactors containment and time of life of power plants). (A.L.B.)

Nuclear power plant control and instrumentation in Italy

International Nuclear Information System (INIS)

Lantieri, A.

1992-01-01

The National Energy Plan (PEN) approved by the Government of Italy in August 1988 provides a programme of research and industrial development or reactors with inherent and passive safety features. For the Control Systems and Instrumentation there is the aim to define rules and design criteria, by evaluating the impact of inherent safety goals on the C and I design. The effort on man-machine interface is considered essential to increase safety and efficiency of advanced reactors. The paper briefly describes the activity in control systems and in the instrumentation area. (author)

Reactor instrumentation renewal of the TRIGA reactor Vienna, Austria

International Nuclear Information System (INIS)

Boeck, H.; Weiss, H.; Hood, W.E.; Hyde, W.K.

1992-01-01

The TRIGA Mark-II reactor at the Atominstitut in Vienna, Austria is replacing its twenty-four year old instrumentation system with a microprocessor based control system supplied by General Atomics. Ageing components, new governmental safety requirements and a need for state of the art instrumentation for training students has spurred the demand for new reactor instrumentation. In Austria a government appointed expert is assigned the responsibility of reviewing the proposed installation and verifying all safety aspects. After a positive review, final assembly and checkout of the instrumentation system may commence. The instrumentation system consists of three basic modules: the control system console, the data acquisition console and the NH-1000 wide range channel. Digital communications greatly reduce interwiring requirements. Hardwired safety channels are independent of computer control, thus, the instrumentation system in no way relies on any computer intervention for safety function. In addition, both the CSC and DAC computers are continuously monitored for proper operation via watchdog circuits which are capable of shutting down the reactor in the event of computer malfunction. Safety channels include two interlocked NMP-1000 multi-range linear channels for steady state mode, an NPP-1000 linear safety channel for pulse mode and a set of three independent fuel temperature monitoring channels. The microprocessor controlled wide range NM- 1000 digital neutron monitor (fission chamber based) functions as a startup/operational channel, and provides all power level related Interlocks. The Atominstitut TRIGA reactor is configured for four modes of operation: manual mode, automatic mode (servo control), pulsing mode and square wave mode. Control of the standard control rods is via stepping motor control rod drives, which offers the operator the choice of which control rods are operated by the servo system in automatic and square wave model. (author)

Reusable libraries for safety-critical Java

DEFF Research Database (Denmark)

Rios Rivas, Juan Ricardo; Schoeberl, Martin

2014-01-01

The large collection of Java class libraries is a main factor of the success of Java. However, these libraries assume that a garbage-collected heap is used. Safety-critical Java uses scope-based memory areas instead of a garbage-collected heap. Therefore, the Java class libraries are problematic...... to use in safety-critical Java. We have identified common programming patterns in the Java class libraries that make them unsuitable for safety-critical Java. We propose ways to improve the libraries to avoid the impact of the identified problematic patterns. We illustrate these changes by implementing...

The Communication Audit as a Class Project.

Science.gov (United States)

Conaway, Roger N.

1994-01-01

Describes a class project in which students conduct a "communication audit" or assessment of an off-campus organization, providing students with opportunities to explore, examine, monitor, and evaluate communication in a practical way. Discusses grading, beginning the class, contacting clients, instrumentation and procedures, costs, and…

Evaluating the Impact of Radio Frequency Identification Retained Surgical Instruments Tracking on Patient Safety: Literature Review.

Science.gov (United States)

Schnock, Kumiko O; Biggs, Bonnie; Fladger, Anne; Bates, David W; Rozenblum, Ronen

2017-02-22

Retained surgical instruments (RSI) are one of the most serious preventable complications in operating room settings, potentially leading to profound adverse effects for patients, as well as costly legal and financial consequences for hospitals. Safety measures to eliminate RSIs have been widely adopted in the United States and abroad, but despite widespread efforts, medical errors with RSI have not been eliminated. Through a systematic review of recent studies, we aimed to identify the impact of radio frequency identification (RFID) technology on reducing RSI errors and improving patient safety. A literature search on the effects of RFID technology on RSI error reduction was conducted in PubMed and CINAHL (2000-2016). Relevant articles were selected and reviewed by 4 researchers. After the literature search, 385 articles were identified and the full texts of the 88 articles were assessed for eligibility. Of these, 5 articles were included to evaluate the benefits and drawbacks of using RFID for preventing RSI-related errors. The use of RFID resulted in rapid detection of RSI through body tissue with high accuracy rates, reducing risk of counting errors and improving workflow. Based on the existing literature, RFID technology seems to have the potential to substantially improve patient safety by reducing RSI errors, although the body of evidence is currently limited. Better designed research studies are needed to get a clear understanding of this domain and to find new opportunities to use this technology and improve patient safety.

Safety-related instrumentation and control systems for nuclear power plants

International Nuclear Information System (INIS)

1984-01-01

This Safety Guide deals mainly with design requirements for those I and C systems that are important to safety but are not safety systems. The Guide is intended to expand paragraphs 3.1, 3.2 and 3.3 of the Code of Practice on Design for Safety of Nuclear Power Plants (IAEA Safety Series No.50-C-D) in the area of I and C systems important to safety and refers to them as safety-related I and C systems. It also gives guidance and enumerates requirements for multiplexing and the use of the digital computers employed in this area

Modernization of control instrumentation and security of reactor IAN - R1

International Nuclear Information System (INIS)

Gonzalez, J. M.

1993-01-01

The program to modernize IAN-R1 research reactor control and safety instrumentation has been carried out considering two main aspects: updating safety philosophy requirements and acquiring the newest reactor control instrumentation controlled by computer, following the present criteria internationally recognized, for safety and reliable reactor operations and the latest developments of nuclear electronic technology. The new IAN-R1 reactor instrumentation consist of two wide range neutron monitoring channels, commanded by microprocessor a data acquisition system and reactor control, (controlled by computers). The reactor control desk is providing through two displays; all safety and control signals to the reactor operators; furthermore some signals like reactor power, safety and period signals are also showed on digital bar graphics, which are hard wired directly from the neutron monitoring channels

Quantitative assessment of probability of failing safely for the safety instrumented system using reliability block diagram method

International Nuclear Information System (INIS)

Jin, Jianghong; Pang, Lei; Zhao, Shoutang; Hu, Bin

2015-01-01

Highlights: • Models of PFS for SIS were established by using the reliability block diagram. • The more accurate calculation of PFS for SIS can be acquired by using SL. • Degraded operation of complex SIS does not affect the availability of SIS. • The safe undetected failure is the largest contribution to the PFS of SIS. - Abstract: The spurious trip of safety instrumented system (SIS) brings great economic losses to production. How to ensure the safety instrumented system is reliable and available has been put on the schedule. But the existing models on spurious trip rate (STR) or probability of failing safely (PFS) are too simplified and not accurate, in-depth studies of availability to obtain more accurate PFS for SIS are required. Based on the analysis of factors that influence the PFS for the SIS, using reliability block diagram method (RBD), the quantitative study of PFS for the SIS is carried out, and gives some application examples. The results show that, the common cause failure will increase the PFS; degraded operation does not affect the availability of the SIS; if the equipment was tested and repaired one by one, the unavailability of the SIS can be ignored; the corresponding occurrence time of independent safe undetected failure should be the system lifecycle (SL) rather than the proof test interval and the independent safe undetected failure is the largest contribution to the PFS for the SIS

Optimal Design of Safety Instrumented Systems for Pressure Control of Methanol Separation Columns in the Bisphenol a Manufacturing Process

Directory of Open Access Journals (Sweden)

In-Bok Lee

2016-12-01

Full Text Available A bisphenol A production plant possesses considerable potential risks in the top of the methanol separation column, as pressurized acetone, methanol, and water are processed at an elevated temperature, especially in the event of an abnormal pressure increase due to a sudden power outage. This study assesses the potential risks in the methanol separation column through hazard and operability assessments and evaluates the damages in the case of fire and explosion accident scenarios. The study chooses three leakage scenarios: a 5-mm puncture on the methanol separation column, a 50-mm diameter fracture of a discharge pipe and a catastrophic rupture, and, simulated using Phast (Ver. 6.531, the concentration distribution of scattered methanol, thermal radiation distribution of fires, and overpressure distribution of vapor cloud explosions. Implementation of a safety-instrumented system equipped with two-out-of-three voting as a safety measure can detect overpressure at the top of the column and shut down the main control valve and the emergency shutoff valve simultaneously. By applying a safety integrity level of three, the maximal release volume of the safety relief valve can be reduced and, therefore, the design capacity of the flare stack can also be reduced. Such integration will lead to improved safety at a reduced cost.

Reliability analysis and computation of computer-based safety instrumentation and control used in German nuclear power plant. Final report; Zuverlaessigkeitsuntersuchung und -berechnung rechnerbasierter Sicherheitsleittechnik zum Einsatz in deutschen Kernkraftwerken. Abschlussbericht

Energy Technology Data Exchange (ETDEWEB)

Ding, Yongjian [Hochschule Magdeburg-Stendal, Magdeburg (Germany). Inst. fuer Elektrotechnik; Krause, Ulrich [Magdeburg Univ. (Germany). Inst. fuer Apparate- und Umwelttechnik; Gu, Chunlei

2014-08-21

The trend of technological advancement in the field of safety instrumentation and control (I and C) leads to increasingly frequent use of computer-based (digital) control systems which consisting of distributed, connected bus communications computers and their functionalities are freely programmable by qualified software. The advantages of the new I and C system over the old I and C system with hard-wired technology are e.g. in the higher flexibility, cost-effective procurement of spare parts, higher hardware reliability (through higher integration density, intelligent self-monitoring mechanisms, etc.). On the other hand, skeptics see the new technology with the computer-based I and C a higher potential by influences of common cause failures (CCF), and the easier manipulation by sabotage (IT Security). In this joint research project funded by the Federal Ministry for Economical Affaires and Energy (BMWi) (2011-2014, FJZ 1501405) the Otto-von-Guericke-University Magdeburg and Magdeburg-Stendal University of Applied Sciences are therefore trying to develop suitable methods for the demonstration of the reliability of the new instrumentation and control systems with the focus on the investigation of CCF. This expertise of both houses shall be extended to this area and a scientific contribution to the sound reliability judgments of the digital safety I and C in domestic and foreign nuclear power plants. First, the state of science and technology will be worked out through the study of national and international standards in the field of functional safety of electrical and I and C systems and accompanying literature. On the basis of the existing nuclear Standards the deterministic requirements on the structure of the new digital I and C system will be determined. The possible methods of reliability modeling will be analyzed and compared. A suitable method called multi class binomial failure rate (MCFBR) which was successfully used in safety valve applications will be

IEEE standard criteria for type tests of class 1E modules used in nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1977-01-01

The Institute of Electrical and Electronics Engineers has generated this document to provide direction for type testing Class 1E modules and obtaining specific type test data. It supplements IEEE Std 323-1974, Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations, which describes the basic requirements for Class 1E equipment qualification. Adherence to this document alone may not suffice for assuring public health and safety because it is the integrated performance of the structures, the fluid systems, the electrical systems, the instrumentation systems of the station, and in particular, the plant protection system of which these modules are a part that prevents accidents or limits the consequences of accidents. Each applicant to the Nuclear Regulatory Commission for a license to operate a nuclear power generating station has the responsibility to assure himself and others that this document, if used, is pertinent to his application and that the integrated performance of his station is adequate

Account of requirements for modernization in VPBER-600 enhanced safety reactor instrumentation and control system development

International Nuclear Information System (INIS)

Shashkin, S.L.; Pobedonostsev, A.B.; Drumov, V.V.; Chudin, A.G.

1993-01-01

Nuclear power plant (NPP) with VPBER-600 reactor is a station of new generation. The specified term of reactor plant operation is 60 years and taking into account that the proposed term of starting the first power unit is on the turn of centuries one can definitely state that for Russia conditions VPBER-600 is a plant of 21 century. Such far removed term for NPP now in the stage of development as it can seem does not put the problems of modernization as first order tasks. But open-quotes...who does not think about future lives in the past.close quotes It is that the NPP instrumentation and control (I ampersand C) systems are in the most degree subjected to the influence of factors which favor their modifications. These factors can be arbitrarily divided into two groups: (1) inner factors, i.e. changes (failures, aging, etc) in I ampersand C components as well as changes dictated by technological reasons (change of equipment composition, control algorithms, operation modes); (2) outer factors, i.e. intensive development of information technologies and rapid improvement of electronic components. This presentation addresses the problem of modernization of the safety instrumentation for this next generation facility, and the research effort it will entail. The system is designed to allow for modernization, and the relatively easy adoption of new instrumentation and technology as it becomes available

75 FR 12165 - Class E Airspace; Batesville, AR

Science.gov (United States)

2010-03-15

...-1177; Airspace Docket No. 09-ASW-34] Class E Airspace; Batesville, AR AGENCY: Federal Aviation... Class E airspace at Batesville, AR. Decommissioning of the Independence County non-directional beacon... for standard instrument approach procedures at Batesville Regional Airport, Batesville, AR. Airspace...

Instrumentation for Nuclear Applications

International Nuclear Information System (INIS)

1998-01-01

The objective of this project was to develop and coordinate nuclear instrumentation standards with resulting economies for the nuclear and radiation fields. There was particular emphasis on coordination and management of the Nuclear Instrument Module (NIM) System, U.S. activity involving the CAMAC international standard dataway system, the FASTBUS modular high-speed data acquisition and control system and processing and management of national nuclear instrumentation and detector standards, as well as a modest amount of assistance and consultation services to the Pollutant Characterization and Safety Research Division of the Office of Health and Environmental Research. The principal accomplishments were the development and maintenance of the NIM instrumentation system that is the predominant instrumentation system in the nuclear and radiation fields worldwide, the CAMAC digital interface system in coordination with the ESONE Committee of European Laboratories, the FASTBUS high-speed system and numerous national and international nuclear instrumentation standards

Instrumentation of steam cycle HTR's up to 900 MWe

International Nuclear Information System (INIS)

Leithner, D.E.; Winkenbach, B.

1982-06-01

Due to basic design features and inherent safety qualities in-core instrumentation is not needed in an HTR. Reactor safety requirements can be met by integral measurements. A modest spatial resolving power of the out-of-core instrumentation is sufficient for all operational purposes in small and medium sized steam cycle HTR's. Thus, the instrumentation concept of the THTR 300 MWe prototype reactor can be adopted without major changes for the HTR 450 MWe reactor project, as is demonstrated here for the neutron flux and temperature measurements. (author)

Systematic evaluation program review of NRC Safety Topic VI-10.A associated with the electrical, instrumentation and control portions of the testing of reactor trip system and engineered safety features, including response time for the Dresden station, Unit II nuclear power plant

International Nuclear Information System (INIS)

St Leger-Barter, G.

1980-11-01

This report documents the technical evaluation and review of NRC Safety Topic VI-10.A, associated with the electrical, instrumentation, and control portions of the testing of reactor trip systems and engineered safety features including response time for the Dresden II nuclear power plant, using current licensing criteria

Technical basis for instrumentation and control design improvements in WWER-440/230 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

International Nuclear Information System (INIS)

1996-01-01

Instrumentation and control (I and C) has been recognized as an area which requires substantial improvements in WWER NNPs, particularly for model 230 plants. Under contract with the IAEA the Spanish company Empresarios Agrupados (EA) developed a basic document proposing a technical basis for improvements related to the following most significant aspects of I and C: criteria for safety classification; remote shutdown panel; I and C support to operation and control room design; instrumentation set point margins; accident monitoring instrumentation. This publication is derived from the original report of EA which was circulated by the IAEA for review by staff members and experts from various Member States. It was finally agreed upon at a Consultants' meeting convened by the IAEA in Vienna in May 1994 with the participation of experts from France, Germany and Spain. The guidance expressed in this report is based on the IAEA/NUSS standards, safety guides and practices, and on regulations in use in various Member States. It is proposed as a way of carrying out the necessary studies to improve safety by upgrading the vital part of instrumentation an control in WWER-440 model 230 nuclear power plants. 28 refs, 3 figs

Probabilistic safety assessment for digital instrumentation and control systems in nuclear power plants - a review

International Nuclear Information System (INIS)

Lu, L.; Jiang, J.

2003-01-01

Deregulation in electricity market has created a great deal of challenges for nuclear power industries [1]. To stay competitive, Nuclear Power Plants (NPPs) will have to find ways to reduce their operational costs and to improve the plant safety. Instrumentation and Control (I and C) systems play an important role in this regard. Thus, new methodologies need to be developed to manage the operation of I and C systems more economically without jeopardizing the overall plant safety. Probabilistic Safety Assessment (PSA) technique is one of the promising methods to deal with such an issue, because PSA analyzes various system operational issues from a probabilistic sense, rather than a worst-case approach. However, there are several limitations when PSA is applied to I and C systems directly. A possible solution to this problem can be found by incorporating PSA with several other approaches. To better understand the issues involved, an attempt has been made in this paper to carry out a literature survey on this and related subject, particularly the effort will be made on: 1) the development of digital I and C systems in NPP, 2) PSA and its potential benefits and limitations, and 3) applications of PSA in various aspects of I and C systems including the resource allocation, the determination of surveillance testing strategies and the design of I and C systems. Finally, some solutions to overcome the aforementioned obstacles when applying PSA in I and C systems are also examined critically. (author)

Probabilistic safety assessment for instrumentation and control systems in nuclear power plants. A literature survey

International Nuclear Information System (INIS)

Lu, Lixuan; Jiang, Jin

2003-01-01

Deregulation in electricity market will create a great deal of challenges for Nuclear Power Plants (NPP). To stay competitive, NPP will need to find new ways to reduce their operation costs. In NPP, Instrumentation and Control (I and C) systems play an important role in reducing the cost of producing electricity while maintaining and/or enhancing safety. Therefore, it is extremely important that one should manage the I and C systems more efficiently and economically. Meanwhile, obsolescence problem associated with I and C systems encouraged the usage of advanced digital techniques in I and C systems. Thus, new methodologies are needed to analyze the reliability and determine the maintenance strategy for the digital I and C systems. Probabilistic Safety Assessment (PSA) has been probed to be a promising method to deal with this issue. This paper provides a literature survey on the development of digital I and C systems in NPP, followed by a detailed review of PSA including its benefits, limitations and the future direction of its development. Most importantly, potential applications of PSA in various aspects of I and C systems are brought into perspective throughout the paper. Furthermore, the applicability of PSA in the regulation of safety-related I and C systems is demonstrated. Detailed information on PSA applications in 1) the resource allocation for I and C systems: 2) the determination of surveillance testing strategies; and 3) I and C system designs, is provided. (author)

Traceability of radiation protection instruments

Science.gov (United States)

Hino, Y.; Kurosawa, T.

2007-08-01

Radiation protection instruments are used in daily measurement of dose and activities in workplaces and environments for safety management. The requirements for calibration certificates with traceability are increasing for these instruments to ensure the consistency and reliabilities of the measurement results. The present traceability scheme of radiation protection instruments for dose and activity measurements is described with related IEC/ISO requirements. Some examples of desirable future calibration systems with recent new technologies are also discussed to establish the traceability with reasonable costs and reliabilities.

Instrumentation needs in LWR severe fuel damage experiments

International Nuclear Information System (INIS)

McCormick, R.D.

1980-01-01

The Class 9 type nuclear accident is defined and the Three Mile Island type accident and proposed Idaho National Engineering Laboratory experiment series are described in some detail. Different types of severe fuel damage experiments are briefly discussed in order to show typical measurement requirements. General instrumentation needs and problems encountered in Class 9 accident research are outlined. It is concluded that the extremely high temperatures, high nuclear radiation fields, and oxidizing atmosphere will necessitate instrument development programs. Noncontact type sensing will be necessary in most of the molten core experiments

NASA Instrument Cost Model for Explorer-Like Mission Instruments (NICM-E)

Science.gov (United States)

Habib-Agahi, Hamid; Fox, George; Mrozinski, Joe; Ball, Gary

2013-01-01

NICM-E is a cost estimating relationship that supplements the traditional NICM System Level CERs for instruments flown on NASA Explorer-like missions that have the following three characteristics: 1) fly on Class C missions, 2) major development led and performed by universities or research foundations, and 3) have significant level of inheritance.

Qualifying commercial grade instruments for use in nuclear power generating stations

International Nuclear Information System (INIS)

Lamothe, R.J.; Scally, C.R.

1983-01-01

Nuclear environmental qualification of instrumentation has been successfully accomplished by many commercial grade equipment manufacturers. This paper was prepared as a guide to those manufacturers who want some insight into a qualification program. The areas addressed are the regulations and documents, the qualification program, and a case history of a chart recorder qualifications. The principal standards relating to a nuclear qualification program are IEEE Std. 323-1974 IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations, IEEE Std. 344-1975 IEEE Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations and 10CFR50.49. Previously NUREG 0588 Interim Staff Position on Environmental Qualification of Safety-Related Equipment. These define the intent and purpose of the qualification. The qualification program itself consists of several distinct parts which require explanation, including the determination of qualified life, choice of test samples, selection of appropriate acceptance criteria, aging program, radiation testing, seismic testing, abnormal environment tests and others. The case history illustrates the qualification program and the thought processes involved

Technical evaluation of the electrical, instrumentation, and control design aspects of the override of containment purge valve isolation and other engineered safety feature signals for the Fort Calhoun Nuclear Power Plant

International Nuclear Information System (INIS)

Hackett, D.B.

1980-01-01

This report documents the technical evaluation of the electrical, instrumentation, and control design aspects of the override of containment purge valve isolation and other engineered safety feature signals for the Fort Calhoun nuclear power plant. The review criteria are based on IEEE Std-279-1971 requirements for the safety signals to all purge and ventilation isolation valves. This report is supplied as part of the Selected Electrical, Instrumentation, and Control Systems Issues Program being conducted for the US Nuclear Regulatory Commission by Lawrence Livermore Laboratory

Class 2 piping rules in elevated temperature applications compared with Class 1 prescriptions for LMFBRs

International Nuclear Information System (INIS)

Capello, R.; Stretti, G.; Cesari, F.G.

1989-01-01

An LMFBR plant has many piping systems subjected to elevated temperature (> 427 o C) which, depending on their function and safety criteria, are classified as of quality level 1 or 2. The design of class 1 and class 2 piping for elevated temperatures is performed in accordance with ASME CCN-47 and CCN-253 respectively. This paper discusses what level of knowledge and analysis is necessary, to apply the rules of class 2 (CCN-253) rather than those of class 1 (CCN-47) for the design analysis of piping systems. From the designer viewpoint the burden of verification is much greater in class 1 than in class 2. This paper also examines the reliability of class 2 rules for elevated temperature when used to obtain structural results and justify the design of class 1 systems. In fact it can be shown that in some cases it is possible to design class 1 piping systems using class 2 rules. (author)

Digitizing instrumentation and control systems in nuclear power plants. DAtF autumn meeting Leittec '96, October 8, 1996 in Koenigswinter

International Nuclear Information System (INIS)

Aleite, W.

1997-01-01

Recently, digitization for upgrading and retrofitting of instrumentation and control systems has been extended to German nuclear power plants, and initial action to commence modification started with a very suitable system, the limiters of the Neckar-1 reactor unit of GKN. This action is generally welcomed. Systems of the control room of relevance to safety -even if not belonging to priority classes - are systems for process information for example, or operator guidance, as well as diagnostic systems for inspection and maintenance. (orig./DG) [de

75 FR 12162 - Class E Airspace; Manila, AR

Science.gov (United States)

2010-03-15

...-1184; Airspace Docket No. 09-ASW-39] Class E Airspace; Manila, AR AGENCY: Federal Aviation... Class E airspace at Manila, AR. Decommissioning of the Manila non-directional beacon (NDB) at Manila... instrument approach procedures at Manila Municipal Airport, Manila, AR. Airspace reconfiguration is necessary...

The impact of the instrumentation and control systems in the safety of a nuclear plant: a general vision; El impacto de los sistemas de instrumentacion y control en la seguridad de una planta nuclear: una vision general

Energy Technology Data Exchange (ETDEWEB)

Celis del Angel, L.; Rivero, T., E-mail: lina.celis@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2011-11-15

One of the fundamental components so much for the sure operation, like in emergency cases or accident are the equipment s and instrumentation and control systems. The nuclear industry has had some accidents where the instrumentation and control have played and important part: a wrong design, instrumentation lack, faulty systems of safety, etc. At the present time the necessity to modernize the instrumentation and control in a nuclear power plant is before the challenge of finding innovative forms to improve the competitiveness and readiness, reducing operation costs without put ing in risk the safety and reliability of the nuclear power plant. Most of the nuclear power plants require actualizing their instrumentation and control systems, here the digital systems represent a great alternative, improving the performance and the safety, increasing the readiness and reducing the maintenance s. However they require of strict tests that allow assuring their application in critical systems. It is also necessary, the development of modernization programs that allow the programmed substitution of the systems without affecting the readiness of the nuclear power plants. During this whole modernization process will be necessary to put special attention in the cyber-safety because the attacks every time they are more elaborated. Therefore will be necessary to go toward the modernization of the instrumentation and control with the challenge of making without detriment some in the safety of the normal operation and with response reliability in emergency conditions or accident that which represents an effort that should not be postponed in the case of the nuclear power plant of Laguna Verde. (Author)

Safety; Avertissement

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

This annual report of the Senior Inspector for the Nuclear Safety, analyses the nuclear safety at EDF for the year 1999 and proposes twelve subjects of consideration to progress. Five technical documents are also provided and discussed concerning the nuclear power plants maintenance and safety (thermal fatigue, vibration fatigue, assisted control and instrumentation of the N4 bearing, 1300 MW reactors containment and time of life of power plants). (A.L.B.)

Nuclear power plants - Instrumentation and control systems important for safety - Classification (International Electrotechnical Commission Standard Publication 1226:1993)

International Nuclear Information System (INIS)

Stefanik, J.

1996-01-01

This international standard established a method of classification of the information and command functions for nuclear power plants, and the I and C and equipment that provide those functions, into categories that designate the importance for safety of the functions, and the associated systems and equipment. The resulting classification then determines relevant design criteria. The design criteria are the measures of quality by which the adequacy of each functions, and the associated systems and equipment in relation to its importance to plant safety is ensured. In this standard, the criteria are those of functionality, reliability, performance, environmental durability and quality assurance. This standard is applicable to all the information and command functions, and the instrumentation and control systems and equipment that provide those functions. The functions, systems and equipment under consideration provide automated protection, closed or open loop control, and information to the operating staff. They keep the NPP conditions inside the safe operating envelope and provide automatic actions, or enable manual actions, that mitigate accidents or prevent or minimize radioactive releases to the site or wider environment. The functions, and the associated systems and equipment that fulfill these roles safeguard the health and safety of the NPP operators and the public. This standard complements, and does not replace or supersede, the Safety Guides and Codes of Practice published by the International Atomic Energy Agency

High-temperature gas-cooled reactor steam-cycle/cogeneration lead plant. Plant Protection and Instrumentation System design description

International Nuclear Information System (INIS)

1983-01-01

The Plant Protection and Instrumentation System provides plant safety system sense and command features, actuation of plant safety system execute features, preventive features which maintain safety system integrity, and safety-related instrumentation which monitors the plant and its safety systems. The primary function of the Plant Protection and Instrumentation system is to sense plant process variables to detect abnormal plant conditions and to provide input to actuation devices directly controlling equipment required to mitigate the consequences of design basis events to protect the public health and safety. The secondary functions of the Plant Protection and Instrumentation System are to provide plant preventive features, sybsystems that monitor plant safety systems status, subsystems that monitor the plant under normal operating and accident conditions, safety-related controls which allow control of reactor shutdown and cooling from a remote shutdown area

Seismic instrumentation

International Nuclear Information System (INIS)

1984-06-01

RFS or Regles Fondamentales de Surete (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety, while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the Service Central de Surete des Installations Nucleaires, or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary, any RFS and specify, if need be, the terms under which a modification is deemed retroactive. The aim of this RFS is to define the type, location and operating conditions for seismic instrumentation needed to determine promptly the seismic response of nuclear power plants features important to safety to permit comparison of such response with that used as the design basis

Safety climate in Swiss hospital units: Swiss version of the Safety Climate Survey

Science.gov (United States)

Gehring, Katrin; Mascherek, Anna C.; Bezzola, Paula

2015-01-01

Abstract Rationale, aims and objectives Safety climate measurements are a broadly used element of improvement initiatives. In order to provide a sound and easy‐to‐administer instrument for the use in Swiss hospitals, we translated the Safety Climate Survey into German and French. Methods After translating the Safety Climate Survey into French and German, a cross‐sectional survey study was conducted with health care professionals (HCPs) in operating room (OR) teams and on OR‐related wards in 10 Swiss hospitals. Validity of the instrument was examined by means of Cronbach's alpha and missing rates of the single items. Item‐descriptive statistics group differences and percentage of ‘problematic responses’ (PPR) were calculated. Results 3153 HCPs completed the survey (response rate: 63.4%). 1308 individuals were excluded from the analyses because of a profession other than doctor or nurse or invalid answers (n = 1845; nurses = 1321, doctors = 523). Internal consistency of the translated Safety Climate Survey was good (Cronbach's alpha G erman = 0.86; Cronbach's alpha F rench = 0.84). Missing rates at item level were rather low (0.23–4.3%). We found significant group differences in safety climate values regarding profession, managerial function, work area and time spent in direct patient care. At item level, 14 out of 21 items showed a PPR higher than 10%. Conclusions Results indicate that the French and German translations of the Safety Climate Survey might be a useful measurement instrument for safety climate in Swiss hospital units. Analyses at item level allow for differentiating facets of safety climate into more positive and critical safety climate aspects. PMID:25656302

The Cosmology Large Angular Scale Surveyor (CLASS) Telescope Architecture

Science.gov (United States)

Chuss, David T.; Ali, Aamir; Amiri, Mandana; Appel, John W.; Araujo, Derek; Bennett, Charles L.; Boone, Fletcher; Chan, Manwei; Cho, Hsiao-Mei; Colazo, Felipe;

Meteorological instrumentation

International Nuclear Information System (INIS)

1982-06-01

RFS or ''Regles Fondamentales de Surete'' (Basic Safety Rules) applicable to certain types of nuclear facilities lay down requirements with which compliance, for the type of facilities and within the scope of application covered by the RFS, is considered to be equivalent to compliance with technical French regulatory practice. The object of the RFS is to take advantage of standardization in the field of safety , while allowing for technical progress in that field. They are designed to enable the operating utility and contractors to know the rules pertaining to various subjects which are considered to be acceptable by the ''Service Central de Surete des Installations Nucleaires'' or the SCSIN (Central Department for the Safety of Nuclear Facilities). These RFS should make safety analysis easier and lead to better understanding between experts and individuals concerned with the problems of nuclear safety. The SCSIN reserves the right to modify, when considered necessary any RFS and specify, if need be, the terms under which a modification is deemed retroactive. The purpose of this RFS is to specify the meteorological instrumentation required at the site of each nuclear power plant equipped with at least one pressurized water reactor

Comparing Ratings: In-Class (Paper) vs. out of Class (Online) Student Evaluations

Science.gov (United States)

Mau, Ronald R.; Opengart, Rose A.

2012-01-01

Student evaluations of teaching (SET) are used by institutions of higher learning in the tenure and promotion process and in awarding merit pay increases. The trend at some institutions has been towards using an online student assessment instrument (SAI) in lieu of the traditional paper-based, in-class assessment. This study examines the…

The safety and clinical outcomes of chemoembolization in child-pugh class C patients with hepatocellular carcinomas

Energy Technology Data Exchange (ETDEWEB)

Choi, Tae Won; Kim, Hyo Cheol; Lee, Jeong Hoon; Yu, Su Jong; Kang, Beom Sik; Hur, Sae Beom; Lee, Myung Su; Jae, Hwan Jun; Chung, Jin Wook [Seoul National University College of Medicine, Seoul National University Hospital, Seoul (Korea, Republic of)

2015-12-15

To evaluate the safety and clinical outcomes of chemoembolization in Child-Pugh class C patients with hepatocellular carcinomas (HCC). The study comprised 55 patients with HCC who were classified as Child-Pugh class C and who underwent initial chemoembolization between January 2003 and December 2012. Selective chemoembolization was performed in all technically feasible cases to minimize procedure-related complications. All adverse events within 30 days were recorded using the Common Terminology Criteria for Adverse Events (CTCAE). The tumor response to chemoembolization was evaluated using the modified Response Evaluation Criteria In Solid Tumors. Thirty (54.5%) patients were within the Milan criteria, and 25 (45.5%) were beyond. The mortality of study subjects at 30 days was 5.5%. Major complications were observed in five (9.1%) patients who were all beyond the Milan criteria: two hepatic failures, one hepatic encephalopathy, and two CTCAE grade 3 increases in aspartate aminotransferase/alanine aminotransferase abnormality. The mean length of hospitalization was 6.3 ± 8.3 days (standard deviation), and 18 (32.7%) patients were discharged on the next day after chemoembolization. The tumor responses of the patients who met the Milan criteria were significantly higher (p = 0.014) than those of the patients who did not. The overall median survival was 7.1 months (95% confidence interval: 4.4-9.8 months). Even in patients with Child-Pugh class C, chemoembolization can be performed safely with a selective technique in selected cases with a small tumor burden.

Seismic instrumentation for nuclear power plants

International Nuclear Information System (INIS)

Senne Junior, M.

1983-01-01

A seismic instrumentation system used in Nuclear Power Plants to monitor the design parameters of systems, structures and components, needed to provide safety to those Plants, against the action of earthquakes is described. The instrumentation described is based on the nuclear standards in force. The minimum amount of sensors and other components used, as well as their general localization, is indicated. The operation of the instrumentation system as a whole and the handling of the recovered data are dealt with accordingly. The various devices used are not covered in detail, except for the accelerometer, which is the seismic instrumentation basic component. (Author) [pt

The Cosmology Large Angular Scale Surveyor (CLASS)

Science.gov (United States)

Cleary, Joseph

2018-01-01

The Cosmology Large Angular Scale Surveyor (CLASS) is an array of four telescopes designed to measure the polarization of the Cosmic Microwave Background. CLASS aims to detect the B-mode polarization from primordial gravitational waves predicted by cosmic inflation theory, as well as the imprint left by reionization upon the CMB E-mode polarization. This will be achieved through a combination of observing strategy and state-of-the-art instrumentation. CLASS is observing 70% of the sky to characterize the CMB at large angular scales, which will measure the entire CMB power spectrum from the reionization peak to the recombination peak. The four telescopes operate at frequencies of 38, 93, 145, and 217 GHz, in order to estimate Galactic synchrotron and dust foregrounds while avoiding atmospheric absorption. CLASS employs rapid polarization modulation to overcome atmospheric and instrumental noise. Polarization sensitive cryogenic detectors with low noise levels provide CLASS the sensitivity required to constrain the tensor-to-scalar ratio down to levels of r ~ 0.01 while also measuring the optical depth the reionization to sample-variance levels. These improved constraints on the optical depth to reionization are required to pin down the mass of neutrinos from complementary cosmological data. CLASS has completed a year of observations at 38 GHz and is in the process of deploying the rest of the telescope array. This poster provides an overview and update on the CLASS science, hardware and survey operations.

Seismic instrumentation for nuclear power plants

International Nuclear Information System (INIS)

Senne Junior, M.

1983-07-01

A seismic instrumentation system used in Nuclear Power Plants to monitor the design parameters of systems, structures and components, needed to provide safety to those plants, against the action of earth quarks is described. The instrumentation is based on the nuclear standards and other components used, as well as their general localization is indicated. The operation of the instrumentation system as a whole and the handling of the recovered data are dealt with accordingly. The accelerometer is described in detail. (Author) [pt

The status of safety in the public high school chemistry laboratories in Mississippi

Science.gov (United States)

Lacy, Sarah Louise Trotman

Since laboratory-based science courses have become an essential element of any science curriculum and are required by the Mississippi Department of Education for graduation, the chemistry laboratories in the public high schools in Mississippi must be safe. The purpose of this study was to determine: the safety characteristics of a high school chemistry laboratory; the perceived safety characteristics of the chemistry laboratories in public high schools in Mississippi; the basic safety knowledge of chemistry teachers in public high schools in Mississippi, where chemistry teachers in Mississippi gain knowledge about laboratory safety and instruction; if public high school chemistry laboratories in Mississippi adhere to recommended class size, laboratory floor space per student, safety education, safety equipment, and chemical storage; and the relationship between teacher knowledge of chemistry laboratory safety and the safety status of the laboratory in which they teach. The survey instrument was composed of three parts. Part I Teacher Knowledge consisted of 23 questions concerning high school chemistry laboratory safety. Part II Chemistry Laboratory Safety Information consisted of 40 items divided into four areas of interest concerning safety in high school chemistry laboratories. Part III Demographics consisted of 11 questions relating to teacher certification, experience, education, and safety training. The survey was mailed to a designated chemistry teacher in every public high school in Mississippi. The responses to Part I of the survey indicated that the majority of the teachers have a good understanding of knowledge about chemistry laboratory safety but need more instruction on the requirements for a safe high school chemistry laboratory. Less than 50% of the responding teachers thought they had received adequate preparation from their college classes to conduct a safe chemistry laboratory. According to the responses of the teachers, most of their high school

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

Milestones on the way to a reconfigurable automotive instrument cluster

Science.gov (United States)

Knoll, Peter M.; Kosmowski, Bogdan B.

2002-06-01

Nowadays, the car driver are faced with a rapidly increasing flood of information. In addition to established information systems (car radio, vehicle monitoring, mobile phones), high class vehicles feature navigation systems almost as standard. In the current decade, driver assistance and collision avoidance systems will appear in vehicles. Hence, there is an increasing demand for supplying the driver with more information that help him to drive safer and more economical. The price decline in the computer market and the availability of powerful graphic hard- and software concepts make it possible to enhance the classical functions of the instrument board to an interactive multifunctional information panel - an interface between information systems of the car and the driver. Therefore, the question of additional visual and cognitive stress, and a possible distraction of the driver by the large amount of information, and its complexity becomes predominant. Reconfigurable instruments, based on a microprocessor controlled active matrix color display, provide a powerful alternative to the usual mechanical/electromechanical instrument clusters in vehicles. They will help to strengthen passive safety, they adapt to user and situation requirements, and they are easy to install, to configure, and to maintain. Reconfigurable instruments in future cars will have a high impact on traffic since they can provide the driver with much more information, presenting it in a way that is flexibly matched to the importance of particular data and to the ergonomic properties of the driver. The functions are manifold and span from classical driver information like speed to navigation prompts and ultimately to video and multimedia access.

Assessing hospitals' clinical risk management: Development of a monitoring instrument

Directory of Open Access Journals (Sweden)

Pfeiffer Yvonne

2010-12-01

Full Text Available Abstract Background Clinical risk management (CRM plays a crucial role in enabling hospitals to identify, contain, and manage risks related to patient safety. So far, no instruments are available to measure and monitor the level of implementation of CRM. Therefore, our objective was to develop an instrument for assessing CRM in hospitals. Methods The instrument was developed based on a literature review, which identified key elements of CRM. These elements were then discussed with a panel of patient safety experts. A theoretical model was used to describe the level to which CRM elements have been implemented within the organization. Interviews with CRM practitioners and a pilot evaluation were conducted to revise the instrument. The first nationwide application of the instrument (138 participating Swiss hospitals was complemented by in-depth interviews with 25 CRM practitioners in selected hospitals, for validation purposes. Results The monitoring instrument consists of 28 main questions organized in three sections: 1 Implementation and organizational integration of CRM, 2 Strategic objectives and operational implementation of CRM at hospital level, and 3 Overview of CRM in different services. The instrument is available in four languages (English, German, French, and Italian. It allows hospitals to gather comprehensive and systematic data on their CRM practice and to identify areas for further improvement. Conclusions We have developed an instrument for assessing development stages of CRM in hospitals that should be feasible for a continuous monitoring of developments in this important area of patient safety.

Assessing hospitals' clinical risk management: Development of a monitoring instrument.

Science.gov (United States)

Briner, Matthias; Kessler, Oliver; Pfeiffer, Yvonne; Wehner, Theo; Manser, Tanja

2010-12-13

Clinical risk management (CRM) plays a crucial role in enabling hospitals to identify, contain, and manage risks related to patient safety. So far, no instruments are available to measure and monitor the level of implementation of CRM. Therefore, our objective was to develop an instrument for assessing CRM in hospitals. The instrument was developed based on a literature review, which identified key elements of CRM. These elements were then discussed with a panel of patient safety experts. A theoretical model was used to describe the level to which CRM elements have been implemented within the organization. Interviews with CRM practitioners and a pilot evaluation were conducted to revise the instrument. The first nationwide application of the instrument (138 participating Swiss hospitals) was complemented by in-depth interviews with 25 CRM practitioners in selected hospitals, for validation purposes. The monitoring instrument consists of 28 main questions organized in three sections: 1) Implementation and organizational integration of CRM, 2) Strategic objectives and operational implementation of CRM at hospital level, and 3) Overview of CRM in different services. The instrument is available in four languages (English, German, French, and Italian). It allows hospitals to gather comprehensive and systematic data on their CRM practice and to identify areas for further improvement. We have developed an instrument for assessing development stages of CRM in hospitals that should be feasible for a continuous monitoring of developments in this important area of patient safety.

AREVA advanced safety IC solutions and licensing experience for new nuclear builds and modernization projects - 15545

International Nuclear Information System (INIS)

Fourestie, B.; Pickelmann, J.; Richter, S.; Hilsenkopf, P.; Paris, P.

2015-01-01

Regulatory requirements for the Instrumentation and Control (IC) for Nuclear Power Plants have become significantly more stringent during the last 10 years in the areas of software development and qualification, traceability, diversity, or seismic requirements for instance, and with the introduction of new standards (such as the IEC 62566, or the IEC 62003). Based on a large and comprehensive experience gained from projects in several regulatory environments and different plant types (including non-OEM plants), AREVA has developed and adapted its processes and products to provide state-of-the-art IC solutions in full compliance with the regulatory demands and requirements in terms of robustness (independence, defense-in-depth, diversity and cyber-security). In this paper we present the safety IC platforms developed by AREVA. These platforms include TELEPERM XS as the computerized safety IC platform for class 1 system implementation, the Qualified Display System (QDS) for safety classified screen-based interface, and UNICORN as fully diverse analog safety IC platform for backup systems

Multilevel model of safety climate for furniture industries.

Science.gov (United States)

Rodrigues, Matilde A; Arezes, Pedro M; Leão, Celina P

2015-01-01

Furniture companies can analyze their safety status using quantitative measures. However, the data needed are not always available and the number of accidents is under-reported. Safety climate scales may be an alternative. However, there are no validated Portuguese scales that account for the specific attributes of the furniture sector. The current study aims to develop and validate an instrument that uses a multilevel structure to measure the safety climate of the Portuguese furniture industry. The Safety Climate in Wood Industries (SCWI) model was developed and applied to the safety climate analysis using three different scales: organizational, group and individual. A multilevel exploratory factor analysis was performed to analyze the factorial structure. The studied companies' safety conditions were also analyzed. Different factorial structures were found between and within levels. In general, the results show the presence of a group-level safety climate. The scores of safety climates are directly and positively related to companies' safety conditions; the organizational scale is the one that best reflects the actual safety conditions. The SCWI instrument allows for the identification of different safety climates in groups that comprise the same furniture company and it seems to reflect those groups' safety conditions. The study also demonstrates the need for a multilevel analysis of the studied instrument.

Mechanical Property Characteristics of Butt-Fusion Joint of High Density Polyethylene Pipe for NPP Safety Class Application

International Nuclear Information System (INIS)

Oh, Youngjin; Kim, Kyoungsu; Lee, Seunggun; Park, Heungbae; Yu, Jeongho; Kim, Jongsung; Kim, Jeonghyun; Jang, Changheui; Choi, Sunwoong

2013-01-01

Several NPPs in United States replaced parts of sea water or raw water system pipes to HDPE (high density polyethylene) pipes, which have outstanding resistance for oxidation and seismic loading. ASME B and PV code committee developed Code Case N-755, which describes rules for the construction of Safety Class 3 polyethylene pressure piping components. Several NPP's in US proposed relief requests in order to apply Code Case N-755. Although US NRC permitted using Code Case N-755 and HDPE materials for Class 3 buried piping, their permission was limited to only 10 years because of several concerns for material performance of HDPE. US NRC's major concerns are about material properties and the quality of fusion zone of HDPE. In this study, material property tests for HDPE fusion zone are conducted with varying standard fusion procedures. Mechanical property tests for fused material for HDPE pipes were conducted. Fused material shows lower toughness than base material and fused material of lower fusion pressure shows higher toughness than that of higher fusion pressure

Survey and evaluation of inherent safety characteristics and passive safety systems for use in probabilistic safety analyses

International Nuclear Information System (INIS)

Wetzel, N.; Scharfe, A.

1998-01-01

The present report examines the possibilities and limits of a probabilistic safety analysis to evaluate passive safety systems and inherent safety characteristics. The inherent safety characteristics are based on physical principles, that together with the safety system lead to no damage. A probabilistic evaluation of the inherent safety characteristic is not made. An inventory of passive safety systems of accomplished nuclear power plant types in the Federal Republic of Germany was drawn up. The evaluation of the passive safety system in the analysis of the accomplished nuclear power plant types was examined. The analysis showed that the passive manner of working was always assumed to be successful. A probabilistic evaluation was not performed. The unavailability of the passive safety system was determined by the failure of active components which are necessary in order to activate the passive safety system. To evaluate the passive safety features in new concepts of nuclear power plants the AP600 from Westinghouse, the SBWR from General Electric and the SWR 600 from Siemens, were selected. Under these three reactor concepts, the SWR 600 is specially attractive because the safety features need no energy sources and instrumentation in this concept. First approaches for the assessment of the reliability of passively operating systems are summarized. Generally it can be established that the core melt frequency for the passive concepts AP600 and SBWR is advantageous in comparison to the probabilistic objectives from the European Pressurized Water Reactor (EPR). Under the passive concepts is the SWR 600 particularly interesting. In this concept the passive systems need no energy sources and instrumentation, and has active operational systems and active safety equipment. Siemens argues that with this concept the frequency of a core melt will be two orders of magnitude lower than for the conventional reactors. (orig.) [de

Modeling safety instrumented systems with MooN voting architectures addressing system reconfiguration for testing

International Nuclear Information System (INIS)

Torres-Echeverria, A.C.; Martorell, S.; Thompson, H.A.

2011-01-01

This paper addresses the modeling of probability of dangerous failure on demand and spurious trip rate of safety instrumented systems that include MooN voting redundancies in their architecture. MooN systems are a special case of k-out-of-n systems. The first part of the article is devoted to the development of a time-dependent probability of dangerous failure on demand model with capability of handling MooN systems. The model is able to model explicitly common cause failure and diagnostic coverage, as well as different test frequencies and strategies. It includes quantification of both detected and undetected failures, and puts emphasis on the quantification of common cause failure to the system probability of dangerous failure on demand as an additional component. In order to be able to accommodate changes in testing strategies, special treatment is devoted to the analysis of system reconfiguration (including common cause failure) during test of one of its components, what is then included in the model. Another model for spurious trip rate is also analyzed and extended under the same methodology in order to empower it with similar capabilities. These two models are powerful enough, but at the same time simple, to be suitable for handling of dependability measures in multi-objective optimization of both system design and test strategies for safety instrumented systems. The level of modeling detail considered permits compliance with the requirements of the standard IEC 61508. The two models are applied to brief case studies to demonstrate their effectiveness. The results obtained demonstrated that the first model is adequate to quantify time-dependent PFD of MooN systems during different system states (i.e. full operation, test and repair) and different MooN configurations, which values are averaged to obtain the PFD avg . Also, it was demonstrated that the second model is adequate to quantify STR including spurious trips induced by internal component failure and

Multi-objective optimization of design and testing of safety instrumented systems with MooN voting architectures using a genetic algorithm

International Nuclear Information System (INIS)

Torres-Echeverría, A.C.; Martorell, S.; Thompson, H.A.

2012-01-01

This paper presents the optimization of design and test policies of safety instrumented systems using MooN voting redundancies by a multi-objective genetic algorithm. The objectives to optimize are the Average Probability of Dangerous Failure on Demand, which represents the system safety integrity, the Spurious Trip Rate and the Lifecycle Cost. In this way safety, reliability and cost are included. This is done by using novel models of time-dependent probability of failure on demand and spurious trip rate, recently published by the authors. These models are capable of delivering the level of modeling detail required by the standard IEC 61508. Modeling includes common cause failure and diagnostic coverage. The Probability of Failure on Demand model also permits to quantify results with changing testing strategies. The optimization is performed using the multi-objective Genetic Algorithm NSGA-II. This allows weighting of the trade-offs between the three objectives and, thus, implementation of safety systems that keep a good balance between safety, reliability and cost. The complete methodology is applied to two separate case studies, one for optimization of system design with redundancy allocation and component selection and another for optimization of testing policies. Both optimization cases are performed for both systems with MooN redundancies and systems with only parallel redundancies. Their results are compared, demonstrating how introducing MooN architectures presents a significant improvement for the optimization process.

The installation and operation of the seismic instrumentation in Korean NPPs

International Nuclear Information System (INIS)

Lee, Kye Hyun; Baek, Yong Lak; Chung, Yun Suk

1994-01-01

Including the 7 October, 1978, Hongsung earthquake, many earthquakes have occurred in our country. The Korean peninsular is no longer a safety zone against earthquakes, and there are possibilities of the damage they cause. So therefore, it is essential to verify the safety of the safety-related facilities in the event of an earthquake. If an earthquake occurs, seismic instrumentation provides information on the vibratory ground motion and resultant vibratory responses of representative safety-related structures and equipment so that an evaluation can be made immediately as to whether or not the design response spectra have been exceeded. In this paper, general descriptions of the seismic instrumentation installed in domestic NPPs will be discussed; this includes instrument type and location, the Operating Basis Earthquake (OBE) exceedance criteria, and processing and evaluation of earthquake response data, and items to be studied for further enhancement of post-earthquake evaluation techniques are presented

Texas Instruments : Veiligheid is niet iets om over te stemmen

NARCIS (Netherlands)

Blijswijk, M. van; Pennekamp, E.

1990-01-01

In dit artikel wordt het VGW-beleid bij Texas Instruments beschreven. Hiertoe zijn interviews gehouden met B. Veekamp, hoofd opleidingen bij Texas Instruments Holland BV (TIH) en de J. Stapel, voorzitter van de VGW-commissie. Occupational health and safety policy of Texas Instruments Holland B.V.

Characteristics of the safety climate in teams with world-class safety ...

African Journals Online (AJOL)

Accidents and incidents in the construction environment are not reduced or eliminated effectively, despite numerous efforts made to improve health and safety in the industry. An extensive field of research has been conducted on how teams in the construction environment interact to deliver a project successfully in terms of ...

A escolarização das classes abastadas The schooling of the affluent classes

Directory of Open Access Journals (Sweden)

Antonio David Cattani

2007-12-01

Full Text Available Após indicar a inadequação do termo elite ou burguesia para designar os detentores de grandes fortunas, este artigo sustenta que as classes dominantes se constroem continuamente e se mobilizam de todas as formas para assegurar sua reprodução ampliada, sua existência cotidiana com vistas à preservação e à transmissão das posições dominantes para seus descendentes. A formação ideológica na família e o período de formação nas instituições escolares são parte importantes do processo de construção de classe. O artigo considera que os estudos sobre a escolarização das classes dedicam-se, de modo geral, à formação universal, com ênfase nos problemas que acometem a população menos privilegiada. Os estudos sobre a formação da classe dominante são recentes e apresentam resultados inusitados tais como a relação instrumental com a educação o que distinguiria o caso brasileiro das estratégias das classes abastadas dos países economicamente mais avançados. Entretanto, como as classes dominantes são heterogêneas elas podem se valer de outras estratégias de escolarização para garantir suas posições e a reprodução de classe.After pointing out the inadequacy of the terms elite or bourgeoisie to label those in possession of great wealth, this article maintains that the dominant classes are constantly constructing and mobilizing themselves in every way to assure their extended reproduction and their everyday coexistence with the aim of preserving and transmitting dominant positions to their descendents. Ideological development within the family and the school years are important elements in the process of class construction. Studies on schooling of class generally address universal education, stressing the problems that afflict the underprivileged population. The education of the dominant class is not often explored as a topic and the few studies available present original results, such as the instrumental

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

International Nuclear Information System (INIS)

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

2002-01-01

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

Calibration of UV instruments and limitations on accuracy

International Nuclear Information System (INIS)

Clare, J.F.; Hamlin, J.D.

1993-01-01

Instruments measuring UV radiation may be classified as either spectrometers or broadband monitors; whilst the former determine irradiance as a function of wavelength the latter measure a summation of spectral irradiance weighted by some instrument response function which may be designed to approximate a desired action spectrum. For both classes a proper calibration requires the determination of the instrument's absolute spectral responsivity across the relevant wave-band together with an adequate determination of the wavelengths involved. (author). 7 refs

Study on Instrument Fault Detection using OLM Techniques for PHM Application in NPPs

Energy Technology Data Exchange (ETDEWEB)

Kim, Jae Hwan; Park, Gee Yong; Kim, Jung Taek; Hur, Seop [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-05-15

The diagnosis system is relatively being mature owing to many research. Among the various models, this paper introduces some On-Line Monitoring (OLM) models for instrument health monitoring and review applicability on NPPs. In recent years, many researchers are being focused on the prognostics which is predicting the future failure of instruments or equipment by using the status monitoring data. By using the prognostic techniques, we can expect a lot of advantages such as ease of control, power optimization, or optimal use of maintenance resources. And we have performed the test for detecting fault of safety-critical instruments and analyzed the fault detection sensitivity for various instrument failure modes using OLM techniques. OLM techniques using data-driven based model such AAKR or AANN can be useful tools for securing integrity of safety-critical instrument that should always keep healthy conditions for the plant safety.

21 CFR 880.6150 - Ultrasonic cleaner for medical instruments.

Science.gov (United States)

2010-04-01

... instruments by the emission of high frequency soundwaves. (b) Classification. Class I. The device, including any solutions intended for use with the device for cleaning and sanitizing the instruments, is exempt from the premarket notification procedures in subpart E of part 807 of this chapter, subject to the...

76 FR 39038 - Proposed Establishment of Class E Airspace; Lebanon, PA

Science.gov (United States)

2011-07-05

...-0558; Airspace Docket No. 11-AEA-13] Proposed Establishment of Class E Airspace; Lebanon, PA AGENCY... action proposes to establish Class E Airspace at Lebanon, PA, to accommodate new Standard Instrument... amendment to Title 14, Code of Federal Regulations (14 CFR) part 71 to establish Class E airspace at Lebanon...

RISK MANAGEMENT AS TRANSPORTATION SAFETY PROVISION INSTRUMENT IN RUSSIA

OpenAIRE

V. A. Nikolayev

2012-01-01

Safety of transportation in Russia is subject to a variety of threats. Discussed in the article are characteristics of major threats to transportation security. State transportation policy directions that make it possible to ensure the security of cargo and passenger transportation are shown. A listof activities and innovative risk management tools that provide for improved safety of railway transportation is proposed.

CERCA's fuel elements instrumentation manufacturing

International Nuclear Information System (INIS)

Harbonnier, G.; Jarousse, C.; Pin, T.; Febvre, M.; Colomb, P.

2005-01-01

When research and test reactors wish to further understand the Fuel Elements behavior when operating as well as mastering their irradiation conditions, operators carry out neutron and thermo hydraulic analysis. For thermal calculation, the codes used have to be preliminary validated, at least in the range of the reactor safety operational limits. When some further investigations are requested either by safety authorities or for its own reactor needs, instrumented tools are the ultimate solution for providing representative measurements. Such measurements can be conducted for validating thermal calculation codes, at nominal operating condition as well as during transients ones, or for providing numerous and useful data in the frame of a new products qualification program. CERCA, with many years of experience for implanting thermocouples in various products design, states in this poster his manufacturing background on instrumented elements, plates or targets. (author)

Natural radioactivity of bedrock bath instruments and hot spring instruments in Japan

International Nuclear Information System (INIS)

Kazuki Iwaoka; Hiroyuki Tabe; Hidenori Yonehara

2013-01-01

In Japan, bedrock bath instruments and hot spring instruments that contain natural radioactive nuclides are commercially available. In this study, such instruments containing natural radioactive nuclides, currently distributed in Japan, were collected and the radioactivity concentration of 238 U series, 232 Th series, and 40 K in them was determined by gamma ray spectrum analyses. Effective doses to workers and general consumers handling the materials were estimated, revealing the radioactivity concentration of 238 U series, 232 Th series, and 40 K to be lower than critical values given in the IAEA Safety Guide. The maximum effective doses to workers and general consumers were 210 and 6.1 μSv y -1 , respectively. These values are lower than the intervention exemption level (1,000 μSv y -1 ) given in ICRP Publ. 82. (author)

Walkdown procedure: Seismic adequacy review of safety class 3 ampersand 4 commodities in 2736-Z ampersand ZB buildings at PFP facility

International Nuclear Information System (INIS)

Ocoma, E.C.

1995-01-01

Seismic evaluation of existing safety class (SC) 3 and non-SC 4 commodities at the Plutonium Finishing Plant (PFP) is integrated into an area walkdown program. Field walkdowns of potential PFP seismic deficiencies associated with structural failure and falling will be performed using the DOE SQUG/EPRI methodology. Potential proximity interactions are also addressed. Objective of the walkdown is to qualify as much of the equipment as practical and to identify candidates for further evaluation

RISK MANAGEMENT AS TRANSPORTATION SAFETY PROVISION INSTRUMENT IN RUSSIA

Directory of Open Access Journals (Sweden)

V. A. Nikolayev

2012-01-01

Full Text Available Safety of transportation in Russia is subject to a variety of threats. Discussed in the article are characteristics of major threats to transportation security. State transportation policy directions that make it possible to ensure the security of cargo and passenger transportation are shown. A listof activities and innovative risk management tools that provide for improved safety of railway transportation is proposed.

Psychometric model for safety culture assessment in nuclear research facilities

Energy Technology Data Exchange (ETDEWEB)

Nascimento, C.S. do, E-mail: claudio.souza@ctmsp.mar.mil.br [Centro Tecnológico da Marinha em São Paulo (CTMSP), Av. Professor Lineu Prestes 2468, 05508-000 São Paulo, SP (Brazil); Andrade, D.A., E-mail: delvonei@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN – SP), Av. Professor Lineu Prestes 2242, 05508-000 São Paulo, SP (Brazil); Mesquita, R.N. de, E-mail: rnavarro@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN – SP), Av. Professor Lineu Prestes 2242, 05508-000 São Paulo, SP (Brazil)

2017-04-01

Highlights: • A psychometric model to evaluate ‘safety climate’ at nuclear research facilities. • The model presented evidences of good psychometric qualities. • The model was applied to nuclear research facilities in Brazil. • Some ‘safety culture’ weaknesses were detected in the assessed organization. • A potential tool to develop safety management programs in nuclear facilities. - Abstract: A safe and reliable operation of nuclear power plants depends not only on technical performance, but also on the people and on the organization. Organizational factors have been recognized as the main causal mechanisms of accidents by research organizations through USA, Europe and Japan. Deficiencies related with these factors reveal weaknesses in the organization’s safety culture. A significant number of instruments to assess the safety culture based on psychometric models that evaluate safety climate through questionnaires, and which are based on reliability and validity evidences, have been published in health and ‘safety at work’ areas. However, there are few safety culture assessment instruments with these characteristics (reliability and validity) available on nuclear literature. Therefore, this work proposes an instrument to evaluate, with valid and reliable measures, the safety climate of nuclear research facilities. The instrument was developed based on methodological principles applied to research modeling and its psychometric properties were evaluated by a reliability analysis and validation of content, face and construct. The instrument was applied to an important nuclear research organization in Brazil. This organization comprises 4 research reactors and many nuclear laboratories. The survey results made possible a demographic characterization and the identification of some possible safety culture weaknesses and pointing out potential areas to be improved in the assessed organization. Good evidence of reliability with Cronbach's alpha

Psychometric model for safety culture assessment in nuclear research facilities

International Nuclear Information System (INIS)

Nascimento, C.S. do; Andrade, D.A.; Mesquita, R.N. de

2017-01-01

Highlights: • A psychometric model to evaluate ‘safety climate’ at nuclear research facilities. • The model presented evidences of good psychometric qualities. • The model was applied to nuclear research facilities in Brazil. • Some ‘safety culture’ weaknesses were detected in the assessed organization. • A potential tool to develop safety management programs in nuclear facilities. - Abstract: A safe and reliable operation of nuclear power plants depends not only on technical performance, but also on the people and on the organization. Organizational factors have been recognized as the main causal mechanisms of accidents by research organizations through USA, Europe and Japan. Deficiencies related with these factors reveal weaknesses in the organization’s safety culture. A significant number of instruments to assess the safety culture based on psychometric models that evaluate safety climate through questionnaires, and which are based on reliability and validity evidences, have been published in health and ‘safety at work’ areas. However, there are few safety culture assessment instruments with these characteristics (reliability and validity) available on nuclear literature. Therefore, this work proposes an instrument to evaluate, with valid and reliable measures, the safety climate of nuclear research facilities. The instrument was developed based on methodological principles applied to research modeling and its psychometric properties were evaluated by a reliability analysis and validation of content, face and construct. The instrument was applied to an important nuclear research organization in Brazil. This organization comprises 4 research reactors and many nuclear laboratories. The survey results made possible a demographic characterization and the identification of some possible safety culture weaknesses and pointing out potential areas to be improved in the assessed organization. Good evidence of reliability with Cronbach's alpha

A Study on the Determination of Power Supply Class for HVAC System in KJRR

International Nuclear Information System (INIS)

Kim, Hagtae; Kim, Minjin; Suh, Yong-Suk; Kim, Jun-Yeon; Chae, Hee-Taek

2016-01-01

The purpose of this paper is to propose an appropriate electrical class, power supply class, and operation logic for the major equipment of the HVAC system such as a Confinement Isolation Damper (CID), Fission Molybdenum Isolation Damper (FID), Air Handling Unit (AHU), Air Cleaning Unit (ACU), and Contaminated Air Purification System (CAPS) in light of their functional requirements and importance. The classification for the overall HVAC system of the KJRR is a safety class NNS, Non-Seismic category, quality class S, and electrical class Non-1E. Exceptionally, the CID and FID are safety class 3, seismic category I, and quality class Q. The electrical class for the major equipment of the HVAC system should be determined considering the operation concept during Loss of Normal Electric Power (LOEP) regardless of the safety class. In this paper, the electrical and power supply class is determined and the operation logic is proposed for the major equipment of the HVAC system for the KJRR such as the CID, FID, CAPS, ACU, and AHU. The electrical class Non-1E is determined to implement a fail closed for the enhancement of safety. The power supply class is based on the functional requirements of each equipment. The CID, FID, CAPS, and ACU are Class III, but the AHU is Class IV by reflecting the importance and electrical load. After the recovery of the power supply, there is a difference in the operation concept for the HVAC system between the reactor building and fission molybdenum production building depending on the operator's residence time. The CID and CAPS are operated manually through procedures for checking the accident status, and the FID and ACU are operated automatically without special procedures

A Study on the Determination of Power Supply Class for HVAC System in KJRR

Energy Technology Data Exchange (ETDEWEB)

Kim, Hagtae; Kim, Minjin; Suh, Yong-Suk; Kim, Jun-Yeon; Chae, Hee-Taek [KAERI, Daejeon (Korea, Republic of)

2016-05-15

The purpose of this paper is to propose an appropriate electrical class, power supply class, and operation logic for the major equipment of the HVAC system such as a Confinement Isolation Damper (CID), Fission Molybdenum Isolation Damper (FID), Air Handling Unit (AHU), Air Cleaning Unit (ACU), and Contaminated Air Purification System (CAPS) in light of their functional requirements and importance. The classification for the overall HVAC system of the KJRR is a safety class NNS, Non-Seismic category, quality class S, and electrical class Non-1E. Exceptionally, the CID and FID are safety class 3, seismic category I, and quality class Q. The electrical class for the major equipment of the HVAC system should be determined considering the operation concept during Loss of Normal Electric Power (LOEP) regardless of the safety class. In this paper, the electrical and power supply class is determined and the operation logic is proposed for the major equipment of the HVAC system for the KJRR such as the CID, FID, CAPS, ACU, and AHU. The electrical class Non-1E is determined to implement a fail closed for the enhancement of safety. The power supply class is based on the functional requirements of each equipment. The CID, FID, CAPS, and ACU are Class III, but the AHU is Class IV by reflecting the importance and electrical load. After the recovery of the power supply, there is a difference in the operation concept for the HVAC system between the reactor building and fission molybdenum production building depending on the operator's residence time. The CID and CAPS are operated manually through procedures for checking the accident status, and the FID and ACU are operated automatically without special procedures.

Latest NASA Instrument Cost Model (NICM): Version VI

Science.gov (United States)

Mrozinski, Joe; Habib-Agahi, Hamid; Fox, George; Ball, Gary

2014-01-01

The NASA Instrument Cost Model, NICM, is a suite of tools which allow for probabilistic cost estimation of NASA's space-flight instruments at both the system and subsystem level. NICM also includes the ability to perform cost by analogy as well as joint confidence level (JCL) analysis. The latest version of NICM, Version VI, was released in Spring 2014. This paper will focus on the new features released with NICM VI, which include: 1) The NICM-E cost estimating relationship, which is applicable for instruments flying on Explorer-like class missions; 2) The new cluster analysis ability which, alongside the results of the parametric cost estimation for the user's instrument, also provides a visualization of the user's instrument's similarity to previously flown instruments; and 3) includes new cost estimating relationships for in-situ instruments.

Aviation Safety Issues Database

Science.gov (United States)

Morello, Samuel A.; Ricks, Wendell R.

2009-01-01

The aviation safety issues database was instrumental in the refinement and substantiation of the National Aviation Safety Strategic Plan (NASSP). The issues database is a comprehensive set of issues from an extremely broad base of aviation functions, personnel, and vehicle categories, both nationally and internationally. Several aviation safety stakeholders such as the Commercial Aviation Safety Team (CAST) have already used the database. This broader interest was the genesis to making the database publically accessible and writing this report.

76 FR 75449 - Establishment of Class E Airspace; Stuart, IA

Science.gov (United States)

2011-12-02

...-0831; Airspace Docket No. 11-ACE-17] Establishment of Class E Airspace; Stuart, IA AGENCY: Federal... for Stuart, IA, to accommodate new COPTER area navigation (RNAV) Standard Instrument Approach... Federal Register a notice of proposed rulemaking to establish Class E airspace for Stuart, IA, creating...

76 FR 73505 - Establishment of Class E Airspace; Nashville, AR

Science.gov (United States)

2011-11-29

...-0497; Airspace Docket No. 11-ASW-4] Establishment of Class E Airspace; Nashville, AR AGENCY: Federal... for Nashville, AR, to accommodate new Area Navigation (RNAV) Standard Instrument Approach Procedures... a notice of proposed rulemaking to amend Class E airspace for Nashville, AR, creating additional...

The stress and strain analysis research of class 1 eqnipments

International Nuclear Information System (INIS)

Ye Yuanwu; Tang Long; Wang Yueying; Qi Min; Yu Huajin

2008-01-01

The class 1 equipment is very important in the nuclear device, in the design and testing process required to carry out their stress and strain analysis, so as to ensure their safety. There are two ways to get stress and strain analysis of the class 1 equipment, the theoretical and experimental methods. Through theoretical method can get the stress and strain of the class 1 equipment, so as to provide a basis for the design of the equipment; through the experimental method to verify the accuracy of the theoretical methods and provide a basis for the safety assessment of the equipment. The main ressel of CEFR (China Experimental Fast Reactor) is the class 1 equipment. In this paper, according to the stress and strain analysis research of CEFR main vessel, the theories and expperimental methods of nuclear class 1 equipments stress and strain analysis has been described. (authors)

Monitoring human and organizational factors influencing common-cause failures of safety-instrumented system during the operational phase

International Nuclear Information System (INIS)

Rahimi, Maryam; Rausand, Marvin

2013-01-01

Safety-instrumented systems (SISs) are important safety barriers in many technical systems in the process industry. Reliability requirements for SISs are specified as a safety integrity level (SIL) with reference to the standard IEC 61508. The SIS reliability is often threatened by common-cause failures (CCFs), and the beta-factor model is the most commonly used model for incorporating the effects of CCFs. In the design phase, the beta-factor, β, is determined by answering a set of questions that is given in part 6 of IEC 61508. During the operational phase, there are several factors that influence β, such that the actual β differs from what was predicted in the design phase, and therefore the required reliability may not be maintained. Among the factors influencing β in the operational phase are human and organizational factors (HOFs). A number of studies within industries that require highly reliable products have shown that HOFs have significant influence on CCFs and therefore on β in the operational phase, but this has been neglected in the process industry. HOFs are difficult to predict, and susceptible to be changed during the operational phase. Without proper management, changing HOFs may cause the SIS reliability to drift out of its required value. The aim of this article is to highlight the importance of HOFs in estimation of β for SISs, and also to propose a framework to follow the HOFs effects and to manage them such that the reliability requirement can be maintained

Management system of instrument database

International Nuclear Information System (INIS)

Zhang Xin

1997-01-01

The author introduces a management system of instrument database. This system has been developed using with Foxpro on network. The system has some characters such as clear structure, easy operation, flexible and convenient query, as well as the data safety and reliability

78 FR 45848 - Amendment of Class E Airspace; Salt Lake City, UT

Science.gov (United States)

2013-07-30

...) and Instrument Landing System (ILS) or Localizer (LOC) standard instrument approach procedures at Salt...: Paragraph 6005 Class E airspace areas extending upward from 700 feet or more above the surface of the earth...

21 CFR 882.4560 - Stereotaxic instrument.

Science.gov (United States)

2010-04-01

...) Identification. A stereotaxic instrument is a device consisting of a rigid frame with a calibrated guide mechanism for precisely positioning probes or other devices within a patient's brain, spinal cord, or other part of the nervous system. (b) Classification. Class II (performance standards). ...

Enhancing Public Helicopter Safety as a Component of Homeland Security

Science.gov (United States)

2016-12-01

Risk Assessment Tool GPS Global Positioning System IFR instrument flight rules ILS instrument landing system IMC instrument meteorological...daily operations. Additionally, the effectiveness of the standards is evaluated by determining if these standards would have prevented the accidents...trends, such as human behavior and lack of standards, that are common in public safety helicopter accidents. Public safety aviation agencies can use this

76 FR 30532 - Amendment of Class D and E Airspace; Palmdale, CA

Science.gov (United States)

2011-05-26

... Class E Airspace at Palmdale, CA, to accommodate aircraft using Instrument Landing System (ILS.... Paragraph 6005 Class E airspace areas extending upward from 700 feet or more above the surface of the earth...

Seismic Instrumentation Placement Recommendations Report

International Nuclear Information System (INIS)

Kennedy, W.N.

1998-01-01

DOE Order 420.1, ''Facility Safety'', requires that facilities or sites with hazardous materials be provided with instrumentation or other means to detect and record the occurrences and severity of seismic events. These requirements assure that necessary records are available after an earthquake for evaluation purposes and to supplement other data to justify a facility restart or curtailing plant operations after an earthquake. This report documents the basis for the selection of Savannah River Site areas and existing facilities to be instrumented. The need to install instrumentation in new facilities such as the Actinide Packaging and Storage Facility, Commercial Light Water Reactor Tritium Extraction Facility and the Accelerator Production of Tritium Facility will be assessed separately

76 FR 59503 - Establishment of Class E Airspace; Lebanon, PA

Science.gov (United States)

2011-09-27

...-0558; Airspace Docket No. 11-AEA-13] Establishment of Class E Airspace; Lebanon, PA AGENCY: Federal... at Lebanon, PA, to accommodate new Standard Instrument Approach Procedures that have been developed... amend Class E airspace 700 feet above the surface, at Lebanon, PA (76 FR 39038). Subsequent to...

Safety aspects of NPP ageing

International Nuclear Information System (INIS)

1995-01-01

Preparation of safety practices on assessment and management of aging of major NPP components important to safety, CRP on management of aging of concrete containment buildings, CRP on management of aging of in-containment instrumentation and control cables are outlined

Upgrade of Dhruva fuel channel flow instrumentation

International Nuclear Information System (INIS)

Gadgil, Kaustubh; Awale, P.K.; Sengupta, C.; Sumanth, P.; Roy, Kallol

2014-01-01

Dhruva, a 100 MW Heavy Water moderated and cooled, vertical tank-type Research Reactor, using metallic natural Uranium fuel has flow instrumentation for all the 144 fuel channels, consisting of venturi and triplicate DP gauges for each fuel channel. These gauges provide contacts for generation of reactor trip on low flow through fuel channel. These DP gauges were facing numerous generic and ageing related failures over the years and was also difficult to maintain owing to obsolescence. While considering an upgrade for these DP gauges, it was also planned to replace the existing Coolant Low Flow Trip (CLFT) system with a computer based Reactor Trip Logic System (RTLS). Being a retrofit job, the existing panels for mounting the gauges, cable layout, impulse tubing layout, etc. were retained, thereby simplifying the site execution, reducing reactor down time and also reducing person-milli-Sievert consumption. A customized Electronic DP Indicating Switch (EDPIS) was conceptualized for achieving these objectives. Such a design, utilizing a standard DP transmitter with customized electronic circuitry, was developed, evaluated and finalized after a series of factory trials, field trials and prototyping. The instrument design included contact input for existing CLFT system and also provision for 4-20 mA current output for the proposed computer based RTLS. The display and form factor of the instrument remained identical to older one and ensures familiarity of O and M personnel. Since EDPIS is classified as Safety Class IA, stringent type tests, hardware FMEA and V and V of the micro-controller software were carried out as per the requirements laid down by relevant standards for qualification of these instruments. Being a customized instrument, the manufacturing process was closely monitored and was followed by stringent QA plan and acceptance tests. A total of 396 gauges were replaced in a phased manner during scheduled fuelling outages and thereby did not affect reactor

Verification of Safety Margins of Battery Banks Capacity of Class 1E DC System in a Nuclear Power Plant

International Nuclear Information System (INIS)

Lukman, Abdulrauf; Zhu, Oon-Pyo

2015-01-01

According to Ref 'Station blackout (SBO) is generally a plant condition with complete loss of all alternating current (AC) power from off-site sources, from the main generator and from standby AC power sources important to safety to the essential and nonessential switchgear buses. Direct current (DC) power supplies and uninterruptible AC power supplies may be available as long as batteries can supply the loads, alternate AC power supplies are available'. The above IAEA document indicated the importance of batteries during SBO. Prior to the Fukushima accident, most batteries might be designed with coping capability of four hours. However, the accident showed the need for the coping capability to be increased to at least eight hours. The purpose of this research is to verify the safety capacity margin of the nuclear qualified battery banks of class 1E DC system and test the response to SBO using the load profile of a Korean design nuclear power plant (NPP). The capacity margins of class 1E batteries of DC power system batteries in a nuclear power plant were determined using the load profile of the plant. It was observed that if appropriate manufacturer Kt data are not available, the accuracy of the battery capacity might not be accurately calculated. The result obtained shows that the batteries have the coping capability of two hours for channel A and B, and eight hours for channel C and D. Also capacity margin as show in figure show a reasonable margin for each batteries of the DC system

Page | 210 TOWARDS A CLASS ACTION UNDER RWANDAN LAW ...

African Journals Online (AJOL)

Fr. Ikenga

Under article 3 of the Rwandan code of civil procedure,1 a person may not institute a .... with a certain ECOCAS company Ltd for the purpose of terracing certain hills. .... Apart from informing class members of the class action, the notice given to all ... this way prior certification will serve as an instrument of justice rather than a ...

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

International Nuclear Information System (INIS)

1986-11-01

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

78 FR 47237 - Proposed Amendment of Class E Airspace; Chariton, IA

Science.gov (United States)

2013-08-05

...-0255; Airspace Docket No. 13-ACE-4] Proposed Amendment of Class E Airspace; Chariton, IA AGENCY... action proposes to amend Class E airspace at Chariton, IA. Decommissioning of the Chariton non... for standard instrument approach procedures at Chariton Municipal Airport, Chariton, IA. Airspace...

The "School Safety & Security Questionnaire": Middle Grades Students' Perceptions of Safety at School

Science.gov (United States)

Miller, Janice Williams; Nickell, Linda K.

2008-01-01

This study presents the development and basic psychometric characteristics of the "School Safety and Security Questionnaire" (SSSQ). This new measure was constructed to assess middle grade students' perceptions of safety and security during the school year. The content validity of the theoretically-based instrument was assessed and the measure was…

76 FR 15231 - Proposed Amendment of Class D and E Airspace; Palmdale, CA

Science.gov (United States)

2011-03-21

... using Instrument Landing System (ILS) Localizer (LOC) standard instrument approach procedures at.... Paragraph 6005 Class E Airspace areas extending upward from 700 feet or more above the surface of the earth...

Instrumentation utilisation for risk control in safety operations. [balloons and rockets

Science.gov (United States)

Swayer, F. R.

1987-01-01

Ways in which instrumentation is utilized for risk control for inherently safe (no control or guidance) and flight programmed launch vehicles is presented. Instrumentation and how it is utilized in the launching and recovery of balloons and payloads is also presented. Wind sensing, computer systems, tracking, and telemetry are discussed.

78 FR 27872 - Proposed Amendment of Class E Airspace; Salt Lake City, UT

Science.gov (United States)

2013-05-13

... System (GPS) and Instrument Landing System (ILS) or Localizer (LOC) standard instrument approach...: Paragraph 6005 Class E airspace areas extending upward from 700 feet or more above the surface of the earth...

75 FR 17637 - Proposed Amendment of Class E Airspace; Cherokee, IA

Science.gov (United States)

2010-04-07

...-0085; Airspace Docket No. 10-ACE-1] Proposed Amendment of Class E Airspace; Cherokee, IA AGENCY... action proposes to amend Class E airspace at Cherokee, IA. Decommissioning of the Pilot Rock non... for standard instrument approach procedures at Cherokee County Regional Airport, Cherokee, IA...

77 FR 71362 - Proposed Amendment of Class E Airspace; Decorah, IA

Science.gov (United States)

2012-11-30

...-1433; Airspace Docket No. 11-ACE-26] Proposed Amendment of Class E Airspace; Decorah, IA AGENCY... action proposes to amend Class E airspace at Decorah, IA. Decommissioning of the Decorah non-directional... instrument approach procedures at Decorah Municipal Airport, Decorah, IA. Airspace reconfiguration is...

78 FR 25231 - Proposed Establishment of Class E Airspace; Colt, AR

Science.gov (United States)

2013-04-30

...-1281; Airspace Docket No. 12-ASW-13] Proposed Establishment of Class E Airspace; Colt, AR AGENCY... action proposes to establish Class E airspace at Colt, AR. Controlled airspace is necessary to...-mile radius of Delta Regional Airport, Colt, AR, to accommodate new standard instrument approach...

Nuclear power plant systems, structures and components and their safety classification

International Nuclear Information System (INIS)

2000-01-01

The assurance of a nuclear power plant's safety is based on the reliable functioning of the plant as well as on its appropriate maintenance and operation. To ensure the reliability of operation, special attention shall be paid to the design, manufacturing, commissioning and operation of the plant and its components. To control these functions the nuclear power plant is divided into structural and functional entities, i.e. systems. A systems safety class is determined by its safety significance. Safety class specifies the procedures to be employed in plant design, construction, monitoring and operation. The classification document contains all documentation related to the classification of the nuclear power plant. The principles of safety classification and the procedures pertaining to the classification document are presented in this guide. In the Appendix of the guide, examples of systems most typical of each safety class are given to clarify the safety classification principles

Particle size distribution instrument. Topical report 13

Energy Technology Data Exchange (ETDEWEB)

Okhuysen, W.; Gassaway, J.D.

1995-04-01

The development of an instrument to measure the concentration of particles in gas is described in this report. An in situ instrument was designed and constructed which sizes individual particles and counts the number of occurrences for several size classes. Although this instrument was designed to detect the size distribution of slag and seed particles generated at an experimental coal-fired magnetohydrodynamic power facility, it can be used as a nonintrusive diagnostic tool for other hostile industrial processes involving the formation and growth of particulates. Two of the techniques developed are extensions of the widely used crossed beam velocimeter, providing simultaneous measurement of the size distribution and velocity of articles.

Road safety policy of the European Union.

NARCIS (Netherlands)

2013-01-01

The European Union (EU) is important for national road safety policies. The EU has several policymaking instruments, such as binding regulations and directives, and non-binding recommendations. An important element in the EU policy plans on road safety are the non-binding European road safety

Radiation safety and workers safety: partners instead of rivals

International Nuclear Information System (INIS)

Lambotte, S.; Severitt, S.; Sobetzko, T.; Voelker, T.

2008-01-01

It is shown how important and paying it is to look upon working systems as a whole with regard to danger and load at the working place, and to use existing synergies. At many places, a change of approach in this direction is still necessary, in order to recognize the connection between the various fields of operational safety as well as the potential that is hidden behind an effective utilization of the instruments for workers safety. (orig.)

Evolution and validation of a personal form of an instrument for assessing science laboratory classroom environments

Science.gov (United States)

Fraser, Barry J.; Giddings, Geoffrey J.; McRobbie, Campbell J.

The research reported in this article makes two distinctive contributions to the field of classroom environment research. First, because existing instruments are unsuitable for science laboratory classes, the Science Laboratory Environment Inventory (SLEI) was developed and validated. Second, a new Personal form of the SLEI (involving a student's perceptions of his or her own role within the class) was developed and validated in conjunction with the conventional Class form (involving a student's perceptions of the class as a whole), and its usefulness was investigated. The instrument was cross-nationally fieldtested with 5,447 students in 269 senior high school and university classes in six countries, and cross-validated with 1,594 senior high school students in 92 classes in Australia. Each SLEI scale exhibited satisfactory internal consistency reliability, discriminant validity, and factorial validity, and differentiated between the perceptions of students in different classes. A variety of applications with the new instrument furnished evidence about its usefulness and revealed that science laboratory classes are dominated by closed-ended activities; mean scores obtained on the Class form were consistently somewhat more favorable than on the corresponding Personal form; females generally held more favorable perceptions than males, but these differences were somewhat larger for the Personal form than the Class form; associations existed between attitudinal outcomes and laboratory environment dimensions; and the Class and Personal forms of the SLEI each accounted for unique variance in student outcomes which was independent of that accounted for by the other form.

Seismic qualification of safety-related instrumentation cabinets for nuclear generating stations

International Nuclear Information System (INIS)

Sauve, R.G.; Bell, R.P.; Cuttler, J.M.

1979-06-01

The problem of seismically qualifying different electrical instruments mounted in cabinets of a standard design is discussed and the following economical approach is described in detail. An analytical model of the cabinet structure is developed and validated by comparison with the results of shake table tests on a prototype cabinet. Modal analysis is then used to calculate the input spectra for shake table tests to qualify the individual instruments that are mounted at the required elevations in the cabinet. The worst input spectrum, appropriate to qualify each instrument, is then specified to the suppliers. This approach avoids the need to test each cabinet configuration in an assembled state in order to qualify it. (auth)

76 FR 53360 - Proposed Establishment of Class E Airspace; Stuart, IA

Science.gov (United States)

2011-08-26

...-0831; Airspace Docket No. 11-ACE-17] Proposed Establishment of Class E Airspace; Stuart, IA AGENCY... action proposes to establish Class E airspace at Stuart, IA. Controlled airspace is necessary to... surface for new standard instrument approach procedures at the City of Stuart Helistop, Stuart, IA...

77 FR 50650 - Proposed Amendment of Class E Airspace; Boone, IA

Science.gov (United States)

2012-08-22

...-1432; Airspace Docket No. 11-ACE-25] Proposed Amendment of Class E Airspace; Boone, IA AGENCY: Federal... proposes to amend Class E airspace at Boone, IA. Decommissioning of the Boone non-directional beacon (NDB... instrument approach procedures at Boone Municipal Airport, Boone, IA. Airspace reconfiguration is necessary...

78 FR 48840 - Proposed Amendment of Class E Airspace; Hampton, IA

Science.gov (United States)

2013-08-12

...-0585; Airspace Docket No. 13-ACE-7] Proposed Amendment of Class E Airspace; Hampton, IA AGENCY: Federal... proposes to amend Class E airspace at Hampton, IA. Decommissioning of the Hampton non-directional beacon... for standard instrument approach procedures at Hampton Municipal Airport, Hampton, IA. A segment would...

77 FR 50647 - Proposed Amendment of Class E Airspace; Perry, IA

Science.gov (United States)

2012-08-22

...-1435; Airspace Docket No. 11-ACE-28] Proposed Amendment of Class E Airspace; Perry, IA AGENCY: Federal... proposes to amend Class E airspace at Perry, IA. Decommissioning of the Perry non-directional beacon (NDB) at Perry Municipal Airport, Perry, IA, has made reconfiguration necessary for standard instrument...

78 FR 25234 - Proposed Establishment of Class E Airspace; Walker, MN

Science.gov (United States)

2013-04-30

...-0266; Airspace Docket No. 13-AGL-11] Proposed Establishment of Class E Airspace; Walker, MN AGENCY... action proposes to establish Class E airspace at Walker, MN. Controlled airspace is necessary to accommodate new Standard Instrument Approach Procedures (SIAP) at Walker Municipal Airport. The FAA is taking...

76 FR 44288 - Establishment of Class E Airspace; New Market, VA

Science.gov (United States)

2011-07-25

...-380; Airspace Docket No. 11-AEA-12] Establishment of Class E Airspace; New Market, VA AGENCY: Federal... proposes to establish Class E Airspace at New Market, VA, to accommodate the additional airspace needed for the Standard Instrument Approach Procedures developed for New Market Airport. This action would...

78 FR 45478 - Proposed Establishment of Class E Airspace; Salmon, ID

Science.gov (United States)

2013-07-29

...-0531; Airspace Docket No. 13-ANM-20] Proposed Establishment of Class E Airspace; Salmon, ID AGENCY... action proposes to establish Class E airspace at the Salmon VHF Omni-Directional Radio Range/Distance Measuring Equipment (VOR/DME) navigation aid, Salmon, ID, to facilitate vectoring of Instrument Flight Rules...

77 FR 4711 - Proposed Establishment of Class E Airspace; Houston, MO

Science.gov (United States)

2012-01-31

...-0903; Airspace Docket No. 11-ACE-20] Proposed Establishment of Class E Airspace; Houston, MO AGENCY... action proposes to establish Class E airspace at Houston, MO. Controlled airspace is necessary to accommodate new Standard Instrument Approach Procedures (SIAP) at Houston Memorial Airport. The FAA is taking...

76 FR 30299 - Proposed Establishment of Class E Airspace; Kayenta, AZ

Science.gov (United States)

2011-05-25

...-0393; Airspace Docket No. 11-AWP-2] Proposed Establishment of Class E Airspace; Kayenta, AZ AGENCY... action proposes to establish Class E Airspace at Kayenta Airport, Kayenta, AZ. Controlled airspace is...) standard instrument approach procedures at Kayenta Airport. The FAA is proposing this action to enhance the...

78 FR 33019 - Proposed Amendment of Class E Airspace; Commerce, TX

Science.gov (United States)

2013-06-03

...-0269; Airspace Docket No. 13-ASW-3] Proposed Amendment of Class E Airspace; Commerce, TX AGENCY... action proposes to amend Class E airspace at Commerce, TX. Additional controlled airspace is necessary to accommodate new Standard Instrument Approach Procedures (SIAPs) at Commerce Municipal Airport (AAF). The FAA...

Safety classification of nuclear power plant systems, structures and components

International Nuclear Information System (INIS)

1992-01-01

The Safety Classification principles used for the systems, structures and components of a nuclear power plant are detailed in the guide. For classification, the nuclear power plant is divided into structural and operational units called systems. Every structure and component under control is included into some system. The Safety Classes are 1, 2 and 3 and the Class EYT (non-nuclear). Instructions how to assign each system, structure and component to an appropriate safety class are given in the guide. The guide applies to new nuclear power plants and to the safety classification of systems, structures and components designed for the refitting of old nuclear power plants. The classification principles and procedures applying to the classification document are also given

Intermediate probabilistic safety assessment approach for safety critical digital systems

International Nuclear Information System (INIS)

Taeyong, Sung; Hyun Gook, Kang

2001-01-01

Even though the conventional probabilistic safety assessment methods are immature for applying to microprocessor-based digital systems, practical needs force to apply it. In the Korea, UCN 5 and 6 units are being constructed and Korean Next Generation Reactor is being designed using the digital instrumentation and control equipment for the safety related functions. Korean regulatory body requires probabilistic safety assessment. This paper analyzes the difficulties on the assessment of digital systems and suggests an intermediate framework for evaluating their safety using fault tree models. The framework deals with several important characteristics of digital systems including software modules and fault-tolerant features. We expect that the analysis result will provide valuable design feedback. (authors)

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

Preliminary safety evaluation (PSE) for Sodium Storage Facility at the Fast Flux Test Facility

International Nuclear Information System (INIS)

Bowman, B.R.

1994-01-01

This evaluation was performed for the Sodium Storage Facility (SSF) which will be constructed at the Fast Flux Test Facility (FFTF) in the area adjacent to the South and West Dump Heat Exchanger (DHX) pits. The purpose of the facility is to allow unloading the sodium from the FFTF plant tanks and piping. The significant conclusion of this Preliminary Safety Evaluation (PSE) is that the only Safety Class 2 components are the four sodium storage tanks and their foundations. The building, because of its imminent risk to the tanks under an earthquake or high winds, will be Safety Class 3/2, which means the building has a Safety Class 3 function with the Safety Class 2 loads of seismic and wind factored into the design

Neutron instrumentation for biology

Energy Technology Data Exchange (ETDEWEB)

Mason, S.A. [Institut Laue-Langevin, Grenoble (France)

1994-12-31

In the October 1994 round of proposals at the ILL, the external biology review sub- committee was asked to allocate neutron beam time to a wide range of experiments, on almost half the total number of scheduled neutron instruments: on 3 diffractometers, on 3 small angle scattering instruments, and on some 6 inelastic scattering spectrometers. In the 3.5 years since the temporary reactor shutdown, the ILL`s management structure has been optimized, budgets and staff have been trimmed, the ILL reactor has been re-built, and many of the instruments up-graded, many powerful (mainly Unix) workstations have been introduced, and the neighboring European Synchrotron Radiation Facility has established itself as the leading synchrotron radiation source and has started its official user program. The ILL reactor remains the world`s most intense dedicated neutron source. In this challenging context, it is of interest to review briefly the park of ILL instruments used to study the structure and energetics of small and large biological systems. A brief summary will be made of each class of experiments actually proposed in the latest ILL proposal round.

Factors affecting the design of instrument flight procedures

Directory of Open Access Journals (Sweden)

Ivan FERENCZ

2008-01-01

Full Text Available The article highlights factors, which might affect the design of instrument flight procedures. Ishikawa diagram is used to distribute individual factors into classes, as are People, Methods, Regulations, Tools, Data and Environment.

Operational and reliability experience with reactor instrumentation

International Nuclear Information System (INIS)

Dixon, F.; Gow, R.S.

1978-01-01

In the last 15 years the CEGB has experienced progressive plant development, integration and changes in operating regime through nine nuclear (gas-cooled reactor) power stations with corresponding instrumentation advances leading towards more refined centralized control. Operation and reliability experience with reactor instrumentation is reported in this paper with reference to the progressive changes related to the early magnox, late magnox and AGR periods. Data on instrumentation reliability in terms of reactor forced outages are presented and show that the instrumentation contributions to loss of generating plant availability are small. Reactor safety circuits, neutron flux and temperature measurements, gas analysis and vibration monitoring are discussed. In reviewing the reactor instrumentation the emphasis is on reporting recent experience, particularly on AGR equipment, but overall performance and changes to magnox equipment are included so that some appreciation can be obtained of instrumentation requirements with respect to plant lifetimes. (author)

WORKING WITH JAZZ PERCUSSIONISTS IN THE VIBRAPHONE CLASS

Directory of Open Access Journals (Sweden)

BEREZOVICOVA TATIANA

2015-12-01

Full Text Available The present article approaches some aspects of teaching students whose major is light music and jazz instruments (percus­sion instruments in the vibraphone class. The authors examine problems specific to studying the vibraphone by the percussion­ist that work in the field of light music and jazz such as setting the interpretative apparatus, forming the repertoire, overcoming some technical difficulties in the process of assimilating the instructive-didactic programme etc.

76 FR 30298 - Proposed Amendment of Class E Airspace; Cocoa, FL

Science.gov (United States)

2011-05-25

...-0070; Airspace Docket No. 10-ASO-43] Proposed Amendment of Class E Airspace; Cocoa, FL AGENCY: Federal... proposes to amend Class E Airspace at Cocoa, FL, as the Merritt Island Non-Directional Beacon (NDB) has... surface to support new standard instrument approach procedures developed at Merritt Island Airport, Cocoa...

75 FR 15360 - Proposed Amendment of Class E Airspace; Austin, TX

Science.gov (United States)

2010-03-29

...-1152; Airspace Docket No. 09-ASW-31] Proposed Amendment of Class E Airspace; Austin, TX AGENCY: Federal... proposes to amend Class E airspace in the Austin, TX area. Additional controlled airspace is necessary to accommodate new Standard Instrument Approach Procedures (SIAPs) at Austin Executive Airport, Austin, TX. The...

78 FR 31429 - Proposed Amendment of Class E Airspace; Mason, TX

Science.gov (United States)

2013-05-24

...-1141; Airspace Docket No. 12-ASW-12] Proposed Amendment of Class E Airspace; Mason, TX AGENCY: Federal... proposes to amend Class E airspace at Mason, TX. Additional controlled airspace is necessary to accommodate new Standard Instrument Approach Procedures (SIAP) at Mason County Airport. The FAA is taking this...

LOFT integral test system final safety analysis report

International Nuclear Information System (INIS)

1974-03-01

Safety analyses are presented for the following LOFT Reactor systems: engineering safety features; support buildings and facilities; instrumentation and controls; electrical systems; and auxiliary systems. (JWR)

Methodology for safety classification of PWR type nuclear power plants items

International Nuclear Information System (INIS)

Oliveira, Patricia Pagetti de

1995-01-01

This paper contains the criteria and methodology which define a classification system of structures, systems and components in safety classes according to their importance to nuclear safety. The use of this classification system will provide a set of basic safety requirements associated with each safety class specified. These requirements, when available and applicable, shall be utilized in the design, fabrication and installation of structures, systems and components of Pressurized Water Reactor Nuclear Power Plants. (author). 13 refs, 1 tab

Punk and Middle-Class Values: A Content Analysis.

Science.gov (United States)

Lamy, Philip; Levin, Jack

1985-01-01

Compares periodical articles representing the "Punk" movement with articles from the "Reader's Digest" and the 1960s hippie movement. Concludes that the punk movement is more expressive and less instrumental than its middle-class counterpart. (KH)

Nuclear safety considerations with emphasis on instrumentation and control systems

International Nuclear Information System (INIS)

Beare, J.W.

1978-01-01

The conceptual model of a nuclear power plant in Canada is that it consists basically of two kinds of systems. The first kind is the process systems, that is, those structures and components associated with the production of nuclear energy and its conversion to other forms of energy. The second kind is the special safety systems, whose purpose it is to protect the public in the event of a serious failure in the process systems which might otherwise lead to unacceptable radiological consequences. Quantitative limits are set on the unavailability of the special safety systems. These limits are low enough to be consistent with low overall risk and yet can be demonstrated by test during operation of the plant. Low unavailability is an important but not the only condition required for low unrealiability for the special safety systems. The special safety systems minimize the chance of a cross-linked failure particularly under the conditions experienced as a result of the more severe types of postulated serious process failures. Nuclear power plants must also withstand, without a major hazard to the public, certain rare events associated with natural phenomena or man-made activities off-site and also certain in-plant events such as fire or break-up of a turbine-generator which might have a cross-linking effect on process and safety systems. In the latest designs, Canadian nuclear power plants have emergency systems to deal with such events. The emergency systems have an enhanced degree of physical and functional separation from other plant systems. (author)

Interactive teaching and learning with smart phone app in Optoelectronic Instruments course

Science.gov (United States)

Hu, Yao; Hao, Qun; Zhou, Ya; Huang, Yifan

2017-08-01

Optoelectronic Instruments is a comprehensive professional course for senior students majored in optical engineering and similar specialties. Due to the low lecturer/ student ratio, typically less than 1:100, most of the students gave up the chance of one-to-one communication with the lecturers even when they were confused about the principle or applications of the instruments. A smart phone App Rain Classroom associated with messaging App Wechat is introduced. It enables the lecturers to receive instant feedback from students through bullet screen, push preview and review materials and post in-class quiz. Investigation also shows that 76% of the students enjoyed the new interactive tool, acknowledging its help in understanding the topic better, improving in-class interaction, and after class communications.

The multiphase instrumentation: a tool for the development of refining and petrochemical processes; L'instrumentation multiphasique: un outil pour le developpement des procedes de raffinage et petrochimie

Energy Technology Data Exchange (ETDEWEB)

Boyer, C.; Bayle, J.; Harter, I.; Schweitzer, J.M. [Institut Francais du Petrole. Centre d' Etude et de Developpement Industriel de Solaize, 69 (France)

2001-07-01

In the framework of the development of processes involving several phases, a study of contactors hydrodynamics is performed on units of significant size, before extrapolating the pilot results to industrial reactors. In these multiphase processes, the phases most often in contact are: liquid/gas, liquid/gas/solid and gas/solid. The study of their hydrodynamics requires the development of specific multiphase measurement techniques. Taking into consideration the complexity of the flows involved and the size of reactors, a global input-output characterization of the hydrodynamics is not sufficient and it is necessary to have access to the local flow parameters (velocity, flux, fraction of each phase). Moreover, the environment of the measurement (hydrocarbon-type fluid, real catalyst support, pressure) imposes the development of specific instruments of measurement with additional constraints (safety, robustness..). These measurements aim at analyzing the structure of the flows involved, validating the new technologies (distributors, separators, exchangers) and finally supplying a database for the validation of multiphase hydrodynamic models. This article proposes a review of the instrumentation techniques developed in the framework of 3 classes of multiphase reactors: fluidized bed reactors (gas/solid flow), slurry bubble column reactors (liquid/gas/solid flow), and fixed bed reactors (gas/liquid flow through a granular bed). (J.S.)

National Chemistry Teacher Safety Survey

Science.gov (United States)

Plohocki, Barbra A.

This study evaluated the status of secondary school instructional chemistry laboratory safety using a survey instrument which focused on Teacher background Information, Laboratory Safety Equipment, Facility Safety, General Safety, and a Safety Content Knowledge Survey. A fifty question survey instrument based on recent research and questions developed by the researcher was mailed to 500 secondary school chemistry teachers who participated in the 1993 one-week Woodrow Wilson National Fellowship Foundation Chemistry Institute conducted at Princeton University, New Jersey. The data received from 303 respondents was analyzed by t tests and Analysis of Variance (ANOVA). The level of significance for the study was set at ~\\ performance on the Safety Content Knowledge Survey and secondary school chemistry teachers who have had undergraduate and/or graduate safety training and those who have not had undergraduate and/or graduate safety training. Secondary school chemistry teachers who attended school district sponsored safety inservices did not score higher on the Safety Content Knowledge Survey than teachers who did not attend school district sponsored safety inservice sessions. The type of school district (urban, suburban, or rural) had no significant correlation to the type of laboratory safety equipment found in the instructional chemistry laboratory. The certification area (chemistry or other type of certificate which may or may not include chemistry) of the secondary school teacher had no significant correlation to the type of laboratory equipment found in the instructional chemistry laboratory. Overall, this study indicated a majority of secondary school chemistry teachers were interested in attending safety workshops applicable to chemistry safety. Throughout this research project, many teachers indicated they were not adequately instructed on the collegiate level in science safety and had to rely on common sense and self-study in their future teaching careers.

creating social presence in large classes

African Journals Online (AJOL)

Social presence refers to the ability of students to project themselves as 'real people' in an online learning community. While it is difficult to create social presence in large classes, educational technologies can enhance the social dimension of online learning if educators relinquish the use of technology as an instrument of ...

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

Innovative instrumentation for VVERs based in non-invasive techniques

International Nuclear Information System (INIS)

Jeanneau, H.; Favennec, J.M.; Tournu, E.; Germain, J.L.

2000-01-01

Nuclear power plants such as VVERs can greatly benefit from innovative instrumentation to improve plant safety and efficiency. In recent years innovative instrumentation has been developed for PWRs with the aim of providing additional measurements of physical parameters on the primary and secondary circuits: the addition of new instrumentation is made possible by using non-invasive techniques such as ultrasonics and radiation detection. These innovations can be adapted for upgrading VVERs presently in operation and also in future VVERs. The following innovative instrumentation for the control, monitoring or testing at VVERs is described: 1. instrumentation for more accurate primary side direct measurements (for a better monitoring of the primary circuit); 2. instrumentation to monitor radioactivity leaks (for a safer plant); 3. instrumentation-related systems to improve the plant efficiency (for a cheaper kWh)

40 CFR 82.70 - Nonessential Class II products and exceptions.

Science.gov (United States)

2010-07-01

... provide for motor vehicle safety in accordance with Federal Motor Vehicle Safety Standards until January 1... 21 CFR 2.125(e); (ii) Lubricants, coatings or cleaning fluids for electrical or electronic equipment...; (iii) Lubricants, coatings or cleaning fluids used for aircraft maintenance, which contain class II...

Instrument evaluation no. 10. Scanray radiation meter type 751

CERN Document Server

Burgess, P H; White, D F

1978-01-01

The various radiations encountered in radiological protection cover a wide range of energies and radiation measurements have to be carried out under an equally broad spectrum of environmental conditions. This report is one of a series intended to give information on the performance characteristics of radiological protection instruments, to assist in the selection of appropriate instruments for a given purpose, to interpret the results obtained with such instruments, and, in particular, to know the likely sources and magnitude of errors that might be associated with measurements in the field. The radiation, electrical and environmental characteristics of radiation protection instruments are considered together with those aspects of the construction which make an instrument convenient for routine use. To provide consistent criteria for instrument performance, the range of tests performed on any particular class of instrument, the test methods and the criteria of acceptable performance are based broadly on the a...

EPRTM Reactor neutron instrumentation

International Nuclear Information System (INIS)

Pfeiffer, Maxime; SALA, Stephanie

2013-06-01

The core safety during operation is linked, in particular, to the respect of criteria related to the heat generated in fuel rods and to the heat exchange between the rods and the coolant. This local power information is linked to the power distribution in the core. In order to evaluate the core power distribution, the EPR TM reactor relies on several types of neutron detectors: - ionization chambers located outside the vessel and used for protection and monitoring - a fixed in-core instrumentation based on Cobalt Self Powered Neutron Detectors used for protection and monitoring - a mobile reference in-core instrumentation based on Vanadium aero-balls This document provides a description of this instrumentation and its use in core protection, limitation, monitoring and control functions. In particular, a description of the detectors and the principles of their signal generation is supplied as well as the description of the treatments related to these detectors in the EPR TM reactor I and C systems (including periodical calibration). (authors)

Optimum Safety Levels for Breakwaters

DEFF Research Database (Denmark)

Burcharth, H. F.; Sørensen, John Dalsgaard

2005-01-01

Optimum design safety levels for rock and cube armoured rubble mound breakwaters without superstructure are investigated by numerical simulations on the basis of minimization of the total costs over the service life of the structure, taking into account typical uncertainties related to wave...... statistics and structure response. The study comprises the influence of interest rate, service lifetime, downtime costs and damage accumulation. Design limit states and safety classes for breakwaters are discussed. The results indicate that optimum safety levels are somewhat higher than the safety levels...

New quantitative safety standards: different techniques, different results?

International Nuclear Information System (INIS)

Rouvroye, J.L.; Brombacher, A.C.

1999-01-01

Safety Instrumented Systems (SIS) are used in the process industry to perform safety functions. Many factors can influence the safety of a SIS like system layout, diagnostics, testing and repair. In standards like the German DIN no quantitative analysis is demanded (DIN V 19250 Grundlegende Sicherheitsbetrachtungen fuer MSR-Schutzeinrichtungen, Berlin, 1994; DIN/VDE 0801 Grundsaetze fuer Rechner in Systemen mit Sicherheitsaufgaben, Berlin, 1990). The analysis according to these standards is based on expert opinion and qualitative analysis techniques. New standards like the IEC 61508 (IEC 61508 Functional safety of electrical/electronic/programmable electronic safety-related systems, IEC, Geneve, 1997) and the ISA-S84.01 (ISA-S84.01.1996 Application of Safety Instrumented Systems for the Process Industries, Instrument Society of America, Research Triangle Park, 1996) require quantitative risk analysis but do not prescribe how to perform the analysis. Earlier publications of the authors (Rouvroye et al., Uncertainty in safety, new techniques for the assessment and optimisation of safety in process industry, D W. Pyatt (ed), SERA-Vol. 4, Safety engineering and risk analysis, ASME, New York 1995; Rouvroye et al., A comparison study of qualitative and quantitative analysis techniques for the assessment of safety in industry, P.C. Cacciabue, I.A. Papazoglou (eds), Proceedings PSAM III conference, Crete, Greece, June 1996) have shown that different analysis techniques cover different aspects of system behaviour. This paper shows by means of a case study, that different (quantitative) analysis techniques may lead to different results. The consequence is that the application of the standards to practical systems will not always lead to unambiguous results. The authors therefore propose a technique to overcome this major disadvantage

Proposals for investigating instrument tube line breaks in pressurized water reactors

International Nuclear Information System (INIS)

Fletcher, C.D.; Charlton, T.R.; Loomis, G.G.; Hall, D.G.; Cozzuol, J.M.

1985-11-01

Questions posed by the NRC pertaining to instrument tube critical flow and applicability of the Semiscale experimental facility are evaluated. A program is recommended to investigate the issue of generic PWR safety following hypothetical rupture of instrument tubes due to consequences of seismic events

Carbon rentals and silvicultural subsidies for private forests as climate policy instruments

International Nuclear Information System (INIS)

Uusivuori, J.; Laturi, J.

2007-01-01

The impacts of potential climate policy instruments on the carbon production of privately owned and operated forests were investigated. A forest model with an endogenous growth description and age-class structure was used to describe both the output supply and input demand decisions of a private non-industrial landowner with optimized consumption flow, harvest timing, and an intertemporal allocation of forest investments. Two scenarios were examined, notably (1) a scenario in which the landowner was granted periodic carbon rental payments; and (2) a scenario in which the government subsidized the costs of silvicultural investments. The intended and unintended effects of the policies were examined. Models were used to demonstrate that the effectiveness of the instruments was significantly influenced by the age-class structure of forests when future carbon benefits were discounted. It was concluded that carbon rental payments were a more effective policy for older age-class structured forests. Silvicultural subsidies were more beneficial for forests with younger age-class structures. 21 refs., 6 figs

Guards: An approach safety-related systems using cots example of MMI and reactor automation in nuclear submarine application

International Nuclear Information System (INIS)

Brun, M.

1998-01-01

For at least 10 years, the nuclear industry designs and licences specific digital safety-critical systems (IEC 1226 class A). One key issue for future programs is to design and licence safety-related systems providing more complex functions and using Commercial-Off-The-Shelf components. This issue is especially raised for Reactor automation and Man-Machine-Interface. The usual I and C (Instrumentation and Control) organisation for these functions is based on redundancy between a commercial, up-to-date, unclassified > system and a simplified classified > system using traditional technologies. It clearly appears that such organisation is not satisfying from the point of view of people who have actually to operate these systems: The operator is supposed not to trust the normal system and rely on the back-up system which is less helpful and that he use very few. This paper presents a new approach to that problem using COTS components in low-level layers, safety architecture and mechanisms at medium level layer (GUARDS architecture developed in the current ESPRIT project number 20716), and a pre-validated functional layer. The aim of this solution is to comply with the > IEC 1226 class B requirements, at lower overall cost (design, implementation, licensing, long term confidence). This approach is illustrated by its application in Man-Machine-Interface (MMI) for our future program of Nuclear submarine. (author)

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.

HTGR Measurements and Instrumentation Systems

International Nuclear Information System (INIS)

Ball, Sydney J.; Holcomb, David Eugene; Cetiner, Mustafa Sacit

2012-01-01

This report provides an integrated overview of measurements and instrumentation for near-term future high-temperature gas-cooled reactors (HTGRs). Instrumentation technology has undergone revolutionary improvements since the last HTGR was constructed in the United States. This report briefly describes the measurement and communications needs of HTGRs for normal operations, maintenance and inspection, fuel fabrication, and accident response. The report includes a description of modern communications technologies and also provides a potential instrumentation communications architecture designed for deployment at an HTGR. A principal focus for the report is describing new and emerging measurement technologies with high potential to improve operations, maintenance, and accident response for the next generation of HTGRs, known as modular HTGRs, which are designed with passive safety features. Special focus is devoted toward describing the failure modes of the measurement technologies and assessing the technology maturity.

Multiobjective optimization of strategies for operation and testing of low-demand safety instrumented systems using a genetic algorithm and fault trees

International Nuclear Information System (INIS)

Longhi, Antonio Eduardo Bier; Pessoa, Artur Alves; Garcia, Pauli Adriano de Almada

2015-01-01

Since low-demand safety instrumented systems (SISs) do not operate continuously, their failures are often only detected when the system is demanded or tested. The conduction of tests, besides adding costs, can raise risks of failure on demand during their execution and also increase the frequency of spurious activation. Additionally, it is often necessary to interrupt production to carry out tests. In light of this scenario, this paper presents a model to optimize strategies for operation and testing of these systems, applying modeling by fault trees associated with optimization by a genetic algorithm. Its main differences are: (i) ability to represent four modes of operation and test them for each SIS subsystem; (ii) ability to represent a SIS that executes more than one safety instrumented function; (iii) ability to keep track of the down-time generated in the production system; and (iv) alteration of a genetic selection mechanism that permits identification of more efficient solutions with smaller influence on the optimization parameters. These aspects are presented by applying this model in three case studies. The results obtained show the applicability of the proposed approach and its potential to help make more informed decisions. - Highlights: • Models the integrity and cost related to operation and testing of low-demand SISs. • Keeps track of the production down-time generated by SIS tests and repairs. • Allows multiobjective optimization to identify operation and testing strategies. • Enables integrated assessment of an SIS that executes more than one SIF. • Allows altering the selection mechanism to identify the most efficient strategies

Recommendations of the Oligonucleotide Safety Working Group's Formulated Oligonucleotide Subcommittee for the Safety Assessment of Formulated Oligonucleotide-Based Therapeutics.

Science.gov (United States)

Marlowe, Jennifer L; Akopian, Violetta; Karmali, Priya; Kornbrust, Douglas; Lockridge, Jennifer; Semple, Sean

2017-08-01

The use of lipid formulations has greatly improved the ability to effectively deliver oligonucleotides and has been instrumental in the rapid expansion of therapeutic development programs using oligonucleotide drugs. However, the development of such complex multicomponent therapeutics requires the implementation of unique, scientifically sound approaches to the nonclinical development of these drugs, based upon a hybrid of knowledge and experiences drawn from small molecule, protein, and oligonucleotide therapeutic drug development. The relative paucity of directly applicable regulatory guidance documents for oligonucleotide therapeutics in general has resulted in the generation of multiple white papers from oligonucleotide drug development experts and members of the Oligonucleotide Safety Working Group (OSWG). The members of the Formulated Oligonucleotide Subcommittee of the OSWG have utilized their collective experience working with a variety of formulations and their associated oligonucleotide payloads, as well as their insights into regulatory considerations and expectations, to generate a series of consensus recommendations for the pharmacokinetic characterization and nonclinical safety assessment of this unique class of therapeutics. It should be noted that the focus of Subcommittee discussions was on lipid nanoparticle and other types of particulate formulations of therapeutic oligonucleotides and not on conjugates or other types of modifications of oligonucleotide structure intended to facilitate delivery.

Obstacles of Teaching Mathematics Faced by the Class Teachers in Jordan

Science.gov (United States)

Nejem, Khamis Mousa; Muhanna, Waffa

2013-01-01

The purpose of the study is to investigate the obstacles of teaching mathematics faced by the class teachers in Jordan. To achieve this purpose a study sample of 192 male and female class teachers was selected randomly from government schools. The instrument of the study was a questionnaire used to investigate the obstacles of mathematics…

76 FR 54148 - Proposed Amendment of Class E Airspace; Emmonak, AK

Science.gov (United States)

2011-08-31

... AK E5 Emmonak, AK [Revised] Emmonak Airport, AK (Lat. 62[deg]47'10'' N., long. 164[deg]29'27'' W...-0880 Airspace Docket No. 11-AAL-17] Proposed Amendment of Class E Airspace; Emmonak, AK AGENCY: Federal... proposes to revise Class E airspace at Emmonak, AK. The amendment of two standard instrument approach...

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)

New quantitative safety standards : Different techniques, different results?

NARCIS (Netherlands)

Rouvroye, J.L.; Brombacher, A.C.; Lydersen, S.; Hansen, G.K.; Sandtor, H.

1998-01-01

Safety Instrumented Systems (SIS) are used in the process industry to perform safety functions. Many parameters can influence the safety of a SIS like system layout, diagnostics, testing and repair. In standards like the German DIN [DIN19250, DIN0801] no quantitative analysis was demanded. The

77 FR 4713 - Proposed Establishment of Class E Airspace; Red Cloud, NE

Science.gov (United States)

2012-01-31

...-0426; Airspace Docket No. 11-ACE-7] Proposed Establishment of Class E Airspace; Red Cloud, NE AGENCY... action proposes to establish Class E airspace at Red Cloud, NE. Controlled airspace is necessary to accommodate new Standard Instrument Approach Procedures (SIAP) at Red Cloud Municipal Airport. The FAA is...

77 FR 49399 - Proposed Amendment of Class E Airspace; Forest City, IA

Science.gov (United States)

2012-08-16

...-0654; Airspace Docket No. 12-ACE-3] Proposed Amendment of Class E Airspace; Forest City, IA AGENCY... action proposes to amend Class E airspace at Forest City, IA. Additional controlled airspace is necessary... accommodate new standard instrument approach procedures at Forest City Municipal Airport, Forest City, IA. The...

77 FR 71361 - Proposed Amendment of Class E Airspace; West Union, IA

Science.gov (United States)

2012-11-30

...-1434; Airspace Docket No. 11-ACE-27] Proposed Amendment of Class E Airspace; West Union, IA AGENCY... action proposes to amend Class E airspace at West Union, IA. Decommissioning of the West Union non... instrument approach procedures at George L. Scott Municipal Airport, West Union, IA. Airspace reconfiguration...

77 FR 41939 - Proposed Establishment of Class E Airspace; Deer Lodge, MT

Science.gov (United States)

2012-07-17

...-0379; Airspace Docket No. 12-ANM-7 Proposed Establishment of Class E Airspace; Deer Lodge, MT AGENCY... action proposes to establish Class E airspace at Deer Lodge-City-County Airport, Deer Lodge, MT... System (GPS) standard instrument approach procedures at Deer Lodge-City-County Airport, Deer Lodge, MT...

The qualification of electrical components and instrumentations relevant to safety; La qualificazione dei componenti elettrici e di strumentazione rilevanti per la sicurezza

Energy Technology Data Exchange (ETDEWEB)

Zambardi, F [ENEA - Direzione Sicurezza Nucleare e Protezione Sanitaria, Divisione Sistemi Elettrici e Strumentazione, Rome (Italy)

1989-03-15

Systems and components relevant to safety of nuclear power plants must maintain their functional integrity in order to assure accident prevention and mitigation. Redundancy is utilized against random failures, nevertheless care must be taken to avoid common failures in redundant components. Main sources of degradation and common cause failures consist in the aging effects and in the changes of environmental conditions which occur during the plant life and the postulated accidents. These causes of degradation are expected to be especially significant for instrumentation and electrical equipment, which can have a primary role in safety systems. The qualification is the methodology by which component safety requirements can be met against the above mentioned causes of degradation. In this report the connection between the possible, plant conditions and the resulting degradation effects on components is preliminarily addressed. A general characterization of the qualification is then presented. Basis, methods and peculiar aspects are discussed and the qualification by testing is taken into special account. Technical and organizational aspects related to a plant qualification program are also focused. The report ends with a look to the most significant research and development activities. (author)

The Character Strengths of Class Clowns

Directory of Open Access Journals (Sweden)

Willibald F. Ruch

2014-09-01

Full Text Available Class clowns traditionally were studied as a type concept and identified via sociometric procedures. In the present study a variable-centered approach was favored and class clown behaviors were studied in the context of character strengths, orientations to happiness and satisfaction with life. A sample of 672 Swiss children and adolescents filled in an 18 item self-report instrument depicting class clown behaviors. A hierarchical model of class clown behaviors was developed distinguishing a general factor and the four positively correlated dimensions of identified as a class clown, comic talent, disruptive rule-breaker, and subversive joker. Analysis of the general factor showed that class clowns were primarily male, and tended to be seen as class clowns by the teacher. Analyses of the 24 character strengths of the VIA-Youth (Park & Peterson, 2006 showed that class clowns were high in humor and leadership, and low in strengths like prudence, self-regulation, modesty, honesty, fairness, perseverance, and love of learning. An inspection of signature strengths revealed that 75% of class clowns had humor as a signature strength. Furthermore, generally class clown behaviors were shown by students indulging in a life of pleasure, but low life of engagement. The four dimensions yielded different character strengths profiles. While all dimensions of class clowns behaviors were low in temperance strengths, the factors identified as the class clown and comic talent were correlated with leadership strengths and the two negative factors (disruptive rule-breaker, subversive joker were low in other directed strengths. The disruptive rule breaking class clown was additionally low in intellectual strengths. While humor predicted life satisfaction, class clowning tended to go along with diminished satisfaction with life. It is concluded that different types of class clowns need to be kept apart and need different attention by teachers.

The character strengths of class clowns.

Science.gov (United States)

Ruch, Willibald; Platt, Tracey; Hofmann, Jennifer

2014-01-01

Class clowns traditionally were studied as a type concept and identified via sociometric procedures. In the present study a variable-centered approach was favored and class clown behaviors were studied in the context of character strengths, orientations to happiness and satisfaction with life. A sample of 672 Swiss children and adolescents filled in an 18 item self-report instrument depicting class clown behaviors. A hierarchical model of class clown behaviors was developed distinguishing a general factor and the four positively correlated dimensions of "identified as a class clown," "comic talent," "disruptive rule-breaker," and "subversive joker." Analysis of the general factor showed that class clowns were primarily male, and tended to be seen as class clowns by the teacher. Analyses of the 24 character strengths of the VIA-Youth (Park and Peterson, 2006) showed that class clowns were high in humor and leadership, and low in strengths like prudence, self-regulation, modesty, honesty, fairness, perseverance, and love of learning. An inspection of signature strengths revealed that 75% of class clowns had humor as a signature strength. Furthermore, class clown behaviors were generally shown by students indulging in a life of pleasure, but low life of engagement. The four dimensions yielded different character strengths profiles. While all dimensions of class clowns behaviors were low in temperance strengths, the factors "identified as the class clown" and "comic talent" were correlated with leadership strengths and the two negative factors ("disruptive rule-breaker," "subversive joker") were low in other directed strengths. The disruptive rule breaking class clown was additionally low in intellectual strengths. While humor predicted life satisfaction, class clowning tended to go along with diminished satisfaction with life. It is concluded that different types of class clowns need to be kept apart and need different attention by teachers.

Safety enhancement through calibration and maintenance

International Nuclear Information System (INIS)

Mohammad Ali Khalid; Taiman Kadni

2000-01-01

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

ATLAS Facility and Instrumentation Description Report

International Nuclear Information System (INIS)

Kang, Kyoung Ho; Moon, Sang Ki; Park, Hyun Sik

2009-06-01

A thermal-hydraulic integral effect test facility, ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation), has been constructed at KAERI (Korea Atomic Energy Research Institute). The ATLAS is a half-height and 1/288-volume scaled test facility with respect to the APR1400. The fluid system of the ATLAS consists of a primary system, a secondary system, a safety injection system, a break simulating system, a containment simulating system, and auxiliary systems. The primary system includes a reactor vessel, two hot legs, four cold legs, a pressurizer, four reactor coolant pumps, and two steam generators. The secondary system of the ATLAS is simplified to be of a circulating looptype. Most of the safety injection features of the APR1400 and the OPR1000 are incorporated into the safety injection system of the ATLAS. In the ATLAS test facility, about 1300 instrumentations are installed to precisely investigate the thermal-hydraulic behavior in simulation of the various test scenarios. This report describes the scaling methodology, the geometric data of the individual component, and the specification and the location of the instrumentations which are specific to the simulation of 50% DVI line break accident of the APR1400 for supporting the 50 th OECD/NEA International Standard Problem Exercise (ISP-50)

Strategy to safety grade systems replacements

International Nuclear Information System (INIS)

Stimler, M.; Sullivan, K.E.; Trebincevic, I.

1993-01-01

The introduction of digital instrumentation and control systems in nuclear power plants is characterized by the need to satisfy the requirements of safety, reliability and man-machine ergonomics. Today digital instrumentation and control systems meet these requirements and the trend in Europe is towards full digital based nuclear power plant control systems. This paper describes Siemens (KWU) experience in nuclear power plants and development in trends within Europe. Topics which are the subject of major concern to NPP operators addressed in this paper are: human performance factors - man-machine interface; operating philosophy; safety, availability and reliability. Other aspects addressed are: Siemens open-quotes defense in depthclose quotes concept, description of Siemens digital I ampersand C systems, safety requirements and systems, I ampersand C qualification, control room ergonomics, information systems and retrofitting experience

75 FR 53876 - Proposed Establishment of Class E Airspace; Berryville, AR

Science.gov (United States)

2010-09-02

... Class E Airspace; Berryville, AR AGENCY: Federal Aviation Administration (FAA), DOT. ACTION: Notice of proposed rulemaking (NPRM). SUMMARY: This action proposes to establish Class E airspace at Berryville, AR... SIAPs operations at Carroll County Airport, Berryville, AR. Controlled airspace is needed for the safety...

Twenty-fifth water reactor safety information meeting: Proceedings. Volume 3: Thermal hydraulic research and codes; Digital instrumentation and control; Structural performance

International Nuclear Information System (INIS)

Monteleone, S.

1998-04-01

This three-volume report contains papers presented at the conference. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Japan, Norway, and Russia. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume contains the following: (1) thermal hydraulic research and codes; (2) digital instrumentation and control; (3) structural performance

Food Sanitation and Safety Self-assessment Instrument for Family Day-Care Homes.

Science.gov (United States)

1990

This self-assessment instrument for family day care providers is designed to help caregivers provide safe food to children. The eight sections of the instrument, presented in checklist format, concern: (1) personal hygiene; (2) purchasing and inspecting of food; (3) food storage; (4) kitchen equipment; (5) food preparation; (6) infant food…

AERB information booklet: personal protective equipment- safety footwear

International Nuclear Information System (INIS)

1992-01-01

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

Handbook of laboratory health and safety measures

International Nuclear Information System (INIS)

Pal, S.B.

1985-01-01

The application of radioactive isotopes and various scientific instruments based on different ionizing and non-ionizing radiation have brought new safety problems to laboratory workers today. Therefore, there is a need to revise present knowledge of safety measures to deal with new hazards, thus broadening the outlook towards health and safety measures for contemporary laboratory staff. This handbook presents a series of articles on current knowledge regarding laboratory safety

Sudanese Students' Perceptions of Their Class Activities: Psychometric Properties and Measurement Invariance of My Class Activities--Arabic Language Version

Science.gov (United States)

Pereira, Nielsen; Bakhiet, Salaheldin Farah; Gentry, Marcia; Balhmar, Tahani Abdulrahman; Hakami, Sultan Mohammed

2017-01-01

This study examined the psychometric properties and measurement invariance of the Arabic version of "My Class Activities" (MCA), an instrument designed to measure students' perceptions of interest, challenge, choice, and enjoyment in classrooms. Scores of 3,516 Sudanese students in Grades 2 to 8 were used. Confirmatory factor analysis…

CMOS Electrochemical Instrumentation for Biosensor Microsystems: A Review

Directory of Open Access Journals (Sweden)

Haitao Li

2016-12-01

Full Text Available Modern biosensors play a critical role in healthcare and have a quickly growing commercial market. Compared to traditional optical-based sensing, electrochemical biosensors are attractive due to superior performance in response time, cost, complexity and potential for miniaturization. To address the shortcomings of traditional benchtop electrochemical instruments, in recent years, many complementary metal oxide semiconductor (CMOS instrumentation circuits have been reported for electrochemical biosensors. This paper provides a review and analysis of CMOS electrochemical instrumentation circuits. First, important concepts in electrochemical sensing are presented from an instrumentation point of view. Then, electrochemical instrumentation circuits are organized into functional classes, and reported CMOS circuits are reviewed and analyzed to illuminate design options and performance tradeoffs. Finally, recent trends and challenges toward on-CMOS sensor integration that could enable highly miniaturized electrochemical biosensor microsystems are discussed. The information in the paper can guide next generation electrochemical sensor design.

The Use of Theatre Tours in Road Safety Education.

Science.gov (United States)

Powney, Janet; And Others

The Scottish Road Safety Campaign and the Road Safety Council of Wales have made a large investment in theater tours as a method of providing road safety education. This study aimed to evaluate the effectiveness of a road safety message delivered by a theater group, Road Safety Officers (RSOs), or, teachers for pupils in upper secondary classes.…

An improved instrument setpoint control program

International Nuclear Information System (INIS)

Cash, J.S. Jr.; George, R.T.; Kincaid, S.C.

1991-01-01

Instrument setpoints have a definite and often significant impact on plant safety, reliability, and availability. Although typically overshadowed by plant design, modification, and physical change activities, instrument setpoints can alter plant status and system operating characteristics just as significantly. Recognizing the need for a formal program that provides configuration control of instrument setpoints, provides a readily accessible and clearly documented basis for instrument setpoints, and integrates and coordinates operations, engineering, and maintenance activities that influence the basis for instrument setpoints, Philadelphia Electric Company (PECo) is developing an Improved Instrument Setpoint Control Program (IISCP) that incorporates current industry guidance and practices and state-of-the-art information systems technology. The IISCP was designed around PECo's then existing business processes for setpoint control, determination, and maintenance. A task force representing the various constituencies from both plants and the engineering and services organizations were formed to identify objectives and design features for the IISCP. Utilizing industry standards and guidance, regulatory documents, the experiences and good practices obtained from other utilities, and PECo's nuclear group strategies, objectives, and goals, specific objectives were identified to enhance the business processes

Instrumentation and control doctrine for VVER upgrading

International Nuclear Information System (INIS)

Pernette, R.; Cucciniello, J.; Trebot, R.

1997-01-01

The main results are reported of analyses carried out on the WWER-400 and WWER-1000 series, and the reasons are summed up underlying the decision to establish a policy of WWER instrumentation and control upgrading. It is shown that such a policy forms a key stage in any upgrading project and contributes to the improvement of reactor safety at several levels: it helps to optimize the integration of safety requirements; it makes it easier to achieve a high level of automation and a better man-machine interaction; it should raise the culture of reactor safety. Four annexes demonstrate the factual fundamentals and structure of such a policy. (A.K.)

76 FR 53359 - Proposed Establishment of Class E Airspace; Nashville, AR

Science.gov (United States)

2011-08-26

...-0497; Airspace Docket No. 11-ASW-4] Proposed Establishment of Class E Airspace; Nashville, AR AGENCY... action proposes to establish Class E airspace at Nashville, AR. Controlled airspace is necessary to... approach procedures at Howard County Airport, Nashville, AR. Controlled airspace is needed for the safety...

Safety Research Experiment Facility Project. Conceptual design report. Volume VIII. Instrumentation and control

International Nuclear Information System (INIS)

1975-01-01

Included are sections dealing with the following: nuclear instrumentation system, reactor control system, plant protection system, plant annunciator system, data acquisition system, and reactor cooling system instrumentation and control

76 FR 35967 - Amendment of Class E Airspace; Bozeman, MT

Science.gov (United States)

2011-06-21

..., Gallatin Field Airport, Bozeman, MT, to accommodate aircraft using Instrument Landing System (ILS... 6005 Class E airspace areas extending upward from 700 feet or more above the surface of the earth...

Alternative development and action plan for the atomic safety regulation instruments

International Nuclear Information System (INIS)

Kim, J. Y.; Ahn, S. K.; Ham, Y. S.

2004-01-01

The goal of this study to provide highly practical model to regulation agency. Since nuclear power safety regulation has different characteristics, compared to general regulation, it is important to have new point of view and approach. But application possibility for regulation that guarantees the 'perfect safety' is very low. Therefore, it is important establish nuclear power safety regulation that is realistic as well as safety securing. In order to establish high quality regulation, evaluation of existing regulation must be done first. Thus in this study, 6 standards to evaluate existing regulation are suggested. They are clearness, efficiency, flexibility, reliability, responsibility and political consideration. Also, strategies to complement the weak points of regulatory governance, regulatory sunset, regulatory map, regulatory negotiation, regulatory benefit cost analysis, etc. These strategies can be applied all in one regulation, and can strategically be selected for application. After analyzing the result if case analysis on nuclear furnace regulation for research study, agreement was made that it is most efficient to consider in the order if clearness reliability, flexibility, confidence, political consideration, administrative efficiency and economic efficiency

Irradiation technology (1). Development of new in-pile instrumentation at JMTR

International Nuclear Information System (INIS)

Shibata, Akira; Kimura, Nobuaki; Tanimoto, Masataka; Nakamura, Jinichi; Saito, Takashi; Tsuchiya, Kunihiko

2012-01-01

Development of instrumentation which can use under severe accident condition is important issue for the purpose to cope with severe accident at nuclear reactors. And also to improve the quality of irradiation tests data and to increase the reliability of safety management system of reactors, the development of new instrumentation is key issue. JAEA is developing several in-pile instrumentations to conduct irradiation tests at JMTR. This study includes the developments of three new instrumentations and describes the characteristics of the instrumentations. These are ECP sensor, new water level indicator and in-reactor observation system using Cherenkov light. (author)

Instrument calibration optimization at Bruce Power: ECI loops

International Nuclear Information System (INIS)

Chugh, V.; Angelova, M.; Ghias, S.; Parmar, R.; Wang, V.; Xie, H.; Higgs, J.; Schut, J.; Cruchley, I.

2011-01-01

Most instruments in a nuclear power plant are calibrated at regular intervals to ensure consistency with the assumptions in the plant Technical Specifications and/or Safe Operating Envelope (SOE) compliance limits (e.g., As-Found Tolerance). In the Instrument Uncertainty Calculations (IUC), As-Found Tolerance for instrument drift is estimated based on statistical analysis of As-Found and As-Left calibration data such as that carried out for Bruce NGS by EPRI (Electric Power Research Institute) in 1998. Bruce specific drift values were found to compare favorably with industry benchmarks. Recently a significant amount of work has been done by EPRI and IAEA (International Atomic Energy Agency) on extending calibration intervals of safety related instruments. Reduction in calibration frequency reduces time commitments on the part of Authorized Nuclear Operators and safety system qualified Control Maintenance Technicians, and allows more schedule flexibility. To establish the proof of concept, As-Left/As-Found tolerances and available margins have been evaluated for the Bruce B Emergency Coolant Injection (ECI) system instrument loops to determine whether an extension of the calibration period from one or two year to three years is justifiable on the basis that these loops will still be in compliance with SOE. The analysis showed that 60% of instruments in the ECI system are qualified for calibration interval extension up to three years. Sensitivity assessment of the effect of proposed changes in calibration intervals for 60% of the instruments on the ECI system unavailability has also been performed using the current Bruce Power ECI unavailability model. The results show that, the largest ECI Predicted Future Unavailability (PFU) is 9.2E-4 year/year for in-core LOCA accident. This value is still below the target unavailability of 1.0E-3 year/year. (author)

Instrument calibration optimization at Bruce Power: ECI loops

Energy Technology Data Exchange (ETDEWEB)

Chugh, V.; Angelova, M.; Ghias, S.; Parmar, R.; Wang, V.; Xie, H. [AMEC NSS, Toronto, Ontario (Canada); Higgs, J.; Schut, J.; Cruchley, I. [Bruce Power, Tiverton, Ontario (Canada)

2011-07-01

Most instruments in a nuclear power plant are calibrated at regular intervals to ensure consistency with the assumptions in the plant Technical Specifications and/or Safe Operating Envelope (SOE) compliance limits (e.g., As-Found Tolerance). In the Instrument Uncertainty Calculations (IUC), As-Found Tolerance for instrument drift is estimated based on statistical analysis of As-Found and As-Left calibration data such as that carried out for Bruce NGS by EPRI (Electric Power Research Institute) in 1998. Bruce specific drift values were found to compare favorably with industry benchmarks. Recently a significant amount of work has been done by EPRI and IAEA (International Atomic Energy Agency) on extending calibration intervals of safety related instruments. Reduction in calibration frequency reduces time commitments on the part of Authorized Nuclear Operators and safety system qualified Control Maintenance Technicians, and allows more schedule flexibility. To establish the proof of concept, As-Left/As-Found tolerances and available margins have been evaluated for the Bruce B Emergency Coolant Injection (ECI) system instrument loops to determine whether an extension of the calibration period from one or two year to three years is justifiable on the basis that these loops will still be in compliance with SOE. The analysis showed that 60% of instruments in the ECI system are qualified for calibration interval extension up to three years. Sensitivity assessment of the effect of proposed changes in calibration intervals for 60% of the instruments on the ECI system unavailability has also been performed using the current Bruce Power ECI unavailability model. The results show that, the largest ECI Predicted Future Unavailability (PFU) is 9.2E-4 year/year for in-core LOCA accident. This value is still below the target unavailability of 1.0E-3 year/year. (author)

76 FR 54152 - Proposed Amendment of Class E Airspace Galbraith Lake, AK

Science.gov (United States)

2011-08-31

..., AK [Revised] Galbraith Lake Airport, AK (Lat. 68[deg]28'47'' N., long. 149[deg]29'24'' W) That...-0865; Airspace Docket No. 11-AAL-14] Proposed Amendment of Class E Airspace Galbraith Lake, AK AGENCY... action proposes to amend Class E airspace at Galbraith Lake AK. The creation of two special instrument...

Instrument for assessing the quality of mobile emergency pre-hospital care: content validation

Directory of Open Access Journals (Sweden)

Rodrigo Assis Neves Dantas

2015-06-01

Full Text Available OBJECTIVES To validate an instrument to assess quality of mobile emergency pre-hospital care. METHOD A methodological study where 20 professionals gave their opinions on the items of the proposed instrument. The analysis was performed using Kappa test (K and Content Validity Index (CVI, considering K> 0.80 and CVI ≥ 0.80. RESULTS Three items were excluded from the instrument: Professional Compensation; Job Satisfaction and Services Performed. Items that obtained adequate K and CVI indexes and remained in the instrument were: ambulance conservation status; physical structure; comfort in the ambulance; availability of material resources; user/staff safety; continuous learning; safety demonstrated by the team; access; welcoming; humanization; response time; costumer privacy; guidelines on care; relationship between professionals and costumers; opportunity for costumers to make complaints and multiprofessional conjunction/actuation. CONCLUSION The instrument to assess quality of care has been validated and may contribute to the evaluation of pre-hospital care in mobile emergency services.

World class manufacturing in metallurgical enterprise

OpenAIRE

B. Gajdzik

2013-01-01

World Class Manufacturing (WCM) assumes increase of efficiency of the company by elimination of all the losses, wastage and dangers of safety. In ArcelorMittal the concept of WCM is implemented in particular enterprises within the capital group. In this publication the activities conducted in some of those enterprises are described.

77 FR 58473 - Minimum Technical Standards for Class II Gaming Systems and Equipment

Science.gov (United States)

2012-09-21

... to all equipment, including computer, electronic, or other technologic aids used with Class II games..., computer, or other technologic aids in connection with the play of Class II games. This part establishes... gaming system, causes a discontinuance of game play or other component functions. Financial instrument...

76 FR 3571 - Proposed Establishment of Class E Airspace; Kahului, HI

Science.gov (United States)

2011-01-20

...-1233; Airspace Docket No. 10-AWP-21] Proposed Establishment of Class E Airspace; Kahului, HI AGENCY... action proposes to establish Class E airspace at Kahului Airport, Kahului, HI. Controlled airspace is... procedures at Kahului Airport, Kahului, HI. The FAA is proposing this action to enhance the safety and...

75 FR 6594 - Proposed Amendment of Class E Airspace; Osceola, AR

Science.gov (United States)

2010-02-10

...-1183; Airspace Docket No. 09-ASW-38] Proposed Amendment of Class E Airspace; Osceola, AR AGENCY... action proposes to amend Class E airspace at Osceola, AR. Decommissioning of the Osceola non-directional beacon (NDB) at Osceola Municipal Airport, Osceola, AR, has made this action necessary for the safety and...

VFR Class B Graphics - Aeronautical Information Services Digital Products

Data.gov (United States)

Department of Transportation — These graphics are designed to increase safety and aid pilots in gaining situational awareness within existing and redesigned Class B areas. The graphic provides an...

Development of a methodology for safety classification on a non-reactor nuclear facility illustrated using an specific example

International Nuclear Information System (INIS)

Scheuermann, F.; Lehradt, O.; Traichel, A.

2015-01-01

To realize the safety of personnel and environment systems and components of nuclear facilities are classified according to their potential danger into safety classes. Based on this classification different demands on the manufacturing quality result. The objective of this work is to present the standardized method developed by NUKEM Technologies Engineering Services for the categorization into the safety classes restricted to Non-reactor nuclear facilities (NRNF). Exemplary the methodology is used on the complex Russian normative system (four safety classes). For NRNF only the lower two safety classes are relevant. The classification into the lowest safety class 4 is accordingly if the maximum resulting dose following from clean-up actions in case of incidents/accidents remains below 20 mSv and the volume activity restrictions of set in NRB-99/2009 are met. The methodology is illustrated using an example. In short the methodology consists of: - Determination of the working time to remove consequences of incidents, - Calculation of the dose resulting from direct radiation and due to inhalation during these works. The application of this methodology avoids over-conservative approaches. As a result some previously higher classified equipment can be classified into the lower safety class.

Safety Education in the Elementary School. Fastback 170.

Science.gov (United States)

Wayne, Joseph E.

This pamphlet deals with incorporating effective safety education programs into the elementary school curriculum. Covered in a discussion of the scope and nature of the safety problem are classes of accidents (motor vehicle, home, work, and public accidents) and causes of accidents. Various functions of safety education in elementary schools are…

Systematic evaluation program review of NRC Safety Topic VI-7.3 associated with the electrical, instrumentation and control portions of the ECCS actuation system for the Dresden II Nuclear Power Plant

International Nuclear Information System (INIS)

St Leger-Barter, G.

1980-11-01

This report documents the technical evaluation and review of NRC Safety Topic VI-7.A.3, associated with the electrical, instrumentation, and control portions of the classification of the ECCS actuation system for the Dresden II nuclear power plant, using current licensing criteria

HTGR safety research program. Progress report, April--June 1975

International Nuclear Information System (INIS)

Kirk, W.L.

1975-09-01

Progress in HTGR safety research is reported under the following headings: fission product technology; primary coolant impurities; structural investigation; safety instrumentation and control systems; phenomena modeling and systems analysis. (JWR)

Strategy for the development of EU Test Blanket Systems instrumentation

Energy Technology Data Exchange (ETDEWEB)

Calderoni, P., E-mail: Pattrick.Calderoni@f4e.europa.eu; Ricapito, I.; Poitevin, Y.

2013-10-15

Highlights: • We developed a strategy for the development of instrumentation for EU ITER TBSs. • TBSs instrumentation functions: safety, operation and scientific mission. • Described activities are in support of ITER design review process. -- Abstract: The instrumentation of the HCLL and HCPB Test Blanket System is fundamental in ensuring that ITER safety and operational requirements are satisfied as well as in enabling the scientific mission of the TBM program. It carries out three essential functions: (i) safety, intended as compliance with ITER requirements toward public and workers protection; (ii) system control, intended as compliance with ITER operational requirements and investment protection; and (iii) scientific mission, intended as validating technology and predictive tools for blanket concepts relevant to fusion energy systems. This paper describes the strategy for instrumentation development by providing details of the following five steps to be implemented in procured activities in the short to mid-term (3–4 years): (i) provide mapping of sensors requirements based on critical review of preliminary design data; (ii) develop functional specifications for TBS sensors based on the analysis of operative conditions in the various ITER buildings in which they are located; (iii) assess availability of commercial sensors against developed specifications; (iv) develop prototypes when no available solution is identified; and (v) perform single effect tests for the most critical solicitations and post-test examination of commercial products and prototypes. Examples of technology assessment in two technical areas are included to reinforce and complement the strategy description.

Safety studies project on waste management. Final report. Chapters 2 and 3

International Nuclear Information System (INIS)

1985-01-01

The report presents, in summary form, a mode of procedure for accident analysis in nuclear waste management facilities. New instruments for safety analysis have been developed and tested. The report describes exemplary safety analyses with the new instrumentation. The safety analyses were carried out in surface systems, i.e. reprocessing and waste treatment systems, and in underground nuclear waste storage road and rail transport of radioactive materials have been investigated. (EF) [de

KAERI software safety guideline for developing safety-critical software in digital instrumentation and control system of nuclear power plant

International Nuclear Information System (INIS)

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

1997-07-01

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 organization. The requirements for software important to safety of nuclear reactor are described in such positions and standards. Most of them are describing mandatory requirements, what shall be done, for the safety-critical software. The developers of such a software. However, there have been a lot of controversial factors on whether the work practices satisfy the regulatory requirements, and to justify the safety of such a system developed by the work practices, between the licenser and the licensee. We believe it is caused by the reason that there is a gap between the mandatory requirements (What) and the work practices (How). We have developed a guidance to fill such gap, which can be useful for both licenser and licensee to conduct a justification of the safety in the planning phase of developing the software for nuclear reactor protection systems. (author). 67 refs., 13 tabs., 2 figs

KAERI software safety guideline for developing safety-critical software in digital instrumentation and control system of nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

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

1997-07-01

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 organization. The requirements for software important to safety of nuclear reactor are described in such positions and standards. Most of them are describing mandatory requirements, what shall be done, for the safety-critical software. The developers of such a software. However, there have been a lot of controversial factors on whether the work practices satisfy the regulatory requirements, and to justify the safety of such a system developed by the work practices, between the licenser and the licensee. We believe it is caused by the reason that there is a gap between the mandatory requirements (What) and the work practices (How). We have developed a guidance to fill such gap, which can be useful for both licenser and licensee to conduct a justification of the safety in the planning phase of developing the software for nuclear reactor protection systems. (author). 67 refs., 13 tabs., 2 figs.

Probabilistic safety analysis and interpretation thereof

International Nuclear Information System (INIS)

Steininger, U.; Sacher, H.

1999-01-01

Increasing use of the instrumentation of PSA is being made in Germany for quantitative technical safety assessment, for example with regard to incidents which must be reported and forwarding of information, especially in the case of modification of nuclear plants. The Commission for Nuclear Reactor Safety recommends regular execution of PSA on a cycle period of ten years. According to the PSA guidance instructions, probabilistic analyses serve for assessing the degree of safety of the entire plant, expressed as the expectation value for the frequency of endangering conditions. The authors describe the method, action sequence and evaluation of the probabilistic safety analyses. The limits of probabilistic safety analyses arise in the practical implementation. Normally the guidance instructions for PSA are confined to the safety systems, so that in practice they are at best suitable for operational optimisation only to a limited extent. The present restriction of the analyses has a similar effect on power output operation of the plant. This seriously degrades the utilitarian value of these analyses for the plant operators. In order to further develop PSA as a supervisory and operational optimisation instrument, both authors consider it to be appropriate to bring together the specific know-how of analysts, manufacturers, plant operators and experts. (orig.) [de

Safety Climate of Ab-Initio Flying Training Organizations: The Case of an Australian Tertiary (Collegiate) Aviation Program

OpenAIRE

Gao, Yi; Rajendran, Natalia

2017-01-01

A healthy safety culture is essential to the safe operation of any aviation organization, including flight schools. This study aimed to assess the safety climate of an Australian tertiary (collegiate) aviation program using a self-constructed instrument. Factor analysis of the instrument identified four safety themes, which are Safety Reporting Culture, Safety Reporting Procedure, Organizational Culture and Practice, and General Safety Knowledge. The responses of student pilots suggested that...

Nuclear safety in Slovak Republic. Status of safety improvements

International Nuclear Information System (INIS)

Toth, A.

1999-01-01

Status of the safety improvements at Bohunice V-1 units concerning WWER-440/V-230 design upgrading were as follows: supplementing of steam generator super-emergency feed water system; higher capacity of emergency core cooling system; supplementing of automatic links between primary and secondary circuit systems; higher level of secondary system automation. The goal of the modernization program for Bohunice V-1 units WWER-440/V-230 was to increase nuclear safety to the level of the proposals and IAEA recommendations and to reach probability goals of the reactor concerning active zone damage, leak of radioactive materials, failures of safety systems and damage shields. Upgrading program for Mochovce NPP - WWER-440/V-213 is concerned with improving the integrity of the reactor pressure vessel, steam generators 'leak before break' methods applied for the NPP, instrumentation and control of safety systems, diagnostic systems, replacement of in-core monitoring system, emergency analyses, pressurizers safety relief valves, hydrogen removal system, seismic evaluations, non-destructive testing, fire protection. Implementation of quality assurance has a special role in improvement of operational safety activities as well as safety management and safety culture, radiation protection, decommissioning and waste management and training. The Year 2000 problem is mentioned as well

Does Class-Size Reduction Close the Achievement Gap? Evidence from TIMSS 2011

Science.gov (United States)

Li, Wei; Konstantopoulos, Spyros

2017-01-01

Policies about reducing class size have been implemented in the US and Europe in the past decades. Only a few studies have discussed the effects of class size at different levels of student achievement, and their findings have been mixed. We employ quantile regression analysis, coupled with instrumental variables, to examine the causal effects of…

76 FR 53353 - Proposed Amendment of Class E Airspace; Carroll, IA

Science.gov (United States)

2011-08-26

...-0845; Airspace Docket No. 11-ACE-19] Proposed Amendment of Class E Airspace; Carroll, IA AGENCY... action proposes to amend Class E airspace at Carroll, IA. Decommissioning of the Carroll non-directional beacon (NDB) at Arthur N. Neu Airport, Carroll, IA, has made this action necessary for the safety and...

76 FR 66870 - Proposed Amendment of Class E Airspace; Rugby, ND

Science.gov (United States)

2011-10-28

...-0433; Airspace Docket No. 11-AGL-12] Proposed Amendment of Class E Airspace; Rugby, ND AGENCY: Federal... proposes to amend Class E airspace at Rugby, ND. Decommissioning of the Rugby non-directional beacon (NDB) at Rugby Municipal Airport, Rugby, ND, has made this action necessary for the safety and management...

75 FR 43884 - Proposed Amendment of Class E Airspace; Searcy, AR

Science.gov (United States)

2010-07-27

...-1182; Airspace Docket No. 09-ASW-37] Proposed Amendment of Class E Airspace; Searcy, AR AGENCY: Federal... proposes to amend Class E airspace at Searcy, AR. Decommissioning of the Searcy non-directional beacon (NDB) at Searcy Municipal Airport, Searcy, AR, has made this action necessary for the safety and management...

An international nuclear safety regime

International Nuclear Information System (INIS)

Rosen, M.

1995-01-01

For all the parties involved with safe use of nuclear energy, the opening for signature of the 'Convention on Nuclear Safety' (signed by 60 countries) and the ongoing work to prepare a 'Convention on Radioactive Waste Safety' are particularly important milestones. 'Convention on Nuclear Safety' is the first legal instrument that directly addresses the safety of nuclear power plants worldwide. The two conventions are only one facet of international cooperation to enhance safety. A review of some cooperative efforts of the past decades, and some key provisions of the new safety conventions, presented in this paper, show how international cooperation is increasing nuclear safety worldwide. The safety philosophy and practices involved with legal framework for the safe use of nuclear power will foster a collective international involvement and commitment. It will be a positive step towards increasing public confidence in nuclear power

Plutonium finishing plant safety systems and equipment list

International Nuclear Information System (INIS)

Bergquist, G.G.

1995-01-01

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

Safety functions and component classification for BWR, PWR and PTR

International Nuclear Information System (INIS)

1979-01-01

The Safety Guide forms part of the IAEA programme, referred to as the NUSS programme (Nuclear Safety Standards), for establishing Codes of Practice and Safety Guides relating to thermal neutron power plants. The present Safety Guide has the following chapters: safety functions, ranking of safety functions, assignment of safety class requirements. Design requirements for structural integrity of boundaries of fluid-retaining components are also discussed

Software Quality Assurance for Nuclear Safety Systems

International Nuclear Information System (INIS)

Sparkman, D R; Lagdon, R

2004-01-01

-critical software and applies the highest level of rigor for those systems. DOE has further defined a risk approach to nuclear safety system software consistent with the analyses required for operation of nuclear facilities. This requires the grading of software in terms of safety class and safety significant structures, systems and components (SSCs). Safety-class SSCs are related to public safety where as safety-significant SSCs are identified for specific aspects of defense-in-depth and worker safety. Industry standards do not directly categorize nuclear safety software and DOE sites are not consistent in their approach to nuclear safety software quality assurance. DOE is establishing a more detailed graded approach for software associated with safety class and safety significant systems. This paper presents the process and results that DOE utilized to develop a detailed classification scheme for nuclear safety software

Questionnaire report of safety control on instrument in nuclear medicine laboratory

International Nuclear Information System (INIS)

1987-01-01

A questionaire survey concerning the safety of equipment and facilities used in nuclear medicine laboratories was made in order to clarify the incidence of accidents during nuclear medicine testing. The questionaire consists of two parts. One part contains questions regarding the testing personnel, facilities, equipment and maintenance and management of the equipment. The other part deals with accidents that had occurred within the areas under management, potential risks that may cause accidents, measures to improve safety management, troubles with and failure of equipment, and requests and opinions directed to equipment manufactures. It is concluded from results of the survey that to raise the safety of equipment, so-called man-machine interfaces should be improved by increasing the durability of equipment and performance of the personnel operating the equipment while reducing the physical and mental effects on the persons subjected to testing. Systematic educational measures, including lecture meetings and training courses, are required to raise the consciousness of personnel. Such education and training should cover safety handling techniques, including those for checking of equipment and for instructing and helping the persons under testing. (Nogami, K.)

A study of the modifications of nuclear instrumentation systems for JRR-2

International Nuclear Information System (INIS)

Azim, Mohammad; Horiki, Ooichiro; Sato, Mitsugu

1978-04-01

In this report a comparative study has been carried out between the original A.M.F. design and the modified design for the nuclear instrumentation systems of the Research Reactor JRR-2, at the Tokai Research Establishment of JAERI. Due to a fire accident in the control room, in July 1968, the originally designed nuclear instrumentation systems, using conventional vacuum tube circuits, were destroyed and were replaced by the modified design, incorporating solid state linear integrated circuits as basic circuit components. The results of the reactor instrumentation systems modification at JRR-2 are very encouraging as the operating efficiency of the Reactor registered an improvement of 43%. Moreover the safety aspects have been fully taken care of in the new design and the reactor is well guarded against all possible instrument failures and human errors. This report presents the basic theory of operation of the two designs alongwith a comparative safety analysis. (auth.)

Development of the evaluation instrument use CIPP on the implementation of project assessment topic optik

Science.gov (United States)

Asfaroh, Jati Aurum; Rosana, Dadan; Supahar

2017-08-01

This research aims to develop an evaluation instrument models CIPP valid and reliable as well as determine the feasibility and practicality of an evaluation instrument models CIPP. An evaluation instrument models CIPP to evaluate the implementation of the project assessment topic optik to measure problem-solving skills of junior high school class VIII in the Yogyakarta region. This research is a model of development that uses 4-D. Subject of product trials are students in class VIII SMP N 1 Galur and SMP N 1 Sleman. Data collection techniques in this research using non-test techniques include interviews, questionnaires and observations. Validity in this research was analyzed using V'Aikens. Reliability analyzed using ICC. This research uses 7 raters are derived from two lecturers expert (expert judgment), two practitioners (science teacher) and three colleagues. The results of this research is the evaluation's instrument model of CIPP is used to evaluate the implementation of the implementation of the project assessment instruments. The validity result of evaluation instrument have V'Aikens values between 0.86 to 1, which means a valid and 0.836 reliability values into categories so well that it has been worth used as an evaluation instrument.

World class manufacturing in metallurgical enterprise

Directory of Open Access Journals (Sweden)

B. Gajdzik

2013-01-01

Full Text Available World Class Manufacturing (WCM assumes increase of efficiency of the company by elimination of all the losses, wastage and dangers of safety. In ArcelorMittal the concept of WCM is implemented in particular enterprises within the capital group. In this publication the activities conducted in some of those enterprises are described.

K West integrated water treatment system subproject safety analysis document

International Nuclear Information System (INIS)

SEMMENS, L.S.

1999-01-01

This Accident Analysis evaluates unmitigated accident scenarios, and identifies Safety Significant and Safety Class structures, systems, and components for the K West Integrated Water Treatment System

K West integrated water treatment system subproject safety analysis document

Energy Technology Data Exchange (ETDEWEB)

SEMMENS, L.S.

1999-02-24

This Accident Analysis evaluates unmitigated accident scenarios, and identifies Safety Significant and Safety Class structures, systems, and components for the K West Integrated Water Treatment System.

NASA SMD Airborne Science Capabilities for Development and Testing of New Instruments

Science.gov (United States)

Fladeland, Matthew

2015-01-01

The SMD NASA Airborne Science Program operates and maintains a fleet of highly modified aircraft to support instrument development, satellite instrument calibration, data product validation and earth science process studies. This poster will provide an overview of aircraft available to NASA researchers including performance specifications and modifications for instrument support, processes for requesting aircraft time and developing cost estimates for proposals, and policies and procedures required to ensure safety of flight.

Neutronic control instrumentation of protection systems

International Nuclear Information System (INIS)

Furet, J.

1977-01-01

The aims of neutronic control instrumentation are briefly recalled and the present status of materials research and development is presented. As for the out-of-pile instrumentation, emphasis is put on the reliability and efficiency of the detectors and the new solutions of electric signal processing. The possible reactivity measurements at rest are examined. As for in-pile instrumentation results relating to mobile detectors of the type of miniaturized fission chambers are presented. The radiation tests on course of development for several years in the working conditions of neutron self-powdered detectors are analyzed so as to show that their use as built-in in-core instrumentation is to be envisaged at short term. Basic options inherent to the 'Nuclear Safety' philosophy that define the protection system are recalled. A definition and a justification of the performance testing of the instrumentation at rest and in-service are then derived. Some new solutions are envisaged for processing the digital data obtained from the various sensors . A quality control of the materials setting conditions (especially electric noise) ensures a high reliability and availability of the materials involved in the neutron control and the protection system in working conditions [fr

Minilaparoscopic hysterectomy made easy: first report on alternative instrumentation and new integrated energy platform.

Science.gov (United States)

Ng, Ying Woo; Lim, Li Min; Fong, Yoke Fai

2014-05-01

Minilaparoscopy is an attractive approach for hysterectomy due to advantages such as reduced morbidities and enhanced cosmesis. However, it has not been popularized due to the lack of suitable instruments and high technical demand. We aim to highlight the first case of minilaparoscopic hysterectomy reported in Asia and the use of a new integrated energy platform, Thunderbeat. We would like to propose an alternative method of instrumentation, so as to improve the feasibility and safety of minilaparoscopic hysterectomy. The first minilaparoscopic hysterectomy in Singapore was successfully completed using the alternative instrumentation and new energy platform. There was no conversion or complication during the surgery. The patient recovered uneventfully. To our knowledge, this is the first report on the use of such alternative instrumentation. This approach in instrumentation and the new energy platform will improve the feasibility and speed of the surgery and ensure safety in our patients. © 2014 The Authors. Journal of Obstetrics and Gynaecology Research © 2014 Japan Society of Obstetrics and Gynecology.

Renovation of PARR instrumentation and controls

International Nuclear Information System (INIS)

Karim, A.; Haq, I.; Akhtar, K.M.; Alam, G.D.

1987-01-01

The Pakistan research reactor (PARR) was commissioned in 1965 and operated since then in accordance with the requirements. In the first instance, it was proposed that the controls and instrumentation be modernized according to the state of current technology and for meeting the more stringent safety, and operational needs. A computer has been added for data acquisition, logging and analysis. A closed circuit television system has been installed to monitor access of personnel to the reactor building and for viewing the reactor core with an underwater camera. This report gives a brief account of the old instrumentation and some details of the new replacements. (orig./A.B)

Experiment to evaluate software safety

International Nuclear Information System (INIS)

Soubies, B.; Henry, J.Y.

1994-01-01

The process of licensing nuclear power plants for operation consists of mandatory steps featuring detailed examination of the instrumentation and control system by the safety authorities, including softwares. The criticality of these softwares obliges the manufacturer to develop in accordance with the IEC 880 standard 'Computer software in nuclear power plant safety systems' issued by the International Electronic Commission. The evaluation approach, a two-stage assessment is described in detail. In this context, the IPSN (Institute of Protection and Nuclear Safety), the technical support body of the safety authority uses the MALPAS tool to analyse the quality of the programs. (R.P.). 4 refs

Spallation Neutron Source Accelerator Facility Target Safety and Non-safety Control Systems

International Nuclear Information System (INIS)

Battle, Ronald E.; DeVan, B.; Munro, John K. Jr.

2006-01-01

The Spallation Neutron Source (SNS) is a proton accelerator facility that generates neutrons for scientific researchers by spallation of neutrons from a mercury target. The SNS became operational on April 28, 2006, with first beam on target at approximately 200 W. The SNS accelerator, target, and conventional facilities controls are integrated by standardized hardware and software throughout the facility and were designed and fabricated to SNS conventions to ensure compatibility of systems with Experimental Physics Integrated Control System (EPICS). ControlLogix Programmable Logic Controllers (PLCs) interface to instruments and actuators, and EPICS performs the high-level integration of the PLCs such that all operator control can be accomplished from the Central Control room using EPICS graphical screens that pass process variables to and from the PLCs. Three active safety systems were designed to industry standards ISA S84.01 and IEEE 603 to meet the desired reliability for these safety systems. The safety systems protect facility workers and the environment from mercury vapor, mercury radiation, and proton beam radiation. The facility operators operated many of the systems prior to beam on target and developed the operating procedures. The safety and non-safety control systems were tested extensively prior to beam on target. This testing was crucial to identify wiring and software errors and failed components, the result of which was few problems during operation with beam on target. The SNS has continued beam on target since April to increase beam power, check out the scientific instruments, and continue testing the operation of facility subsystems

Managing changes of location classes of gas pipelines

Energy Technology Data Exchange (ETDEWEB)

Cunha, Sergio B; Sousa, Antonio Geraldo de [PETROBRAS Transporte S.A. (TRANSPETRO), Rio de Janeiro, RJ (Brazil)

2009-12-19

Most of the gas pipeline design codes utilize a class location system, where the design safety factor and the hydrostatic test factor are determined according to the population density in the vicinities of the pipeline route. Consequently, if an operator is requested or desires to maintain an existing gas pipeline in compliance with its design code, it will reduce the operational pressure or replace pipe sections to increase the wall thickness whenever a change in location class takes place. This article introduces an alternative methodology to deal with changes in location classes of gas pipelines. Initially, selected codes that utilize location class systems are reviewed. Afterwards, a model for the area affected by an ignition following a natural gas pipeline leak is described. Finally, a methodology to determine the MAOP and third part damage mitigation measures for gas transport pipelines that underwent changes in location class is presented. (author)

New instrumentation for the IPR-R1 reactor of CDTN

International Nuclear Information System (INIS)

Carvalho, P.V.R. de.

1992-01-01

The Nuclear Engineering Institute reactor instrumentation area has developed systems and equipment for reactor operation and safety. In such way, the new I and C for IEN Argonauta reactor and the nuclear instrumentation for IPEN critical facility were built. This paper describes our real work, the new I and C systems for IPR-R1, a Triga type reactor, located at CDTN (Belo Horizonte - MG). (author)

49 CFR 572.200 - Instrumentation and test conditions.

Science.gov (United States)

2010-10-01

... TRAFFIC SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) ANTHROPOMORPHIC TEST DEVICES IIsD... Test, unless noted otherwise. (g) All instrumented response signal measurements shall be treated to the... conform to the Sign Convention For Vehicle Crash Testing, Surface Vehicle Information Report, SAE J1733...

Type Classes for Lightweight Substructural Types

Directory of Open Access Journals (Sweden)

Edward Gan

2015-02-01

Full Text Available Linear and substructural types are powerful tools, but adding them to standard functional programming languages often means introducing extra annotations and typing machinery. We propose a lightweight substructural type system design that recasts the structural rules of weakening and contraction as type classes; we demonstrate this design in a prototype language, Clamp. Clamp supports polymorphic substructural types as well as an expressive system of mutable references. At the same time, it adds little additional overhead to a standard Damas-Hindley-Milner type system enriched with type classes. We have established type safety for the core model and implemented a type checker with type inference in Haskell.

Safety assessment of computerized instrumentation and control for nuclear power plants

International Nuclear Information System (INIS)

Fride, B.; Henry, J.Y.; Manners, S.

1996-01-01

France's latest 1400 MWe 'N4' generation of Pressurised Water Reactors (PWR) use distributed programmable control systems interconnected by data networks. The protection system is also software based. IPSN have the task of evaluating the safety demonstration before the government safety authority (DSIN) give the licensee (EDF) permission to fuel the reactor and to raise power. Some of the different aspects of the evaluation carried out and the methodologies used for assessing the C and I are presented. (author)

[Learning from aviation - how to increase patient safety in surgery].

Science.gov (United States)

Renz, B; Angele, M K; Jauch, K-W; Kasparek, M S; Kreis, M; Müller, M H

2012-04-01

During the last years attempts have been made to draw lessons from aviation to increase patient safety in medicine. In particular similar conditions are present in surgery as pilots and surgeons may have to support high physical and mental pressure. The use of a few safety instruments from aviation is feasible in an attempt to increase safety in surgery. First a "root caused" accident research may be established. This is achievable by morbidity and mortality conferences and critical incident reporting systems (CIRS). Second, standard operating procedures may assure a uniform mental model of team members. Furthermore, crew resource management illustrates a strategy and attitude concept, which is applicable in all situations. Safety instruments from aviation, therefore, seem to have a high potential to increase safety in surgery when properly employed. © Georg Thieme Verlag KG Stuttgart ˙ New York.

Instrument evaluation no. 11. ESI nuclear model 271 C contamination monitor

CERN Document Server

Burgess, P H

1978-01-01

The various radiations encountered in radiological protection cover a wide range of energies and radiation measurements have to he carried out under an equally broad spectrum of environmental conditions. This report is one of a series intended to give information on the performance characteristics of radiological protection instruments, to assist in the selection of appropriate instruments for a given purpose, to interpret the results obtained with such instruments, and, in particular, to know the likely sources and magnitude of errors that might be associated with measurements in the field. The radiation, electrical and environmental characteristics of radiation protection instruments are considered together with those aspects of the construction which make an instrument convenient for routine use. To provide consistent criteria for instrument performance, the range of tests performed on any particular class of instrument, the test methods and the criteria of acceptable performance are based broadly on the a...

Instrument evaluation no. 17. Wallac automatic alarm dosimeter type RAD21

CERN Document Server

Burgess, P H

1980-01-01

The various radiations encountered in radiological protection cover a wide range of energies and radiation measurements have to be carried out under an equally broad spectrum of environmental conditions. This report is one of a series intended to give information on the performance characteristics of radiological protection instruments, to assist in the selection of appropriate instruments for a given purpose, to interpret the results obtained with such instruments, and, in particular, to know the likely sources and magnitude of errors that might be associated with measurements in the field. The radiation, electrical and environmental characteristics of radiation protection instruments are considered together with those aspects of the construction which make an instrument convenient for routine use. To provide consistent criteria for instrument performance, the range of tests performed on any particular class of instrument, the test methods and the criteria of acceptable performance are based broadly on the a...

Human machine interface for research reactor instrumentation and control system

International Nuclear Information System (INIS)

Mohd Sabri Minhat; Mohd Idris Taib; Izhar Abu Hussin; Zareen Khan Abdul Jalil Khan; Nurfarhana Ayuni Joha

2010-01-01

Most present design of Human Machine Interface for Research Reactor Instrumentation and Control System is modular-based, comprise of several cabinets such as Reactor Protection System, Control Console, Information Console as well as Communication Console. The safety, engineering and human factor will be concerned for the design. Redundancy and separation of signal and power supply are the main factor for safety consideration. The design of Operator Interface absolutely takes consideration of human and environmental factors. Physical parameters, experiences, trainability and long-established habit patterns are very important for user interface, instead of the Aesthetic and Operator-Interface Geometry. Physical design for New Instrumentation and Control System of RTP are proposed base on the state-of- the-art Human Machine Interface design. (author)

CLASS: The Cosmology Large Angular Scale Surveyor

Science.gov (United States)

Essinger-Hileman, Thomas; Ali, Aamir; Amiri, Mandana; Appel, John W.; Araujo, Derek; Bennett, Charles L.; Boone, Fletcher; Chan, Manwei; Cho, Hsiao-Mei; Chuss, David T.;

77 FR 27666 - Proposed Amendment of Class E Airspace; Bar Harbor, ME

Science.gov (United States)

2012-05-11

...-1366; Airspace Docket No. 11-ANE-13] Proposed Amendment of Class E Airspace; Bar Harbor, ME AGENCY... action proposes to amend Class E Airspace at Bar Harbor, ME, as the Surry Non-Directional Radio Beacon... Hancock County-Bar Harbor Airport. This action would enhance the safety and airspace management of...

Instrumentation Cables Test Plan

Energy Technology Data Exchange (ETDEWEB)

Muna, Alice Baca [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); LaFleur, Chris Bensdotter [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2016-10-01

A fire at a nuclear power plant (NPP) has the potential to damage structures, systems, and components important to safety, if not promptly detected and suppressed. At Browns Ferry Nuclear Power Plant on March 22, 1975, a fire in the reactor building damaged electrical power and control systems. Damage to instrumentation cables impeded the function of both normal and standby reactor coolant systems, and degraded the operators’ plant monitoring capability. This event resulted in additional NRC involvement with utilities to ensure that NPPs are properly protected from fire as intended by the NRC principle design criteria (i.e., general design criteria 3, Fire Protection). Current guidance and methods for both deterministic and performance based approaches typically make conservative (bounding) assumptions regarding the fire-induced failure modes of instrumentation cables and those failure modes effects on component and system response. Numerous fire testing programs have been conducted in the past to evaluate the failure modes and effects of electrical cables exposed to severe thermal conditions. However, that testing has primarily focused on control circuits with only a limited number of tests performed on instrumentation circuits. In 2001, the Nuclear Energy Institute (NEI) and the Electric Power Research Institute (EPRI) conducted a series of cable fire tests designed to address specific aspects of the cable failure and circuit fault issues of concern1. The NRC was invited to observe and participate in that program. The NRC sponsored Sandia National Laboratories to support this participation, whom among other things, added a 4-20 mA instrumentation circuit and instrumentation cabling to six of the tests. Although limited, one insight drawn from those instrumentation circuits tests was that the failure characteristics appeared to depend on the cable insulation material. The results showed that for thermoset insulated cables, the instrument reading tended to drift

Safety assessment of computerized instrumentation and control for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Fride, B.; Henry, J.Y.; Manners, S.

1996-12-31

France`s latest 1400 MWe `N4` generation of Pressurised Water Reactors (PWR) use distributed programmable control systems interconnected by data networks. The protection system is also software based. IPSN have the task of evaluating the safety demonstration before the government safety authority (DSIN) give the licensee (EDF) permission to fuel the reactor and to raise power. Some of the different aspects of the evaluation carried out and the methodologies used for assessing the C and I are presented. (author). 3 refs.

Advanced Measuring (Instrumentation Methods for Nuclear Installations: A Review

Directory of Open Access Journals (Sweden)

Wang Qiu-kuan

2012-01-01

Full Text Available The nuclear technology has been widely used in the world. The research of measurement in nuclear installations involves many aspects, such as nuclear reactors, nuclear fuel cycle, safety and security, nuclear accident, after action, analysis, and environmental applications. In last decades, many advanced measuring devices and techniques have been widely applied in nuclear installations. This paper mainly introduces the development of the measuring (instrumentation methods for nuclear installations and the applications of these instruments and methods.

Analysis of mechanical preparations in extracted teeth using ProTaper rotary instruments: value of the safety quotient.

Science.gov (United States)

Blum, J Y; Machtou, P; Ruddle, C; Micallef, J P

2003-09-01

The purpose of this study was to apply the Endographe to analyze the vertical forces and torque developed during mechanical preparations in extracted teeth. The data collected in this study may be used to calculate the safety quotient (SQ) as proposed by J.T. McSpadden. The SQ formula is defined as the torque required to break a file at D3 divided by the mean working torque required to cut dentin. The Endographe is a unique force-analyzer device equipped to measure, record, and generate graphs of the vertical forces and torque exerted during root canal preparation. All preparations were performed by endodontists in roots with narrow, more restrictive canals, larger, more open canals, or in roots sectioned in two halves. All canals, including the sectioned canals, were prepared with ProTaper files in accordance with the manufacturer's guidelines for use. For narrow canals, the mean values of the generated vertical forces (g) and torque (g.cm) varied from 80 (+/- 20) g (SX) to 232 (+/- 60) g (F2) and from 80 (+/- 24) g x cm (F1) to 150 (+/- 45) g x cm (S2), respectively. For large canals, the mean values of the generated vertical forces (g) and torque (g x cm) varied from 80 (+/- 20) g (SX) to 340 (+/- 20) g (F1) and from 31 (+/- 9) g x cm (S2) to 96 (+/- 35) g x cm (SX), respectively. The SQ varied from 0.93 to 7.95 for narrow canals and from 1.58 to 14.50 for large canals. The SQ is intended to provide values that can be analyzed to predict whether a rotary file will have a tendency to break or will work safely during clinical use. However, if the formula is going to provide useful information, it must index the "rotation to failure torque" with the "mean working torque" at a specific location along the cutting blades of a file. Additionally, this mathematical formula does not account for factors such as the concentration of forces, the way the instruments are used, or the wear of the instruments. A precise protocol for canal preparation should emphasize using

Nuclear safety: an international approach: the convention on nuclear safety

International Nuclear Information System (INIS)

Rosen, M.

1994-01-01

This paper is a general presentation of the IAEA Convention on Nuclear Safety which has already be signed by 50 countries and which is the first legal instrument that directly addresses the safety of nuclear power plants worldwide. The paper gives a review of its development and some key provisions for a better understanding of how this agreement will operate in practice. The Convention consists of an introductory preamble and four chapters consisting of 35 articles dealing with: the principal objectives, definitions and scope of application; the various obligations (general provisions, legislation, responsibility and regulation, general safety considerations taking into account: the financial and human resources, the human factors, the quality assurance, the assessment and verification of safety, the radiation protection and the emergency preparedness; the safety of installations: sitting, design and construction, operation); the periodic meetings of the contracting parties to review national reports on the measures taken to implement each of the obligations, and the final clauses and other judicial provisions common to international agreements. (J.S.). 1 append

Cost prediction model for various payloads and instruments for the Space Shuttle Orbiter

Science.gov (United States)

Hoffman, F. E.

1984-01-01

The following cost parameters of the space shuttle were undertaken: (1) to develop a cost prediction model for various payload classes of instruments and experiments for the Space Shuttle Orbiter; and (2) to show the implications of various payload classes on the cost of: reliability analysis, quality assurance, environmental design requirements, documentation, parts selection, and other reliability enhancing activities.

Causes and effects of vital instrumentation and control power supply bus failures

International Nuclear Information System (INIS)

Muhlheim, M.D.; Murphy, G.A.

1987-01-01

This article presents the results of a study in which the objective was to evaluate nuclear power-plant operating experience to identify the causes and the effects of vital instrumentation and control (I and C) power supply bus failures. Vital I and C power is normally provided to essential instrumentation and controls through either vital d-c or a-c power supply systems. The vital d-c power supply system generally provides control power for starting the diesel generators, for operating electrical circuit breakers, and for controlling various logic circuits. The vital d-c power system also supplies vital a-c power through an inverter. The vital a-c power supply system generally feeds the reactor protection system channels, the engineered safety features actuation system channels, and critical instrumentation in the control room. The leading cause of vital bus failures is inverter failures; other causes are human errors, battery charger failures, and miscellaneous failures. The effects of these failures are that the margin of safety can be degraded by (1) denying key information to the operators, (2) inducing plant transients, (3) causing safety injection actuations, and (4) causing the loss of shutdown cooling flow

Basic fracture toughness requirements for ferritic materials of nuclear class pressure retaining equipment in NPP

International Nuclear Information System (INIS)

Ning Dong; Yao Weida

2005-01-01

In this paper, theory basis on cold brittleness and anti-brittle fracture design of ferritic materials are introduced summarily and fracture toughness requirements for ferritic materials in ASME code for nuclear safety class pressure retaining equipment in NPP are summarized and evaluated. The results show that notch impact toughness requirements for materials relate to nuclear safety class of materials so as to ensure that brittle fracture of retaining pressure boundary in NPP can not occur. (authors)

The new M-class of Mercedes Benz; Die neue M-Klasse von Mercedes-Benz

Energy Technology Data Exchange (ETDEWEB)

Liebl, Johannes; Siebenpfeiffer, Wolfgang (eds.)

2011-12-15

The contribution under consideration presents the new M-class of Mercedes-Benz describing the following aspects: Design, positioning, design, interior equipment, motor/gear, consumption/emission, powertrain, chassis, NVH/comfort/aerodynamics, testing, integral safety, passive safety, driver assistance system.

Temperature and level measurements realized for Nuclear Safety Level Improvement of Slovak NPPs

International Nuclear Information System (INIS)

Badiar, S.; Slanina, M.; Stanc, S.; Golan, P.; Krupa, J.

2001-01-01

Process of continual safety improvement in the individual Slovak nuclear power plants has been in progress since the beginning of nineties with the objective to upgrade the safety level of units in operation up to the European standards. In the framework of these activities, safety instrumentation systems with 1E qualification for the control of WWER reactor coolant systems were built and added. Methods for implementation of safety instrumentation systems for monitoring temperature and level in reactor coolant systems in the particular plants in Slovakia are presented showing the objectives and methods of their implementation. (Authors)

Proceedings of the third national symposium on advances in control and instrumentation

International Nuclear Information System (INIS)

Tiwari, A.P.; Chauhan, Vikas; Wakankar, Amol; Karnani, Urvashi; Saxena, Nikhil; Haridasan, Remya; Mishra, Elina

2014-01-01

Control and Instrumentation systems play a vital role in nuclear energy, defence, aerospace, discovery science and transportation sectors. These systems are deployed in safety-critical and mission critical applications as well. Advances in these fields have profound impact on performance, quality, reliability, safety, security and economics of these systems. While the basic theme of the symposium is control and instrumentation, this time the coverage of the symposium has been extended to defence, aerospace, discovery science and transportation sectors besides nuclear energy. This was been motivated by the need for synergy and sharing of experiences among these vital, high technology sectors. Papers relevant to INIS are indexed separately

Upgrade of Instrumentation for Purdue Reactor PUR-1

International Nuclear Information System (INIS)

Revankar, S.T.; Merritt, E.; Bean, R.

2000-01-01

The major objective of this program was to upgrade and replace instruments and equipment that significantly improve the performance, control and operational capability of the Purdue University nuclear reactor (PUR-1). Under this major objective two projects on instrument upgrade were implemented. The first one was to convert the vacuum tube control and safety amplifiers (CSA) to solid state electronics, and the other was to upgrade the electrical and electronic shielding. This report is the annual report and gives the efforts and progress achieved on these two projects from July 1999 to June 2000

Development of a patient safety climate survey for Chinese hospitals: cross-national adaptation and psychometric evaluation.

Science.gov (United States)

Zhu, Junya; Li, Liping; Zhao, Hailei; Han, Guangshu; Wu, Albert W; Weingart, Saul N

2014-10-01

Existing patient safety climate instruments, most of which have been developed in the USA, may not accurately reflect the conditions in the healthcare systems of other countries. To develop and evaluate a patient safety climate instrument for healthcare workers in Chinese hospitals. Based on a review of existing instruments, expert panel review, focus groups and cognitive interviews, we developed items relevant to patient safety climate in Chinese hospitals. The draft instrument was distributed to 1700 hospital workers from 54 units in six hospitals in five Chinese cities between July and October 2011, and 1464 completed surveys were received. We performed exploratory and confirmatory factor analyses and estimated internal consistency reliability, within-unit agreement, between-unit variation, unit-mean reliability, correlation between multi-item composites, and association between the composites and two single items of perceived safety. The final instrument included 34 items organised into nine composites: institutional commitment to safety, unit management support for safety, organisational learning, safety system, adequacy of safety arrangements, error reporting, communication and peer support, teamwork and staffing. All composites had acceptable unit-mean reliabilities (≥0.74) and within-unit agreement (Rwg ≥0.71), and exhibited significant between-unit variation with intraclass correlation coefficients ranging from 9% to 21%. Internal consistency reliabilities ranged from 0.59 to 0.88 and were ≥0.70 for eight of the nine composites. Correlations between composites ranged from 0.27 to 0.73. All composites were positively and significantly associated with the two perceived safety items. The Chinese Hospital Survey on Patient Safety Climate demonstrates adequate dimensionality, reliability and validity. The integration of qualitative and quantitative methods is essential to produce an instrument that is culturally appropriate for Chinese hospitals

Proposal for the classification of scenarios for deep geological repositories in probability classes

International Nuclear Information System (INIS)

Beuth, Thomas

2013-03-01

The provided report was elaborated in the framework of the project 3609R03210 ''Research and Development for Proof of the long-term Safety of Deep Geological Repositories''. It contains a proposal for a methodology that enables the assignment of developed scenarios in the frame of Safety Cases to defined probability classes. The assignment takes place indirectly through the categorization of the defining relevant factors (so-called FEP: Features, Events and Processes) of the respective scenarios also in probability classes. Therefore, decision trees and criteria were developed for the categorization of relevant factors in classes. Besides the description of the methodology another focal point of the work was the application of the method taking into account a defined scenario. By means of the scenario the different steps of the method and the decision criteria were documented, respectively. In addition, potential subjective influences along the path of decisions regarding the assignment of scenarios in probability classes were identified.

Labour Universities: Physical Education and the indoctrination of the working class

OpenAIRE

Delgado Granados, Patricia; Ramírez Macías, Gonzalo

2014-01-01

This paper explores the role of Physical Education in Labour Universities (1955-1978) during Franco's regime as an instrument of indoctrination and declassing of the working class. The conclusions obtained after the study and the analysis of various primary sources indicate that, initially, Physical Education was used as an instrument of indoctrination for the purposes of achieving the social and ideological model of Franco's regime after the Fascist uprising (1936-1939). However, this initia...

Development of digital safety system logic and control

International Nuclear Information System (INIS)

Nishikawa, H.; Sakamoto, H.

1995-01-01

Advanced-BWR (ABWR) uses total digital control and instrumentation (C and I) system. In particular, ABWR adopts a newly developed safety system using advanced digital technology. In the presentation the digital safety system design, manufacturing and factory validation test method are shortly overviewed. The digital safety system consists of micro-processor based digital controllers, data and information transmission by optical fibers and human-machine interface using color flat displays. This new developed safety system meet the nuclear safety requirements such as high reliability, independence of divisions, operability and maintainability. (2 refs., 4 figs., 1 tab.)

Critical Characteristics of Radiation Detection System Components to be Dedicated for use in Safety Class and Safety Significant System

International Nuclear Information System (INIS)

DAVIS, S.J.

2000-01-01

This document identifies critical characteristics of components to be dedicated for use in Safety Significant (SS) Systems, Structures, or Components (SSCs). This document identifies the requirements for the components of the common, radiation area, monitor alarm in the WESF pool cell. These are procured as Commercial Grade Items (CGI), with the qualification testing and formal dedication to be performed at the Waste Encapsulation Storage Facility (WESF) for use in safety significant systems. System modifications are to be performed in accordance with the approved design. Components for this change are commercially available and interchangeable with the existing alarm configuration This document focuses on the operational requirements for alarm, declaration of the safety classification, identification of critical characteristics, and interpretation of requirements for procurement. Critical characteristics are identified herein and must be verified, followed by formal dedication, prior to the components being used in safety related applications

Procedures and instrumentation for sodium boiling experiments in EBR-II

International Nuclear Information System (INIS)

Crowe, R.D.

1976-01-01

The development of instrumentation capable of detecting localized coolant boiling in a liquid metal cooled breeder reactor (LMFBR) has a high priority in fast reactor safety. The detection must be rapid enough to allow corrective action to be taken before significant damage occurs to the core. To develop and test a method of boiling detection, it is desirable to produce boiling in a reactor and thereby introduce a condition in the reactor the original design concepts were chosen to preclude. The proposed boiling experiments are designed to safely produce boiling in the subassembly of a fast reactor and provide the information to develop boiling detection instrumentation without core damage or safety compromise. The experiment consists of the operation of two separate subassemblies, first, a gamma heated boiling subassembly which produces non-typical but highly conservative boiling and then a fission heated subassembly which simulates a prototypical boiling event. The two boiling subassemblies are designed to operate in the instrumentation subassembly test facility (INSAT) of Experiment Breeder Reactor II

SNF fuel retrieval sub project safety analysis document

International Nuclear Information System (INIS)

BERGMANN, D.W.

1999-01-01

This safety analysis is for the SNF Fuel Retrieval (FRS) Sub Project. The FRS equipment will be added to K West and K East Basins to facilitate retrieval, cleaning and repackaging the spent nuclear fuel into Multi-Canister Overpack baskets. The document includes a hazard evaluation, identifies bounding accidents, documents analyses of the accidents and establishes safety class or safety significant equipment to mitigate accidents as needed

SNF fuel retrieval sub project safety analysis document

Energy Technology Data Exchange (ETDEWEB)

BERGMANN, D.W.

1999-02-24

This safety analysis is for the SNF Fuel Retrieval (FRS) Sub Project. The FRS equipment will be added to K West and K East Basins to facilitate retrieval, cleaning and repackaging the spent nuclear fuel into Multi-Canister Overpack baskets. The document includes a hazard evaluation, identifies bounding accidents, documents analyses of the accidents and establishes safety class or safety significant equipment to mitigate accidents as needed.

Instrumentation and measurement method for the ATLAS test facility

Energy Technology Data Exchange (ETDEWEB)

Yun, Byong Jo; Chu, In Chul; Eu, Dong Jin; Kang, Kyong Ho; Kim, Yeon Sik; Song, Chul Hwa; Baek, Won Pil

2007-03-15

An integral effect test loop for pressurized water reactors (PWRs), the ATLAS is constructed by thermal-hydraulic safety research division in KAERI. The ATLAS facility has been designed to have the length scale of 1/2 and area scale of 1/144 compared with the reference plant, APR1400 which is a Korean evolution type nuclear reactors. A total 1300 instrumentations is equipped in the ATLAS test facility. In this report, the instrumentation of ATLAS test facility and related measurement methods were introduced.

75 FR 23581 - Amendment of Class E Airspace; Emmetsburg, IA

Science.gov (United States)

2010-05-04

...-1153; Airspace Docket No. 09-ACE-13] Amendment of Class E Airspace; Emmetsburg, IA AGENCY: Federal... Emmetsburg, IA, adding additional controlled airspace to accommodate Area Navigation (RNAV) Standard Instrument Approach Procedures (SIAPs) at Emmetsburg Municipal Airport, Emmetsburg, IA. The FAA is taking...

77 FR 34210 - Amendment of Class E Airspace; Orlando, FL

Science.gov (United States)

2012-06-11

...-0503; Airspace Docket No. 11-ASO-19] Amendment of Class E Airspace; Orlando, FL AGENCY: Federal... Orlando, FL, as new Standard Instrument Approach Procedures have been developed at Orlando Executive... coordinates of Orlando Executive Airport, Orlando International Airport, and Kissimmee Municipal Airport...

Temelin safety monitor

International Nuclear Information System (INIS)

Mlady, O.

2000-01-01

Temelin NPP is a WWER-1000/320 two unit plant under construction, originally designed according to the standards of the former Soviet Union. After a series of reviews in the 80s, a decision was taken to upgrade the design of Temelin, including the supply of fuel and instrumentation and instrumentation and control system (I and C). Details on the current design and other related safety matters were presented to the nuclear community in a meeting organized by the IAEA in November 1994. Based upon recommendations of IAEA OSART missions, post TMI requirements and Temelin Risk Audit recommendations it was decided to perform a Probabilistic Safety Assessment within the Temelin PSA Project. The general purpose of this project was to perform systematic examination of the Temelin Unit 1 NPP for severe accident vulnerabilities by performance of a Level 1 and 2 PSA study. In addition to the completion of Temelin documented living PSA model, the decision was to develop and implement a PSA based software tool able to analyze real and scheduled plant conditions for determining the risk impact of plant configurations and on-line maintenance activities. This paper provides an overview of the key features of the Temelin Safety Monitor, describes its development activities and its current status and intended use at Temelin NPP for PSA applications. (author)

Levels of safety

International Nuclear Information System (INIS)

Povyakalo, A.A.

1996-01-01

When speaking about danger of catastrophe, it is the first level of danger. Its absence is the first level of safety. When speaking about danger of danger of catastrophe, it is the second level of danger. Its absence is the second level of safety. The paper proposes the way to formalize these ideas and use formal models to construct the states-and-event scale for a given object. The proposed approach can be applied to objects of different nature. The states-and-events scale may be used for transformation of initial objectives state-and-transitions graph to reduce bad classes of states

A root cause analysis project in a medication safety course.

Science.gov (United States)

Schafer, Jason J

2012-08-10

To develop, implement, and evaluate team-based root cause analysis projects as part of a required medication safety course for second-year pharmacy students. Lectures, in-class activities, and out-of-class reading assignments were used to develop students' medication safety skills and introduce them to the culture of medication safety. Students applied these skills within teams by evaluating cases of medication errors using root cause analyses. Teams also developed error prevention strategies and formally presented their findings. Student performance was assessed using a medication errors evaluation rubric. Of the 211 students who completed the course, the majority performed well on root cause analysis assignments and rated them favorably on course evaluations. Medication error evaluation and prevention was successfully introduced in a medication safety course using team-based root cause analysis projects.

Management of nanomaterials safety in research environment

Directory of Open Access Journals (Sweden)

Riediker Michael

2010-12-01

Full Text Available Abstract Despite numerous discussions, workshops, reviews and reports about responsible development of nanotechnology, information describing health and environmental risk of engineered nanoparticles or nanomaterials is severely lacking and thus insufficient for completing rigorous risk assessment on their use. However, since preliminary scientific evaluations indicate that there are reasonable suspicions that activities involving nanomaterials might have damaging effects on human health; the precautionary principle must be applied. Public and private institutions as well as industries have the duty to adopt preventive and protective measures proportionate to the risk intensity and the desired level of protection. In this work, we present a practical, 'user-friendly' procedure for a university-wide safety and health management of nanomaterials, developed as a multi-stakeholder effort (government, accident insurance, researchers and experts for occupational safety and health. The process starts using a schematic decision tree that allows classifying the nano laboratory into three hazard classes similar to a control banding approach (from Nano 3 - highest hazard to Nano1 - lowest hazard. Classifying laboratories into risk classes would require considering actual or potential exposure to the nanomaterial as well as statistical data on health effects of exposure. Due to the fact that these data (as well as exposure limits for each individual material are not available, risk classes could not be determined. For each hazard level we then provide a list of required risk mitigation measures (technical, organizational and personal. The target 'users' of this safety and health methodology are researchers and safety officers. They can rapidly access the precautionary hazard class of their activities and the corresponding adequate safety and health measures. We succeed in convincing scientist dealing with nano-activities that adequate safety measures and

Management of nanomaterials safety in research environment.

Science.gov (United States)

Groso, Amela; Petri-Fink, Alke; Magrez, Arnaud; Riediker, Michael; Meyer, Thierry

2010-12-10

Despite numerous discussions, workshops, reviews and reports about responsible development of nanotechnology, information describing health and environmental risk of engineered nanoparticles or nanomaterials is severely lacking and thus insufficient for completing rigorous risk assessment on their use. However, since preliminary scientific evaluations indicate that there are reasonable suspicions that activities involving nanomaterials might have damaging effects on human health; the precautionary principle must be applied. Public and private institutions as well as industries have the duty to adopt preventive and protective measures proportionate to the risk intensity and the desired level of protection. In this work, we present a practical, 'user-friendly' procedure for a university-wide safety and health management of nanomaterials, developed as a multi-stakeholder effort (government, accident insurance, researchers and experts for occupational safety and health). The process starts using a schematic decision tree that allows classifying the nano laboratory into three hazard classes similar to a control banding approach (from Nano 3--highest hazard to Nano1--lowest hazard). Classifying laboratories into risk classes would require considering actual or potential exposure to the nanomaterial as well as statistical data on health effects of exposure. Due to the fact that these data (as well as exposure limits for each individual material) are not available, risk classes could not be determined. For each hazard level we then provide a list of required risk mitigation measures (technical, organizational and personal). The target 'users' of this safety and health methodology are researchers and safety officers. They can rapidly access the precautionary hazard class of their activities and the corresponding adequate safety and health measures. We succeed in convincing scientist dealing with nano-activities that adequate safety measures and management are promoting

Medical instruments and devices principles and practices

CERN Document Server

Schreiner, Steven; Peterson, Donald R

2015-01-01

Medical Instruments and Devices: Principles and Practices originates from the medical instruments and devices section of The Biomedical Engineering Handbook, Fourth Edition. Top experts in the field provide material that spans this wide field. The text examines how biopotential amplifiers help regulate the quality and content of measured signals. It includes instruments and devices that span a range of physiological systems and the physiological scale: molecular, cellular, organ, and system. The book chronicles the evolution of pacemakers and their system operation and discusses oscillometry, cardiac output measurement, and the direct and indirect methods of measuring cardiac output. The authors also expound on the mechanics and safety of defibrillators and cover implantable stimulators, respiration, and the structure and function of mechanical ventilators. In addition, this text covers in depth: Anesthesia Delivery Electrosurgical Units and Devices Biomedical Lasers Measuring Cellular Traction Forces Blood G...

Instrumentation for status monitoring and protection of SST-1 superconducting magnets

Energy Technology Data Exchange (ETDEWEB)

Sharma, A.N., E-mail: aashoo.sharma@yahoo.com; Prasad, U.; Doshi, K.; Varmora, P.; Khristi, Y.; Patel, D.; Pradhan, S.

2016-11-15

Highlights: • Details of status monitoring instrumentation are presented. • Protection instrumentation details are presented. • Instrumentation installation details, signal conditioning and DAQ system details and the results during SST-1 operation are presented. - Abstract: Superconducting magnets of SST-1 are extensively instrumented to continuously monitor the health of magnets during machine cool-down, plasma experiments and also during the machine warm-up phase. These instrumentations include temperature sensors, flow meters, hall probes, strain gages, displacement sensors, pressure sensors and voltage taps. The number of sensors and their locations has been optimized to systematically monitor all important magnet parameters to ensure its safety. In-house developed modular signal conditioning cards have been developed for these instrumentations. The data is acquired on a Versa Module Europa bus based data acquisition system (VME DAQ). This paper gives an overview of selection, installation, laboratory scale validations, and distribution logics of these instrumentations. Results during plasma campaigns and the up-gradation aspects of these instrumentations are also discussed in this paper.

Achievements and Perspectives of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

International Nuclear Information System (INIS)

Louvat, D.; Lacoste, A.C.

2006-01-01

The Joint Convention on the Safety of Spent Fuel management and on the Safety of Radioactive Waste Management is the first legal instrument to directly address the safety of spent fuel and radioactive waste management on a global scale. The Joint Convention entered into force in 2001. This paper describes its process and its main achievements to date. The perspectives to establish of a Global Waste Safety Regime based on the Joint Convention are also discussed. (authors)

Nuclear electronic instrumentation

International Nuclear Information System (INIS)

Ramirez J, F. J.

2010-01-01

The activities carried out in the Instituto Nacional de Investigaciones Nucleares (ININ) in the field of the nuclear electronic instrumentation included those activities corresponding to the design and production of nuclear instruments in a first stage, as well as the internal activities of design, repair and maintenance that have supported to other projects of the institution during many years. It is mentioned of the presence and constant collaboration of the ININ with the IAEA in different projects and programs. Also, it is mentioned on the establishment of the Radiation Detectors Laboratory, which for their characteristics and repair capacities of radiation detectors of cooled semiconductor, it is only in their specialty. It is emphasized the investigation and the development in the field of new radiation detectors and applications, as well as the important contribution in this field, in institutions like: Mexican Petroleum, National Commission of Nuclear Safety and Safeguards and Federal Commission of Electricity. Finally a position of the future of these activities is made, considering the speed of the advances of the electronic and nuclear technology. (Author)

Analysis and Design of Implementation of Class F Airspace in the Czech Republic

Directory of Open Access Journals (Sweden)

Filip Červený

2014-05-01

Full Text Available This article analyses the airspace of the Czech Republic and suggests the implementation of class F airspace in the Czech Republic for IFR flights at uncontrolled aerodromes. It also suggests procedures and technologies for increasing of safety when performing IFR flights at these aerodromes in class F airspace.

Radiological safety related provisions and instrumentation in Indian PHWRs

International Nuclear Information System (INIS)

Ramamirtham, B.; Dabhadkar, S.B.; Sah, B.M.L.

1994-01-01

The collective radiation doses at the nuclear power plants (NPPs) world-wide have shown a significant downward trend which has resulted due to on-going efforts to keep exposures ALARA and also to meet the recently revised individual exposure limits of ICRP. In keeping with this trend a number of additional designed dose reduction features are also being incorporated in the Indian NPPs. These include better separation and shielding of radioactive systems/equipment, elimination of the use of cobalt-free materials in active systems, improved leak tightness of systems carrying heavy water, augmented ventilation and atmosphere drying systems, etc. The build-up of radiation levels in primary heat transport (PHT) system is controlled by incorporating improvements in the fuel performance and periodic system decontamination. Plant layouts have been modified, to improve the contamination control arrangements and optimum utilisation of dosimetry devices. For better control of internal exposures continuous efforts are on to make the protective gear more user-friendly. Green belts are being established around the NPPs to provide further protection against environmental impact. A number of additional radiation monitoring instruments /systems have been incorporated to provide information on radiation/activity levels, both within the plant and outside areas, particularly during emergency conditions. For processing of data provided by the large numbers of installed radiation instruments and initiating corrective/alarm actions, a computerised system (RADAS) has been provided. (author). 7 refs., 2 tabs

Safety audits/Verkehrssicherheitsaudits : ein vielsprechendes Instrument zur Förderung der Verkehrssicherheit ?

NARCIS (Netherlands)

Wegman, F.C.M. & Schagen, I.N.L.G. van

1998-01-01

Das Instrument `Verkehrssicherheitsaudit' (`Audits') hat zum Zweck die infrastrukturellen Bedingungen für Verkehrssicherheit bereits während der Entwurf- und Realisierungsphase der Verkehrsinfrastruktur einzubauen. Dieser Bericht gibt ein Übersicht der Tragweite des Audits. Ausserdem werden

Applying improved instrumentation and computer control systems

International Nuclear Information System (INIS)

Bevilacqua, F.; Myers, J.E.

1977-01-01

In-core and out-of-core instrumentation systems for the Cherokee-I reactor are described. The reactor has 61m-core instrument assemblies. Continuous computer monitoring and processing of data from over 300 fixed detectors will be used to improve the manoeuvering of core power. The plant protection system is a standard package for the Combustion Engineering System 80, consisting of two independent systems, the reactor protection system and the engineering safety features activation system, both of which are designed to meet NRC, ANS and IEEE design criteria or standards. The plants protection system has its own computer which provides plant monitoring, alarming, logging and performance calculations. (U.K.)

75 FR 23580 - Amendment of Class E Airspace; Mapleton, IA

Science.gov (United States)

2010-05-04

...-1155; Airspace Docket No. 09-ACE-14] Amendment of Class E Airspace; Mapleton, IA AGENCY: Federal... Mapleton, IA, adding additional controlled airspace to accommodate Area Navigation (RNAV) Standard Instrument Approach Procedures (SIAPs) at James G. Whiting Memorial Field Airport, Mapleton, IA. The FAA is...

Listening to Learn: The Status of Listening Activities in Secondary Instrumental Ensemble Classes

Science.gov (United States)

Prichard, Stephanie

2013-01-01

The purpose of this study was to determine the status of listening activities as part of middle and high school instrumental music instruction. Research questions addressed teachers' beliefs in the importance of listening, outcomes associated with listening, type and frequency of listening activities, presence of guided listening, and challenges…

RF radiation safety handbook

International Nuclear Information System (INIS)

Kitchen, Ronald.

1993-01-01

Radio frequency radiation can be dangerous in a number of ways. Hazards include electromagnetic compatibility and interference, electro-explosive vapours and devices, and direct effects on the human body. This book is a general introduction to the sources and nature of RF radiation. It describes the ways in which our current knowledge, based on relevant safety standards, can be used to safeguard people from any harmful effects of RF radiation. The book is designed for people responsible for, or concerned with, safety. This target audience will primarily be radio engineers, but includes those skilled in other disciplines including medicine, chemistry or mechanical engineering. The book covers the problems of RF safety management, including the use of measuring instruments and methods, and a review of current safety standards. The implications for RF design engineers are also examined. (Author)

Belgian class II nuclear facilities such as irradiators and accelerators. Regulatory Body attention points and operating experience feedback

Energy Technology Data Exchange (ETDEWEB)

Minne, Etienne; Peters, Christelle; Mommaert, Chantal; Kennes, Christian; Cortenbosch, Geert; Schmitz, Frederic; Haesendonck, Michel van [Bel V, Brussels (Belgium); Carlier, Pascal; Schrayen, Virginie; Wertelaers, An [Federal Agency for Nuclear Control, Brussels (Belgium)

2016-11-15

The aim of this paper is to present the Regulatory Body attention points and the operating experience feedback from Belgian ''class IIA'' facilities such as industrial and research irradiators, bulk radionuclides producers and conditioners. Reinforcement of the nuclear safety and radiation protection has been promoted by the Federal Agency for Nuclear Control (FANC) since 2009. This paper is clearly a continuation of the former paper [1] presenting the evolution in the regulatory framework relative to the creation of Bel V, the subsidiary of the FANC, and to the new ''class IIA'' covering heavy installations such as those mentioned above. Some lessons learnt are extracted from the operating experience feedback based on the events declared to the authorities. Even though a real willingness to meet the new safety requirements is observed among the ''class IIA'' licensees, promoting the safety culture, the nuclear safety and radiation protection remains an endless challenge for the Regulatory Body.

Instrumentation and electrical program at the Three Mile Island Unit 2, Technical Integration Office

International Nuclear Information System (INIS)

Hecker, L.A.

1982-01-01

The Three Mile Island Unit 2 accident of March 28, 1979 presents unique research opportunities that can provide valuable information on nuclear power plant safety philosophy and safety systems performance. The Technical Integration Office at Three Mile Island was established by the Department of Energy to manage a broad-based research and development program. One significant part of this effort is the Instrumentation and Electrical Program, which operates: (1) to identify instruments and electrical components that failed during or since the accident; (2) to test and analyze them in order to identify the causes of failure; and (3) to assess the survivability of those that did not fail. The basis for selection of equipment is discussed, and the testing methodology is described. Also, some results of Instrumentation and Electrical Program work to date are presented

Safety methodology and risk targets

International Nuclear Information System (INIS)

Kazimi, M.S.

1983-01-01

In assessing the potential safety concerns of fusion, the experience from other energy sources lead to a variety of safety assessment approaches. The available approaches are: (1) The maximum possible accident approach; (2) The maximum credible accident approach; (3) The probabilistic total risk assessment. In the first approach, the mechanistic development of the events leading to the safety concern is ignored. Instead, the total radioactivity of the plant is assumed accessible to the public. Such an approach is obviously conservative and unrealistic. In the second approach a selection is made among the most severe of the possible accidents, and the progression of the accident is modeled as mechanistically as possible. In this case, the passive and active accident mitigation capabilities of the plant are taken into consideration. The result is expected to be that none or only a fraction of the total radioactivity can be released to the public. The adverse effect of this approach is to concentrate attention on a particular accident class, and perhaps not allow for other classes, a judgement that may later become undesirable. The probabilistic risk assessment requires the safety analysts to consider all classes of accidents and estimate both the probabilities of their occurrences and their consequences. Thus, the plant design in fact is subjected to a thorough investigation and the impact of alterations in design can be reflected in the total risk estimate. The disadvantage of this approach lies in the absence of well defined acceptable risk criteria as well as the large effect of public perception factors on the accepted risk. This paper will review the impact of application of these approaches in determination of the level of protection needed against activation product release to the atmosphere. (author)

Hospital disinfection: efficacy and safety issues.

Science.gov (United States)

Dettenkofer, Markus; Block, Colin

2005-08-01

To review recent publications relevant to hospital disinfection (and cleaning) including the reprocessing of medical instruments. The key question as to whether the use of disinfectants on environmental surfaces rather than cleaning with detergents only reduces nosocomial infection rates still awaits conclusive studies. New disinfectants, mainly peroxygen compounds, show good sporicidal properties and will probably replace more problematical substances such as chlorine-releasing agents. The safe reprocessing of medical devices requires a well-coordinated approach, starting with proper cleaning. New methods and substances show promising activity for preventing the transmission of prions. Different aspects of virus inactivation have been studied, and the transmissibility, e.g. of norovirus, shows the need for sound data on how different disinfectant classes perform. Biofilms or other forms of surface-adherent organisms pose an extraordinary challenge to decontamination. Although resistance to biocides is generally not judged to be as critical as antibiotic resistance, scientific data support the need for proper use, i.e. the avoidance of widespread application, especially in low concentrations and in consumer products. Chemical disinfection of heat-sensitive instruments and targeted disinfection of environmental surfaces are established components of hospital infection control. To avoid danger to staff, patients and the environment, prudent use as well as established safety precautions are required. New technologies and products should be evaluated with sound methods. As emerging resistant pathogens will challenge healthcare facilities in the future even more than at present, there is a need for well-designed studies addressing the role of disinfection in hospital infection control.

The KNK II instrumentation for global and local supervision of the reactor core

International Nuclear Information System (INIS)

Steiger, W.O.

1991-01-01

After an introduction into the KNK plant itself, their historical development and their present situation, the instrumentation of the global and local supervision of the KNK II-core as well as the main safety-related instrumentation and control systems is described. Special emphasis is laid on the instrumentation of the reactor protection systems and the shut down systems. After that some practices are reported about instrumentation behavior and lessons learned from the operation and maintenance of the above mentioned systems. At last follows a short description of the special instrumentation for the detection of failed fuel subassemblies and of the plant data processing system. (author). 4 refs, 18 tabs

75 FR 35516 - Pipeline Safety: Request for Special Permit

Science.gov (United States)

2010-06-22

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2010-0147] Pipeline Safety: Request for Special Permit AGENCY: Pipeline and Hazardous Materials... with the Class 1 location portion of a 7.4 mile natural gas pipeline to be constructed in Alaska. This...

Surgical risks and perioperative complications of instrumented lumbar surgery in patients with liver cirrhosis

Directory of Open Access Journals (Sweden)

Tung-Yi Lin

2014-02-01

Full Text Available Background: Patients with liver cirrhosis have high surgical risks due to malnutrition, impaired immunity, coagulopathy, and encephalopathy. However, there is no information in English literature about the results of liver cirrhotic patients who underwent instrumented lumbar surgery. The purpose of this study is to report the perioperative complications, clinical outcomes and determine the surgical risk factors in cirrhotic patients. Methods: We retrospectively reviewed 29 patients with liver cirrhosis who underwent instrumented lumbar surgery between 1997 and 2009. The hepatic functional reserves of the patients were recorded according to the Child-Turcotte-Pugh scoring system. Besides, fourteen other variables and perioperative complications were also collected. To determine the risks, we divided the patients into two groups according to whether or not perioperative complications developed. Results: Of the 29 patients, 22 (76% belonged to Child class A and 7 (24% belonged to Child class B. Twelve patients developed one or more complications. Patients with Child class B carried a significantly higher incidence of complications than those with Child class A (p = 0.011. In the Child class A group, patients with 6 points had a significantly higher incidence of complications than those with 5 points (p = 0.025. A low level of albumin was significantly associated with higher risk, and a similar trend was also noted for the presence of ascites although statistical difference was not reached. Conclusion: The study concludes that patients with liver cirrhosis who have undergone instrumented lumbar surgery carry a high risk of developing perioperative complications, especially in those with a Child-Turcotte-Pugh score of 6 or more.

Injury Prevention and Safety

Science.gov (United States)

... 8 49.8 Use of protective equipment for biking, skating, or other sports 69.2 55.4 50.0 Water safety 54.6 42.8 38.0 * In at least 1 elementary school class or in at least 1 required health education course in middle schools or high schools. ...

Safety-related control air systems

International Nuclear Information System (INIS)

Anon.

1977-01-01

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

Investigation of status of safety management in radiation handle works

International Nuclear Information System (INIS)

Amauchi, Hiroshi; Nishimura, Kenji; Izumi, Kokichi

2007-01-01

This report describes the investigation in the title concerning the system for safety management and for accident prevention, which was done by a questionnaire in a period of 1.5 months in 2005. The questionnaire including 55 questions for safety management system, 33 for instruments and safety utilization of radiation and 57 for present status of safety management in high-risk radiation works, was performed in 780 hospitals, of which 313 answered. The first 55 questions concerned with the facility, patient identification, information exchange, management of private information, safety management activities, measures to prevent accident, manual preparation, personnel education and safety awareness; the second, with management of instruments, package insert, system for reporting the safety information, management of implants, re-imaging and radiation protection; and the third, with the systems for patients' emergency, in departments of CT/MR, of IVR, of nuclear diagnosis and of radiation therapy. Based on the results obtained, many problems, tasks and advices are presented to various items and further continuation of efforts to improve the present status is mentioned to be necessary. Details are given in the homepage of the Japanese Society of Radiological Technology. (T.I.)

78 FR 48301 - Establishment of Class E Airspace; Walker, MN

Science.gov (United States)

2013-08-08

...-0266; Airspace Docket No. 13-AGL-11] Establishment of Class E Airspace; Walker, MN AGENCY: Federal... at Walker, MN. Controlled airspace is necessary to accommodate new Area Navigation (RNAV) Standard Instrument Approach Procedures at Walker Municipal Airport. The FAA is taking this action to enhance the...

78 FR 65555 - Establishment of Class E Airspace; Salmon, ID

Science.gov (United States)

2013-11-01

...-0531; Airspace Docket No. 13-ANM-20] Establishment of Class E Airspace; Salmon, ID AGENCY: Federal... at the Salmon VHF Omni-Directional Radio Range/Distance Measuring Equipment (VOR/DME) navigation aid, Salmon, ID, to facilitate vectoring of Instrument Flight Rules (IFR) aircraft under control of Salt Lake...

77 FR 29875 - Establishment of Class E Airspace; Houston, MO