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DEVELOPMENT OF HUMAN FACTORS ENGINEERING GUIDANCE FOR SAFETY EVALUATIONS OF ADVANCED REACTORS.
Advanced reactors are expected to be based on a concept of operations that is different from what is currently used in today's reactors. Therefore, regulatory staff may need new tools, developed from the best available technical bases, to support licensing evaluations. The areas in which new review guidance may be needed and the efforts underway to address the needs will be discussed. Our preliminary results focus on some of the technical issues to be addressed in three areas for which new guidance may be developed: automation and control, operations under degraded conditions, and new human factors engineering methods and tools.
DEVELOPMENT OF HUMAN FACTORS ENGINEERING GUIDANCE FOR SAFETY EVALUATIONS OF ADVANCED REACTORS.
2006-10-01
Advanced reactors are expected to be based on a concept of operations that is different from what is currently used in today's reactors. Therefore, regulatory staff may need new tools, developed from the best available technical bases, to support licensing evaluations. The areas in which new review guidance may be needed and the efforts underway to address the needs will be discussed. Our preliminary results focus on some of the technical issues to be addressed in three areas for which new guidance may be developed: automation and control, operations under degraded conditions, and new human factors engineering methods and tools.
Guidance Document for PMF Applications with the Multilinear Engine
This document serves as a guide for users of the Multilinear Engine version 2 (ME-2) for source apportionment applications utilizing positive matrix factorization (PMF). It aims to educate experienced source apportionment analysts on available ME rotational tools and provides gui...
An Overview of the Application of Human Factors Guidance to Control Room Design
2002-08-26
A new power plant design has the goal of making major improvements in cost and ease of operation over previous designs. Improvements in the way information is organized and presented to control room operators based on established Human Factors Engineering (HFE) criteria is key to achieving these goals. An overview of the process and methods being employed in an ongoing design effort will be discussed, including the ways in which current Human Factors guidance is being applied in a unique operating environment.
The use of simulation in the development of human factors guidelines for alarm systems
This paper describes a research program sponsored by the US Nuclear Regulatory Commission to address the human factors engineering (HFE) aspects of nuclear power plant alarm systems. The overall objective of the program is to develop HFE review guidance for advanced alarm systems. As part of this program, guidance was developed based on a broad review and analysis of technical and research literature. In the course of guidance development, aspects of alarm system design for which the technical basis was insufficient to support guidance developed were identified. Experimental research is currently underway to address the highest priority topics: alarm processing and display characteristics. This paper provides an overview of the approach to guidance development and discusses the role of simulation in the development approach. Finally, the current simulator-based experiment is described to illustrate how the alarm system design features are being studied.
The use of simulation in the development of human factors guidelines for alarm systems
1997-07-01
This paper describes a research program sponsored by the US Nuclear Regulatory Commission to address the human factors engineering (HFE) aspects of nuclear power plant alarm systems. The overall objective of the program is to develop HFE review guidance for advanced alarm systems. As part of this program, guidance was developed based on a broad review and analysis of technical and research literature. In the course of guidance development, aspects of alarm system design for which the technical basis was insufficient to support guidance developed were identified. Experimental research is currently underway to address the highest priority topics: alarm processing and display characteristics. This paper provides an overview of the approach to guidance development and discusses the role of simulation in the development approach. Finally, the current simulator-based experiment is described to illustrate how the alarm system design features are being studied.
Engineering and Design - Rock Foundations
Provides general guidance for factors to be considered in the construction of foundations and cut slopes excavated in rock masses. Divided into five sections with general topic areas to include: Excavation; Dewatering and Ground Water Control; Ground Control; Protection of Sensitive Foundation Materials; and Excavation Mapping and Monitoring.
THE DEVELOPMENT OF DETAILED HUMAN FACTORS ENGINEERING GUIDELINES FOR DIGITAL CONTROL ROOM UPGRADES.
As part of the Department of Energy and Electric Power Research Institute's hybrid control room project, detailed human factors engineering guidance was developed for designing human-system interfaces that may be affected by introduction of additional digital technology during modernization of nuclear power plants. The guidance addresses several aspects of human-system interaction: information display, interface management, soft controls, alarms, computer-based procedures, computerized operator support systems, communications, and workstation/workplace design. In this paper, the ways in which digital upgrades might affect users' interaction with systems in each of these contexts are briefly described, and the contents of the guidance developed for each of the topics is also described.
THE DEVELOPMENT OF DETAILED HUMAN FACTORS ENGINEERING GUIDELINES FOR DIGITAL CONTROL ROOM UPGRADES.
As part of the Department of Energy and Electric Power Research Institute's hybrid control room project, detailed human factors engineering guidance was developed for designing human-system interfaces that may be affected by introduction of additional digital technology during modernization of nuclear power plants. The guidance addresses several aspects of human-system interaction: information display, interface management, soft controls, alarms, computer-based procedures, computerized operator support systems, communications, and workstation/workplace design. In this paper, the ways in which digital upgrades might affect users' interaction with systems in each of these contexts are briefly described, and the contents of the guidance developed for each of the topics is also described.
THE DEVELOPMENT OF DETAILED HUMAN FACTORS ENGINEERING GUIDELINES FOR DIGITAL CONTROL ROOM UPGRADES.
2004-09-19
As part of the Department of Energy and Electric Power Research Institute's hybrid control room project, detailed human factors engineering guidance was developed for designing human-system interfaces that may be affected by introduction of additional digital technology during modernization of nuclear power plants. The guidance addresses several aspects of human-system interaction: information display, interface management, soft controls, alarms, computer-based procedures, computerized operator support systems, communications, and workstation/workplace design. In this paper, the ways in which digital upgrades might affect users' interaction with systems in each of these contexts are briefly described, and the contents of the guidance developed for each of the topics is also described.
THE DEVELOPMENT OF DETAILED HUMAN FACTORS ENGINEERING GUIDELINES FOR DIGITAL CONTROL ROOM UPGRADES
2004-01-01
As part of the Department of Energy and Electric Power Research Institute's hybrid control room project, detailed human factors engineering guidance was developed for designing human-system interfaces that may be affected by introduction of additional digital technology during modernization of nuclear power plants. The guidance addresses several aspects of human-system interaction: information display, interface management, soft controls, alarms, computer-based procedures, computerized operator support systems, communications, and workstation/workplace design. In this paper, the ways in which digital upgrades might affect users' interaction with systems in each of these contexts are briefly described, and the contents of the guidance developed for each of the topics is also described
The corrosion resistance of thermoset composites in alkaline environments
1998-12-31
Corrosion engineers need guidelines for selecting thermoset resins for aggressive applications such as hot alkali and alkaline peroxide. The suitability of fiberglass-reinforced plastic (FRP) for alkaline service depends on factors such as the ester content of the resin, the unsaturated monomer composition, and the cure system. The purpose of the present paper is to show the effect of these factors on the alkaline corrosion resistance of FRP and provide corrosion engineers with the guidance needed for selecting the best epoxy vinyl ester resins for alkaline environments.
GUIDANCE FOR NUCLEAR POWER PLANT CONTROL ROOM AND HUMAN-SYSTEM INTERFACE MODERNIZATION
Several nuclear power plants in the United States are starting instrumentation and control (I&C) modernization programs using digital equipment to address obsolescence issues and the need to improve plant performance while maintaining high levels of safety. As an integral part of the I&C modernization program at a nuclear power plant, the control room and other human-system interfaces (HSIs) are also being modernized. To support safe and effective operation, it is critical to plan, design, implement, train for, operate, and maintain the control room and HSI changes to take advantage of human cognitive processing abilities. A project, jointly funded by the Electric Power Research Institute (EPRI) and the United States Department of Energy (DOE) under the Nuclear Energy Plant Optimization (NEPO) Program, is developing guidance for specifying and designing control rooms, remote shut-down panels, HSIs etc. The guidance is intended for application by utilities and suppliers of control room and HSI modernization. The guidance will facilitate specification, design, implementation, operations, maintenance, training, and licensing activities. This guidance will be used to reduce the likelihood of human errors and licensing risk, to gain maximum benefit of implemented technology, and to increase performance. The guidance is of five types. The first is planning guidance to help a utility develop its plant-specific control room operating concepts, its plant-specific endpoint vision for the control room, its migration path to achieve that endpoint vision, and its regulatory, licensing, and human factors program plans. The second is process guidance for general HSI design and integration, human factors engineering analyses, verification and validation, in-service monitoring processes, etc. The third is detailed human factors engineering guidance for control room and HSI technical areas. The fourth is guidance for licensing. The fifth is guidance for special topics related to operations and maintenance including training and simulation and safety monitoring and control guidance. Currently, the plan is that the overall guidelines will be made up of 34 guidelines on different topics of which 31 are completed. This may increase based on input from the project working group which includes 21 utilities as well as nuclear utility industry participants.
GUIDANCE FOR NUCLEAR POWER PLANT CONTROL ROOM AND HUMAN-SYSTEM INTERFACE MODERNIZATION
Several nuclear power plants in the United States are starting instrumentation and control (I&C) modernization programs using digital equipment to address obsolescence issues and the need to improve plant performance while maintaining high levels of safety. As an integral part of the I&C modernization program at a nuclear power plant, the control room and other human-system interfaces (HSIs) are also being modernized. To support safe and effective operation, it is critical to plan, design, implement, train for, operate, and maintain the control room and HSI changes to take advantage of human cognitive processing abilities. A project, jointly funded by the Electric Power Research Institute (EPRI) and the United States Department of Energy (DOE) under the Nuclear Energy Plant Optimization (NEPO) Program, is developing guidance for specifying and designing control rooms, remote shut-down panels, HSIs etc. The guidance is intended for application by utilities and suppliers of control room and HSI modernization. The guidance will facilitate specification, design, implementation, operations, maintenance, training, and licensing activities. This guidance will be used to reduce the likelihood of human errors and licensing risk, to gain maximum benefit of implemented technology, and to increase performance. The guidance is of five types. The first is planning guidance to help a utility develop its plant-specific control room operating concepts, its plant-specific endpoint vision for the control room, its migration path to achieve that endpoint vision, and its regulatory, licensing, and human factors program plans. The second is process guidance for general HSI design and integration, human factors engineering analyses, verification and validation, in-service monitoring processes, etc. The third is detailed human factors engineering guidance for control room and HSI technical areas. The fourth is guidance for licensing. The fifth is guidance for special topics related to operations and maintenance including training and simulation and safety monitoring and control guidance. Currently, the plan is that the overall guidelines will be made up of 34 guidelines on different topics of which 31 are completed. This may increase based on input from the project working group which includes 21 utilities as well as nuclear utility industry participants.
GUIDANCE FOR NUCLEAR POWER PLANT CONTROL ROOM AND HUMAN-SYSTEM INTERFACE MODERNIZATION
2004-10-06
Several nuclear power plants in the United States are starting instrumentation and control (I&C) modernization programs using digital equipment to address obsolescence issues and the need to improve plant performance while maintaining high levels of safety. As an integral part of the I&C modernization program at a nuclear power plant, the control room and other human-system interfaces (HSIs) are also being modernized. To support safe and effective operation, it is critical to plan, design, implement, train for, operate, and maintain the control room and HSI changes to take advantage of human cognitive processing abilities. A project, jointly funded by the Electric Power Research Institute (EPRI) and the United States Department of Energy (DOE) under the Nuclear Energy Plant Optimization (NEPO) Program, is developing guidance for specifying and designing control rooms, remote shut-down panels, HSIs etc. The guidance is intended for application by utilities and suppliers of control room and HSI modernization. The guidance will facilitate specification, design, implementation, operations, maintenance, training, and licensing activities. This guidance will be used to reduce the likelihood of human errors and licensing risk, to gain maximum benefit of implemented technology, and to increase performance. The guidance is of five types. The first is planning guidance to help a utility develop its plant-specific control room operating concepts, its plant-specific endpoint vision for the control room, its migration path to achieve that endpoint vision, and its regulatory, licensing, and human factors program plans. The second is process guidance for general HSI design and integration, human factors engineering analyses, verification and validation, in-service monitoring processes, etc. The third is detailed human factors engineering guidance for control room and HSI technical areas. The fourth is guidance for licensing. The fifth is guidance for special topics related to operations and maintenance including training and simulation and safety monitoring and control guidance. Currently, the plan is that the overall guidelines will be made up of 34 guidelines on different topics of which 31 are completed. This may increase based on input from the project working group which includes 21 utilities as well as nuclear utility industry participants.
Prototype of evaluation guidance system in Integrated Nuclear Data Evaluation System
1992-01-01
Integrated Nuclear Data Evaluation System (INDES) is being developed to keep experiences of nuclear data evaluation for JENDL-3 and to support new evaluations. One of the INDES functions is to set up input data of theoretical calculation codes automatically. In order to use INDES effectively, a prototype of nuclear data evaluation guidance system (E.T. Evaluation Tutor) was made to help users in selecting a set of suitable theoretical calculation codes by applying knowledge engineering technology. E.T. consists of an inference engine, frames, a rule-base, two example-bases and calculating modules of certainty factors. The inference engine and the calculating modules are written in FORTRAN77. (author)
HUMAN FACTORS GUIDANCE FOR CONTROL ROOM EVALUATION
2000-07-30
The Human-System Interface Design Review Guideline (NUREG-0700, Revision 1) was developed by the US Nuclear Regulatory Commission (NRC) to provide human factors guidance as a basis for the review of advanced human-system interface technologies. The guidance consists of three components: design review procedures, human factors engineering guidelines, and a software application to provide design review support called the ``Design Review Guideline.'' Since it was published in June 1996, Rev. 1 to NUREG-0700 has been used successfully by NRC staff, contractors and nuclear industry organizations, as well as by interested organizations outside the nuclear industry. The NRC has committed to the periodic update and improvement of the guidance to ensure that it remains a state-of-the-art design evaluation tool in the face of emerging and rapidly changing technology. This paper addresses the current research to update of NUREG-0700 based on the substantial work that has taken place since the publication of Revision 1.
Presidential Awards for Excellence in Science, Mathematics and Engineering Mentoring
... and sustained mentoring and effective guidance to a significant number of underrepresented students ... and sustained mentoring and effective guidance to a significant number of underrepresented students ...
Spatially Patterned Gene Expression for Guided Neurite Extension
2009-03-01
Full Text Available.Axon pathfinding by localized expression of guidance molecules is critical for the proper development of the nervous system. In this report, we present a well-defined spatially patterned gene expression system to investigate neurite guidance in vitro. Nonviral gene delivery was patterned by combining substrate-mediated gene delivery with soft lithography techniques, and the amount of protein produced at the region of localized expression was varied by altering the vector concentration and the width of the pattern, highlighting the flexibility of the system. A neuronal coculture model was used to investigate responses to spatial patterns of nerve growth factor (NGF) expression. The soluble NGF gradient elicited a guidance cue, and the degree of guidance was governed by the distance a neuron was cultured from the pattern and the time between accessory cell and neuron seedings. A portion of the diffusible NGF bound to the culture surface in the extracellular space, and the surface-associated NGF supported neuron survival and neurite outgrowth. However, the surface-bound NGF gradient alone did not elicit a guidance signal, and in fact masked the guidance cue by soluble NGF gradients. Mathematical modeling of NGF diffusion was used to predict the concentration gradients, and both the absolute and fractional gradients capable of guiding neurites produced by patterned gene expression differed substantially from the values obtained with existing engineered protein gradients. Spatially patterned gene expression provides a versatile tool to investigate the factors that may promote neurite guidance.
Human factors engineering guidance for the review of advanced alarm systems
1994-09-01
This report provides guidance to support the review of the human factors aspects of advanced alarm system designs in nuclear power plants. The report is organized into three major sections. The first section describes the methodology and criteria that were used to develop the design review guidelines. Also included is a description of the scope, organization, and format of the guidelines. The second section provides a systematic review procedure in which important characteristics of the alarm system are identified, described, and evaluated. The third section provides the detailed review guidelines. The review guidelines are organized according to important characteristics of the alarm system including: alarm definition; alarm processing and reduction; alarm prioritization and availability; display; control; automated; dynamic, and modifiable characteristics; reliability, test, maintenance, and failure indication; alarm response procedures; and control-display integration and layout.
Human factors engineering guidance for the review of advanced alarm systems
This report provides guidance to support the review of the human factors aspects of advanced alarm system designs in nuclear power plants. The report is organized into three major sections. The first section describes the methodology and criteria that were used to develop the design review guidelines. Also included is a description of the scope, organization, and format of the guidelines. The second section provides a systematic review procedure in which important characteristics of the alarm system are identified, described, and evaluated. The third section provides the detailed review guidelines. The review guidelines are organized according to important characteristics of the alarm system including: alarm definition; alarm processing and reduction; alarm prioritization and availability; display; control; automated; dynamic, and modifiable characteristics; reliability, test, maintenance, and failure indication; alarm response procedures; and control-display integration and layout.
Sustainable Re Use of Tyres in Coastal Engineering
2005-07-22
SummaryThe principal output of the project is the project report/guidance document (see below) in which all the work carried out is described. The guidance document includes chapters covering subjects such as:ObjectivesTo explore methods for the re-use of tyres in coastal and river engineering without adverse effect on the environment, and to produce authoritative guidance on their engineering use. Environment Agency Copyright and or/ database right 2008. All rights reserved.
1996-06-01
NUREG-0700, Revision 1, provides human factors engineering (HFE) guidance to the US Nuclear Regulatory Commission staff for its: (1) review of the human system interface (HSI) design submittals prepared by licensees or applications for a license or design certification of commercial nuclear power plants, and (2) performance of HSI reviews that could be undertaken as part of an inspection or other type of regulatory review involving HSI design or incidents involving human performance. The guidance consists of a review process and HFE guidelines. The document describes those aspects of the HSI design review process that are important to the identification and resolution of human engineering discrepancies that could adversely affect plant safety. Guidance is provided that could be used by the staff to review an applicant`s HSI design review process or to guide the development of an HSI design review plan, e.g., as part of an inspection activity. The document also provides detailed HFE guidelines for the assessment of HSI design implementations. NUREG-0700, Revision 1, consists of three stand-alone volumes. Volume 3 contains an interactive software application of the NUREG-0700, Revision 1 guidance and a user`s guide for this software. The software supports reviewers during review preparation, evaluation design using the human factors engineering guidelines, and in report preparation. The user`s guide provides system requirements and installation instructions, detailed explanations of the software`s functions and features, and a tutorial on using the software.
An experimental investigation of the effects of alarm processing and display on operator performance
1998-03-01
This paper describes a research program sponsored by the US Nuclear Regulatory Commission to address the human factors engineering (HFE) aspects of nuclear power plant alarm systems. The overall objective of the program is to develop HFE review guidance for advanced alarm systems. As part of this program, guidance has been developed based on a broad base of technical and research literature. In the course of guidance development, aspects of alarm system design for which the technical basis was insufficient to support complete guidance development were identified. The primary purpose of the research reported in this paper was to evaluate the effects of three of these alarm system design characteristics on operator performance in order to contribute to the understanding of potential safety issues and to provide data to support the development of design review guidance in these areas. Three alarm system design characteristics studied were (1) alarm processing (degree of alarm reduction), (2) alarm availability (dynamic prioritization and suppression), and (3) alarm display (a dedicated tile format, a mixed tile and message list format, and a format in which alarm information is integrated into the process displays). A secondary purpose was to provide confirmatory evidence of selected alarm system guidance developed in an earlier phase of the project. The alarm characteristics were combined into eight separate experimental conditions. Six, two-person crews of professional nuclear power plant operators participated in the study. Following training, each crew completed 16 test trials which consisted of two trials in each of the eight experimental conditions (one with a low-complexity scenario and one with a high-complexity scenario). Measures of process performance, operator task performance, situation awareness, and workload were obtained. In addition, operator opinions and evaluations of the alarm processing and display conditions were collected. No deficient performance was observed in any of the experimental conditions, providing confirmatory support for many design review guidelines. The operators identified numerous strengths and weaknesses associated with individual alarm design characteristics.
Human Factors Engineering Review Model for advanced nuclear power reactors
One of the major issues to emerge from the initial design reviews under the certification process was that detailed human-systems interface (HSI) design information was not available for staff review. To address the lack of design detail issue. The Nuclear Regulatory Commission (NRC) is performing the design certification reviews based on a design process plan which describes the human factors engineering (HFE) program elements that are necessary and sufficient to develop an acceptable detailed design specification. Since the review of a design process is unprecedented in the nuclear industry. The criteria for review are not addressed by current regulations or guidance documents and. therefore, had to be developed. Thus, an HFE Program Review Model was developed. This paper will describe the model's rationale, scope, objectives, development, general characteristics. and application.
Human Factors Engineering Review Model for advanced nuclear power reactors
One of the major issues to emerge from the initial design reviews under the certification process was that detailed human-systems interface (HSI) design information was not available for staff review. To address the lack of design detail issue. The Nuclear Regulatory Commission (NRC) is performing the design certification reviews based on a design process plan which describes the human factors engineering (HFE) program elements that are necessary and sufficient to develop an acceptable detailed design specification. Since the review of a design process is unprecedented in the nuclear industry. The criteria for review are not addressed by current regulations or guidance documents and. therefore, had to be developed. Thus, an HFE Program Review Model was developed. This paper will describe the model`s rationale, scope, objectives, development, general characteristics. and application.
Human Factors Engineering Review Model for advanced nuclear power reactors
1993-01-01
One of the major issues to emerge from the initial design reviews under the certification process was that detailed human-systems interface (HSI) design information was not available for staff review. To address the lack of design detail issue. The Nuclear Regulatory Commission (NRC) is performing the design certification reviews based on a design process plan which describes the human factors engineering (HFE) program elements that are necessary and sufficient to develop an acceptable detailed design specification. Since the review of a design process is unprecedented in the nuclear industry. The criteria for review are not addressed by current regulations or guidance documents and. therefore, had to be developed. Thus, an HFE Program Review Model was developed. This paper will describe the model's rationale, scope, objectives, development, general characteristics. and application.
Human Factors Engineering Review Model for advanced nuclear power reactors
1993-05-01
One of the major issues to emerge from the initial design reviews under the certification process was that detailed human-systems interface (HSI) design information was not available for staff review. To address the lack of design detail issue. The Nuclear Regulatory Commission (NRC) is performing the design certification reviews based on a design process plan which describes the human factors engineering (HFE) program elements that are necessary and sufficient to develop an acceptable detailed design specification. Since the review of a design process is unprecedented in the nuclear industry. The criteria for review are not addressed by current regulations or guidance documents and. therefore, had to be developed. Thus, an HFE Program Review Model was developed. This paper will describe the model`s rationale, scope, objectives, development, general characteristics. and application.
Mentoring is an established strategy for learning that has its root in antiquity. Most, if not all, successful scientists and engineers had an effective mentor at some point in their career. In the context of scientists and engineers, mentoring has been undefined. Reports addressing critical concerns regarding the future of science and engineering in the U.S. mention the practice of mentoring a priori, leaving organizations without guidance in its application. Preliminary results from this study imply that formal mentoring can be effective when properly defined and operationalized. Recognizing the uniqueness of the individual in a symbiotic mentor-protg relationship significantly influences a protg?s learning experience which carries repercussions into their career intentions. The mentor-protg relationship is a key factor in succession planning and preserving and disseminating critical information and tacit knowledge essential to the development of leadership in the science and technological industry.
2006-11-01
Mentoring is an established strategy for learning that has its root in antiquity. Most, if not all, successful scientists and engineers had an effective mentor at some point in their career. In the context of scientists and engineers, mentoring has been undefined. Reports addressing critical concerns regarding the future of science and engineering in the U.S. mention the practice of mentoring a priori, leaving organizations without guidance in its application. Preliminary results from this study imply that formal mentoring can be effective when properly defined and operationalized. Recognizing the uniqueness of the individual in a symbiotic mentor-protg relationship significantly influences a protgs learning experience which carries repercussions into their career intentions. The mentor-protg relationship is a key factor in succession planning and preserving and disseminating critical information and tacit knowledge essential to the development of leadership in the science and technological industry.
...in the NAICS as NAICS 334511, Search, Detection, Navigation, Guidance...associated with the sale of 30 aircraft engines to country E. Aircraft engines are classified in the NAICS as NAICS 336412, Aircraft Engine and Engine Parts...
Increased application of labour based methods through appropriate engineering standards
2005-12-01
DescriptionProject Background: To improve the cost-effective provision of roads in rural and peri-urban areas in Africa by providing guidance on the main factors affecting performance and life cycle costs of roads constructed by labour based methods, including the construction standards adopted, the climate, the sub grade soils, and the traffic. Progress and Impact: This project is being managed by the International Labour Office (ILO), Geneva, and 'in country' field research is being undertaken by [continued...]
2010-01-01
Land subsidence is a common geological hazard. The long-term accumulation of land subsidence in Shanghai has caused economic loss to the city. Since the 1990s, engineering structures have become a new cause of land subsidence. The concept of the geology-environmental capacity of buildings is put forward. The main factors involved in land subsidence were determined and related to the floor area ratio. The relationship was assessed using the adaptive neuro-fuzzy inference system for four typical regions in Shanghai, in order to give some guidance in respect of urban planning.
Advanced alarm systems: Display and processing issues
This paper describes a research program sponsored by the US Nuclear Regulatory Commission to address the human factors engineering (HFE) deficiencies associated with nuclear power plant alarm systems. The overall objective of the study is to develop HFE review guidance for alarm systems. In support of this objective, human performance issues needing additional research were identified. Among the important issues were alarm processing strategies and alarm display techniques. This paper will discuss these issues and briefly describe our current research plan to address them.
Advanced alarm systems: Display and processing issues
1995-05-01
This paper describes a research program sponsored by the US Nuclear Regulatory Commission to address the human factors engineering (HFE) deficiencies associated with nuclear power plant alarm systems. The overall objective of the study is to develop HFE review guidance for alarm systems. In support of this objective, human performance issues needing additional research were identified. Among the important issues were alarm processing strategies and alarm display techniques. This paper will discuss these issues and briefly describe our current research plan to address them.
NUREG-0700, Revision 1, provides human factors engineering (HFE) guidance to the US Nuclear Regulatory Commission staff for its: (1) review of the human system interface (HSI) design submittals prepared by licensees or applications for a license or design certification of commercial nuclear power plants, and (2) performance of HSI reviews that could be undertaken as part of an inspection or other type of regulatory review involving HSI design or incidents involving human performance. The guidance consists of a review process and HFE guidelines. The document describes those aspects of the HSI design review process that are important to the identification and resolution of human engineering discrepancies that could adversely affect plant safety. Guidance is provided that could be used by the staff to review an applicant`s HSI design review process or to guide the development of an HSI design review plan, e.g., as part of an inspection activity. The document also provides detailed HFE guidelines for the assessment of HSI design implementations. NUREG-0700, Revision 1, consists of three stand-alone volumes. Volume 1 consists of two major parts. Part 1 describes those aspects of the review process of the HSI design that are important to identifying and resolving human engineering discrepancies. Part 2 contains detailed guidelines for a human factors engineering review which identify criteria for assessing the implementation of an applicant`s or licensee`s HSI design.
NUREG-0700, Revision 1, provides human factors engineering (HFE) guidance to the US Nuclear Regulatory Commission staff for its: (1) review of the human system interface (HSI) design submittals prepared by licensees or applications for a license or design certification of commercial nuclear power plants, and (2) performance of HSI reviews that could be undertaken as part of an inspection or other type of regulatory review involving HSI design or incidents involving human performance. The guidance consists of a review process and HFE guidelines. The document describes those aspects of the HSI design review process that are important to the identification and resolution of human engineering discrepancies that could adversely affect plant safety. Guidance is provided that could be used by the staff to review an applicant`s HSI design review process or to guide the development of an HSI design review plan, e.g., as part of an inspection activity. The document also provides detailed HFE guidelines for the assessment of HSI design implementations. NUREG-0700, Revision 1, consists of three stand-alone volumes. Volume 1 consists of two major parts. Part 1 describes those aspects of the review process of the HSI design that are important to identifying and resolving human engineering discrepancies. Part 2 contains detailed guidelines for a human factors engineering review which identify criteria for assessing the implementation of an applicant`s or licensee`s HSI design.
1996-06-01
NUREG-0700, Revision 1, provides human factors engineering (HFE) guidance to the US Nuclear Regulatory Commission staff for its: (1) review of the human system interface (HSI) design submittals prepared by licensees or applications for a license or design certification of commercial nuclear power plants, and (2) performance of HSI reviews that could be undertaken as part of an inspection or other type of regulatory review involving HSI design or incidents involving human performance. The guidance consists of a review process and HFE guidelines. The document describes those aspects of the HSI design review process that are important to the identification and resolution of human engineering discrepancies that could adversely affect plant safety. Guidance is provided that could be used by the staff to review an applicant`s HSI design review process or to guide the development of an HSI design review plan, e.g., as part of an inspection activity. The document also provides detailed HFE guidelines for the assessment of HSI design implementations. NUREG-0700, Revision 1, consists of three stand-alone volumes. Volume 1 consists of two major parts. Part 1 describes those aspects of the review process of the HSI design that are important to identifying and resolving human engineering discrepancies. Part 2 contains detailed guidelines for a human factors engineering review which identify criteria for assessing the implementation of an applicant`s or licensee`s HSI design.
Advanced control rooms will use advanced human-system interface (HSI) technologies that may have significant implications for plant safety in that they will affect the operator`s overall role in the system, the method of information presentation, and the ways in which operators interact with the system. The U.S. Nuclear Regulatory Commission (NRC) reviews the HSI aspects of control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported to protect public health and safety. The principal guidance available to the NRC, however, was developed more than ten years ago, well before these technological changes. Accordingly, the human factors guidance needs to be updated to serve as the basis for NRC review of these advanced designs. The purpose of this project was to develop a general approach to advanced HSI review and the human factors guidelines to support. NRC safety reviews of advanced systems. This two-volume report provides the results of the project. Volume I describes the development of the Advanced HSI Design Review Guideline (DRG) including (1) its theoretical and technical foundation, (2) a general model for the review of advanced HSIs, (3) guideline development in both hard-copy and computer-based versions, and (4) the tests and evaluations performed to develop and validate the DRG. Volume I also includes a discussion of the gaps in available guidance and a methodology for addressing them. Volume 2 provides the guidelines to be used for advanced HSI review and the procedures for their use.
1994-07-01
Advanced control rooms will use advanced human-system interface (HSI) technologies that may have significant implications for plant safety in that they will affect the operator`s overall role in the system, the method of information presentation, and the ways in which operators interact with the system. The U.S. Nuclear Regulatory Commission (NRC) reviews the HSI aspects of control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported to protect public health and safety. The principal guidance available to the NRC, however, was developed more than ten years ago, well before these technological changes. Accordingly, the human factors guidance needs to be updated to serve as the basis for NRC review of these advanced designs. The purpose of this project was to develop a general approach to advanced HSI review and the human factors guidelines to support. NRC safety reviews of advanced systems. This two-volume report provides the results of the project. Volume I describes the development of the Advanced HSI Design Review Guideline (DRG) including (1) its theoretical and technical foundation, (2) a general model for the review of advanced HSIs, (3) guideline development in both hard-copy and computer-based versions, and (4) the tests and evaluations performed to develop and validate the DRG. Volume I also includes a discussion of the gaps in available guidance and a methodology for addressing them. Volume 2 provides the guidelines to be used for advanced HSI review and the procedures for their use.
UPDATING THE NRC GUIDANCE FOR HUMAN FACTORS ENGINEERING REVIEWS.
2002-09-15
The U.S. Nuclear Regulatory Commission (NRC) reviews the human factors engineering (HFE) aspects of nuclear plants. NUREG-0800 (Standard Review Plan), Chapter 18, ''Human Factors Engineering,'' is the principal NRC staff guidance document. Two main documents provide the review criteria to support the evaluations. The HFE Program Review Model (NUREG-0711) addresses the design process from planning to verification and validation to design implementation. The Human-System Interface Design Review Guidelines (NUREG-0700) provides the guidelines for the review of the HFE aspects of human-system interface technology, such as alarms, information systems, controls, and control room design. Since these documents were published in 1994 and 1996 respectively, they have been used by NRC staff, contractors, nuclear industry organizations, as well as by numerous organizations outside the nuclear industry. Using feedback from users and NRC research conducted in recent years, both documents have been revised and updated. This was done to ensure that they remain state-of-the-art evaluation tools for changing nuclear industry issues and emerging technologies. This paper describes the methodology used to revise and update the documents and summarizes the changes made to each and their current contents. Index Terms for this report are: Control system human factors, Ergonomics, Human factors, Nuclear power generation safety.
Human factors guidelines for nuclear power plant applications
In 1989, Waters et al. reported to the Human Factors Society on developing human factors criteria for a new reactor plant. They correctly indicated that much of the guidance documentation in human factors engineering has derived from MIL-STD-1472 and its antecedents. Guidelines for human-computer interface have sprung primarily from the Smith and Mosier compendium and its source documents. NUREG-0700, which is currently being updated, was developed by the US Nuclear Regulatory Commission (NRC) as a general evaluation guide for inspecting control rooms. In addition, the Electric Power Research Institute, Institute of Nuclear Power Operations, US Department of Energy, the NRC, and others have published a number of specialized documents on a range of subjects. The number of guidelines and standards has grown in the past few years to an impressive number, including those published by international organizations and professional societies. This paper provides an update on current efforts to provide appropriate guidance for the power industry and, perhaps more importantly, offers a perspective on how users should think about using the available materials and what else is needed. The Electric Power Research Institute (EPRI) continues to be one of the principal participants in providing guidance to the utilities. Human factors guidelines is indeed a timely topic, currently of great interest to EPRI's constituents and to designers of new and upgraded nuclear power plants (NPMs) in the Advanced Light Water Reactor and the Instrumentation and Control Upgrade Initiative programs.
Human factors guidelines for nuclear power plant applications
1993-01-01
In 1989, Waters et al. reported to the Human Factors Society on developing human factors criteria for a new reactor plant. They correctly indicated that much of the guidance documentation in human factors engineering has derived from MIL-STD-1472 and its antecedents. Guidelines for human-computer interface have sprung primarily from the Smith and Mosier compendium and its source documents. NUREG-0700, which is currently being updated, was developed by the US Nuclear Regulatory Commission (NRC) as a general evaluation guide for inspecting control rooms. In addition, the Electric Power Research Institute, Institute of Nuclear Power Operations, US Department of Energy, the NRC, and others have published a number of specialized documents on a range of subjects. The number of guidelines and standards has grown in the past few years to an impressive number, including those published by international organizations and professional societies. This paper provides an update on current efforts to provide appropriate guidance for the power industry and, perhaps more importantly, offers a perspective on how users should think about using the available materials and what else is needed. The Electric Power Research Institute (EPRI) continues to be one of the principal participants in providing guidance to the utilities. Human factors guidelines is indeed a timely topic, currently of great interest to EPRI's constituents and to designers of new and upgraded nuclear power plants (NPMs) in the Advanced Light Water Reactor and the Instrumentation and Control Upgrade Initiative programs.
Navigation of cell locomotion by gradients of soluble factors can be desensitized if the concentration of the chemo-attractant stays unchanged. It remains obscure if the guidance by immobilized extracellular...Full Text Available
Method for plant operation guidance by knowledge engineering technique
1983-04-01
A method for plant operation guidance has been developed by using the Knowledge Engineering technique. The method is characterized by its capability of handling plant dynamics. The knowledge-base includes plant simulation programs as tools to evaluate dynamic behaviors as well as production rules of ''if..., then...'' type. The inference engine is thus capable of predicting plant dynamics and making decisions in accordance wi
Toward integrated design of waste management technologies
What technical, economic and institutional factors make radioactive and/or hazardous waste management technologies publicly acceptable? The goal of this paper is to initiate an identification of factors likely to render radioactive and hazardous waste management technologies publicly acceptable and to provide guidance on how technological R&D might be revised to enhance the acceptability of alternative waste management technologies. Technology development must attend to the full range of technology characteristics (technical, engineering, physical, economic, health, environmental, and socio-institutional) relevant to diverse stakeholders. ORNL`s efforts in recent years illustrate some attempts to accomplish these objectives or, at least, to build bridges toward the integrated design of waste management technologies.
Toward integrated design of waste management technologies
1993-11-01
What technical, economic and institutional factors make radioactive and/or hazardous waste management technologies publicly acceptable? The goal of this paper is to initiate an identification of factors likely to render radioactive and hazardous waste management technologies publicly acceptable and to provide guidance on how technological R&D might be revised to enhance the acceptability of alternative waste management technologies. Technology development must attend to the full range of technology characteristics (technical, engineering, physical, economic, health, environmental, and socio-institutional) relevant to diverse stakeholders. ORNL`s efforts in recent years illustrate some attempts to accomplish these objectives or, at least, to build bridges toward the integrated design of waste management technologies.
Review of human factors in operator aids development at ORNL
1983-01-01
Three related Oak Ridge National Laboratory (ORNL) projects in the area of human factors in diagnostic aids are described. The goal of the first, sponsored by the Electric Power Research Institute (EPRI RP2184), is to provide guidance to nuclear-utility engineers in the selection and retrofit of computer-generated display systems in nuclear-plant control rooms. The goal of the second, sponsored by the Office of Research of the Nuclear Regulatory Commission (NRC), is to provide the NRC with a preview of some of the operator aids currently under development by industry for the purpose of assessing the applicability of current requirements. The goal of the third, also sponsored by the NRC, is to develop a methodology to determine the proper allocation of function between an operator and an automated system. The status of each project is given, together with the current and expected findings.
Tank waste remediation system systems engineering management plan
1998-01-08
This Systems Engineering Management Plan (SEMP) describes the Tank Waste Remediation System (TWRS) implementation of the US Department of Energy (DOE) systems engineering policy provided in 97-IMSD-193. The SEMP defines the products, process, organization, and procedures used by the TWRS Project to implement the policy. The SEMP will be used as the basis for tailoring the systems engineering applications to the development of the physical systems and processes necessary to achieve the desired end states of the program. It is a living document that will be revised as necessary to reflect changes in systems engineering guidance as the program evolves. The US Department of Energy-Headquarters has issued program management guidance, DOE Order 430. 1, Life Cycle Asset Management, and associated Good Practice Guides that include substantial systems engineering guidance.
Advanced control rooms will use advanced human-system interface (HSI) technologies that may have significant implications for plant safety in that they will affect the operator`s overall role in the system, the method of information presentation, and the ways in which operators interact with the system. The U.S. Nuclear Regulatory Commission (NRC) reviews the HSI aspects of control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported to protect public health and safety. The principal guidance available to the NRC, however, was developed more than ten years ago, well before these technological changes. Accordingly, the human factors guidance needs to be updated to serve as the basis for NRC review of these advanced designs. The purpose of this project was to develop a general approach to advanced HSI review and the human factors guidelines to support NRC safety reviews of advanced systems. This two-volume report provides the results of the project. Volume I describes the development of the Advanced HSI Design Review Guideline (DRG) including (1) its theoretical and technical foundation, (2) a general model for the review of advanced HSIs, (3) guideline development in both hard-copy and computer-based versions, and (4) the tests and evaluations performed to develop and validate the DRG. Volume I also includes a discussion of the gaps in available guidance and a methodology for addressing them. Volume 2 provides the guidelines to be used for advanced HSI review and the procedures for their use.
1994-07-01
Advanced control rooms will use advanced human-system interface (HSI) technologies that may have significant implications for plant safety in that they will affect the operator`s overall role in the system, the method of information presentation, and the ways in which operators interact with the system. The U.S. Nuclear Regulatory Commission (NRC) reviews the HSI aspects of control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported to protect public health and safety. The principal guidance available to the NRC, however, was developed more than ten years ago, well before these technological changes. Accordingly, the human factors guidance needs to be updated to serve as the basis for NRC review of these advanced designs. The purpose of this project was to develop a general approach to advanced HSI review and the human factors guidelines to support NRC safety reviews of advanced systems. This two-volume report provides the results of the project. Volume I describes the development of the Advanced HSI Design Review Guideline (DRG) including (1) its theoretical and technical foundation, (2) a general model for the review of advanced HSIs, (3) guideline development in both hard-copy and computer-based versions, and (4) the tests and evaluations performed to develop and validate the DRG. Volume I also includes a discussion of the gaps in available guidance and a methodology for addressing them. Volume 2 provides the guidelines to be used for advanced HSI review and the procedures for their use.
Tank waste remediation system process engineering instruction manual
The purpose of the Tank Waste Remediation System (TWRS) Process Engineering Instruction Manual is to provide guidance and direction to TWRS Process Engineering staff regarding conduct of business. The objective is to establish a disciplined and consistent approach to business such that the work processes within TWRS Process Engineering are safe, high quality, disciplined, efficient, and consistent with Lockheed Martin Hanford Corporation Policies and Procedures. The sections within this manual are of two types: for compliance and for guidance. For compliance sections are intended to be followed per-the-letter until such time as they are formally changed per Section 2.0 of this manual. For guidance sections are intended to be used by the staff for guidance in the conduct of work where technical judgment and discernment are required. The guidance sections shall also be changed per Section 2.0 of this manual. The required header for each manual section is illustrated in Section 2.0, Manual Change Control procedure. It is intended that this manual be used as a training and indoctrination resource for employees of the TWRS Process Engineering organization. The manual shall be required reading for all TWRS Process Engineering staff, matrixed, and subcontracted employees.
Tank waste remediation system process engineering instruction manual
The purpose of the Tank Waste Remediation System (TWRS) Process Engineering Instruction Manual is to provide guidance and direction to TWRS Process Engineering staff regarding conduct of business. The objective is to establish a disciplined and consistent approach to business such that the work processes within TWRS Process Engineering are safe, high quality, disciplined, efficient, and consistent with Lockheed Martin Hanford Corporation Policies and Procedures. The sections within this manual are of two types: for compliance and for guidance. For compliance sections are intended to be followed per-the-letter until such time as they are formally changed per Section 2.0 of this manual. For guidance sections are intended to be used by the staff for guidance in the conduct of work where technical judgment and discernment are required. The guidance sections shall also be changed per Section 2.0 of this manual. The required header for each manual section is illustrated in Section 2.0, Manual Change Control procedure. It is intended that this manual be used as a training and indoctrination resource for employees of the TWRS Process Engineering organization. The manual shall be required reading for all TWRS Process Engineering staff, matrixed, and subcontracted employees.
Tank waste remediation system process engineering instruction manual
1998-11-04
The purpose of the Tank Waste Remediation System (TWRS) Process Engineering Instruction Manual is to provide guidance and direction to TWRS Process Engineering staff regarding conduct of business. The objective is to establish a disciplined and consistent approach to business such that the work processes within TWRS Process Engineering are safe, high quality, disciplined, efficient, and consistent with Lockheed Martin Hanford Corporation Policies and Procedures. The sections within this manual are of two types: for compliance and for guidance. For compliance sections are intended to be followed per-the-letter until such time as they are formally changed per Section 2.0 of this manual. For guidance sections are intended to be used by the staff for guidance in the conduct of work where technical judgment and discernment are required. The guidance sections shall also be changed per Section 2.0 of this manual. The required header for each manual section is illustrated in Section 2.0, Manual Change Control procedure. It is intended that this manual be used as a training and indoctrination resource for employees of the TWRS Process Engineering organization. The manual shall be required reading for all TWRS Process Engineering staff, matrixed, and subcontracted employees.
A designed screening study with prespecified combinations of factor settings
In many applications, the experimenter has limited options about what factor combinations can be chosen for a designed study. Consider a screening study for a production process involving five input factors whose levels have been previously established. The goal of the study is to understand the effect of each factor on the response, a variable that is expensive to measure and results in destruction of the part. From an inventory of available parts with known factor values, we wish to identify a best collection of factor combinations with which to estimate the factor effects. Though the observational nature of the study cannot establish a causal relationship involving the response and the factors, the study can increase understanding of the underlying process. The study can also help determine where investment should be made to control input factors during production that will maximally influence the response. Because the factor combinations are observational, the chosen model matrix will be nonorthogonal and will not allow independent estimation of factor effects. In this manuscript we borrow principles from design of experiments to suggest an 'optimal' selection of factor combinations. Specifically, we consider precision of model parameter estimates, the issue of replication, and abilities to detect lack of fit and to estimate two-factor interactions. Through an example, we present strategies for selecting a subset of factor combinations that simultaneously balance multiple objectives, conduct a limited sensitivity analysis, and provide practical guidance for implementing our techniques across a variety of quality engineering disciplines.
A designed screening study with prespecified combinations of factor settings
2009-01-01
In many applications, the experimenter has limited options about what factor combinations can be chosen for a designed study. Consider a screening study for a production process involving five input factors whose levels have been previously established. The goal of the study is to understand the effect of each factor on the response, a variable that is expensive to measure and results in destruction of the part. From an inventory of available parts with known factor values, we wish to identify a best collection of factor combinations with which to estimate the factor effects. Though the observational nature of the study cannot establish a causal relationship involving the response and the factors, the study can increase understanding of the underlying process. The study can also help determine where investment should be made to control input factors during production that will maximally influence the response. Because the factor combinations are observational, the chosen model matrix will be nonorthogonal and will not allow independent estimation of factor effects. In this manuscript we borrow principles from design of experiments to suggest an 'optimal' selection of factor combinations. Specifically, we consider precision of model parameter estimates, the issue of replication, and abilities to detect lack of fit and to estimate two-factor interactions. Through an example, we present strategies for selecting a subset of factor combinations that simultaneously balance multiple objectives, conduct a limited sensitivity analysis, and provide practical guidance for implementing our techniques across a variety of quality engineering disciplines.
This report summarizes the consensus findings and recommendations emerging from 2007 Symposium, "Quality Assurance of Radiation Therapy: Challenges of Advanced Technology." The Symposium was held in Dallas February 20-22, 2007. The 3-day program, which was sponsored jointly by the American Society for Therapeutic Radiology and Oncology (ASTRO), American Association of Physicists in Medicine (AAPM), and National Cancer Institute (NCI), included >40 invited speakers from the radiation oncology and industrial engineering/human factor communities and attracted nearly 350 attendees, mostly medical physicists. A summary of the major findings follows. The current process of developing consensus recommendations for prescriptive quality assurance (QA) tests remains valid for many of the devices and software systems used in modern radiotherapy (RT), although for some technologies, QA guidance is incomplete or out of date. The current approach to QA does not seem feasible for image-based planning, image-guided therapies, or computer-controlled therapy. In these areas, additional scientific investigation and innovative approaches are needed to manage risk and mitigate errors, including a better balance between mitigating the risk of catastrophic error and maintaining treatment quality, complimenting the current device-centered QA perspective by a more process-centered approach, and broadening community participation in QA guidance formulation and implementation. Industrial engineers and human factor experts can make significant contributions toward advancing a broader, more process-oriented, risk-based formulation of RT QA. Healthcare administrators need to appropriately increase personnel and ancillary equipment resources, as well as capital resources, when new advanced technology RT modalities are implemented. The pace of formalizing clinical physics training must rapidly increase to provide an adequately trained physics workforce for advanced technology RT. The specific recommendations of the Symposium included the following. First, the AAPM, in cooperation with other advisory bodies, should undertake a systematic program to update conventional QA guidance using available risk-assessment methods. Second, the AAPM advanced technology RT Task Groups should better balance clinical process vs. device operation aspects--encouraging greater levels of multidisciplinary participation such as industrial engineering consultants and use-risk assessment and process-flow techniques. Third, ASTRO should form a multidisciplinary subcommittee, consisting of physician, physicist, vendor, and industrial engineering representatives, to better address modern RT quality management and QA needs. Finally, government and private entities committed to improved healthcare quality and safety should support research directed toward addressing QA problems in image-guided therapies.
A New Graphical Microburst Guidance Product
2010-02-12
A new microburst graphical guidance product has been developed that employs data from the Rapid Update Cycle (RUC) model. Prototypical conditions for microbursts include a steep temperature lapse rate and decreasing humidity with decreasing height in the boundary layer. Thus, the graphical guidance product incorporates boundary layer temperature lapse rate and vertical relative humidity difference, important factors in initiating and sustaining a convective downdraft. The new guidance product demonstrated effectiveness in indicating favorable conditions for downbursts during the 2009 convective season.
NUREG-0700, Revision 1, provides human factors engineering (HFE) guidance to the US Nuclear Regulatory Commission staff for its: (1) review of the human system interface (HSI) design submittals prepared by licensees or applications for a license or design certification of commercial nuclear power plants, and (2) performance of HSI reviews that could be undertaken as part of an inspection or other type of regulatory review involving HSI design or incidents involving human performance. The guidance consists of a review process and HFE guidelines. The document describes those aspects of the HSI design review process that are important to the identification and resolution of human engineering discrepancies that could adversely affect plant safety. Guidance is provided that could be used by the staff to review an applicant`s HSI design review process or to guide the development of an HSI design review plan, e.g., as part of an inspection activity. The document also provides detailed HFE guidelines for the assessment of HSI design implementations. NUREG-0700, Revision 1, consists of three stand-alone volumes. Volume 2 is a complete set of the guidelines contained in Volume 1, Part 2, but in a checklist format that can be used by reviewers to assemble sets of individual guidelines for use in specific design reviews. The checklist provides space for reviewers to enter guidelines evaluations and comments.
1996-06-01
NUREG-0700, Revision 1, provides human factors engineering (HFE) guidance to the US Nuclear Regulatory Commission staff for its: (1) review of the human system interface (HSI) design submittals prepared by licensees or applications for a license or design certification of commercial nuclear power plants, and (2) performance of HSI reviews that could be undertaken as part of an inspection or other type of regulatory review involving HSI design or incidents involving human performance. The guidance consists of a review process and HFE guidelines. The document describes those aspects of the HSI design review process that are important to the identification and resolution of human engineering discrepancies that could adversely affect plant safety. Guidance is provided that could be used by the staff to review an applicant`s HSI design review process or to guide the development of an HSI design review plan, e.g., as part of an inspection activity. The document also provides detailed HFE guidelines for the assessment of HSI design implementations. NUREG-0700, Revision 1, consists of three stand-alone volumes. Volume 2 is a complete set of the guidelines contained in Volume 1, Part 2, but in a checklist format that can be used by reviewers to assemble sets of individual guidelines for use in specific design reviews. The checklist provides space for reviewers to enter guidelines evaluations and comments.
Advances in lithium-ion batteries
The editors state in their introduction that this book is intended for lithium-ion scientists and engineers but they hope it may be of interest to scientists from other fields. Their main aim was to provide a snapshot of the state of the Lithium-ion art and in this they have largely succeeded. The book is comprised of a collection of very current reviews of the lithium ion battery literature by acknowledged experts that draw heavily on the authors' own research but are sufficiently general to provide the lithium ion researcher with enough guidance to the current literature and the current thinking in the field. Some of the literature references may be too current as there are numerous citations of conference proceedings which may be easily accessible to the lithium ion scientist or engineer but are not likely to be available to the interested chemist coming to the field for the first time. One author expresses the hope and expectation that properly peer-reviewed articles will appear in due course and the interested reader should look out for them in future. From the point of view of the lithium ion battery scientist and engineer, the book covers most of the topics that are of current interest. Two areas are treated by inference in the various chapters but are not specifically granted chapters of their own. One of these is safety and abuse tolerance and the other is cost. Since there are a number of groups active in the investigation of abuse tolerance of these batteries this is a curious omission and obviously the cost factor is a driver for commercial development. The book should be instructive to the chemical community provided the average chemist can obtain some guidance from an electrochemist or battery engineer. Many of the measurements and techniques referred to (e.g. impedance, capacities, etc.) may be somewhat unfamiliar and confusing in the context they are used. Chemists who persevere and can obtain some guidance will find some rich opportunities for the application of analytical, inorganic and organic chemistry to unravel some of the puzzling mysteries of lithium ion batteries. The book begins with an extended chapter on the crucial role of the surface films on electrodes which provides an excellent introduction to the state of thinking in this field. This work is a tour de force in the application of surface analytical techniques and clearly demonstrates some of the shortcomings in the mechanism development. Several other chapters also provide ample evidence of opportunities for mechanistic determination and the chemist may be left with a rather alarming impression of a very unstable electrolyte system. However, the chapter on surface films will sound familiar to any chemist who has suffered the vagaries of a recalcitrant Grignard reaction. Since the operation of these surface films is of such importance to lithium ion batteries one is amazed that their formation appears to be left to serendipity. Clearly, there are great opportunities here for imaginative chemists and engineers.
Advances in lithium-ion batteries
2003-06-24
The editors state in their introduction that this book is intended for lithium-ion scientists and engineers but they hope it may be of interest to scientists from other fields. Their main aim was to provide a snapshot of the state of the Lithium-ion art and in this they have largely succeeded. The book is comprised of a collection of very current reviews of the lithium ion battery literature by acknowledged experts that draw heavily on the authors' own research but are sufficiently general to provide the lithium ion researcher with enough guidance to the current literature and the current thinking in the field. Some of the literature references may be too current as there are numerous citations of conference proceedings which may be easily accessible to the lithium ion scientist or engineer but are not likely to be available to the interested chemist coming to the field for the first time. One author expresses the hope and expectation that properly peer-reviewed articles will appear in due course and the interested reader should look out for them in future. From the point of view of the lithium ion battery scientist and engineer, the book covers most of the topics that are of current interest. Two areas are treated by inference in the various chapters but are not specifically granted chapters of their own. One of these is safety and abuse tolerance and the other is cost. Since there are a number of groups active in the investigation of abuse tolerance of these batteries this is a curious omission and obviously the cost factor is a driver for commercial development. The book should be instructive to the chemical community provided the average chemist can obtain some guidance from an electrochemist or battery engineer. Many of the measurements and techniques referred to (e.g. impedance, capacities, etc.) may be somewhat unfamiliar and confusing in the context they are used. Chemists who persevere and can obtain some guidance will find some rich opportunities for the application of analytical, inorganic and organic chemistry to unravel some of the puzzling mysteries of lithium ion batteries. The book begins with an extended chapter on the crucial role of the surface films on electrodes which provides an excellent introduction to the state of thinking in this field. This work is a tour de force in the application of surface analytical techniques and clearly demonstrates some of the shortcomings in the mechanism development. Several other chapters also provide ample evidence of opportunities for mechanistic determination and the chemist may be left with a rather alarming impression of a very unstable electrolyte system. However, the chapter on surface films will sound familiar to any chemist who has suffered the vagaries of a recalcitrant Grignard reaction. Since the operation of these surface films is of such importance to lithium ion batteries one is amazed that their formation appears to be left to serendipity. Clearly, there are great opportunities here for imaginative chemists and engineers.
This technical note contains assessments of conventional and special-purpose dredges in removing sediment with minimal sediment resuspension. If sediment resuspension is a critical factor in dredging areas of contaminated material, the following guidance will aid in specifying the dredge and operating conditions. Investigations were conducted as part of the Corps of Engineers Improvement of Operations and Maintenance Techniques (IOMT) Research Program to evaluate the resuspension of sediment into the water column due to dredging operations. Laboratory, field, and literature studies have been used to define the sediment resuspension characteristics of most conventional and several special-purpose dredges. The natural hydrophobic tendency of most organic contaminants and the high sediment-sorptive capacity for inorganic contaminants limits release to the soluble forms and makes the simple measure of sediment resuspension during dredging a relative measure of the potential for contaminant release.
1986-12-01
This technical note contains assessments of conventional and special-purpose dredges in removing sediment with minimal sediment resuspension. If sediment resuspension is a critical factor in dredging areas of contaminated material, the following guidance will aid in specifying the dredge and operating conditions. Investigations were conducted as part of the Corps of Engineers Improvement of Operations and Maintenance Techniques (IOMT) Research Program to evaluate the resuspension of sediment into the water column due to dredging operations. Laboratory, field, and literature studies have been used to define the sediment resuspension characteristics of most conventional and several special-purpose dredges. The natural hydrophobic tendency of most organic contaminants and the high sediment-sorptive capacity for inorganic contaminants limits release to the soluble forms and makes the simple measure of sediment resuspension during dredging a relative measure of the potential for contaminant release.
Stability of existing concrete gravity dams
2001-10-01
In excess of 197 concrete dams are owned by Hydro-Quebec, and 56 per cent of those have a height that exceeds 15 metres. Over 55 per cent of dams have passed the 50 year mark. Dam safety engineers have always been challenged by stability evaluation of existing dams. To assist the engineers, they are in possession of guides where the criteria are expressed in terms of applied loads, safety factors and allowable stresses. Some guidance was provided in the past into the evaluation of existing dams by the Canadian Dam Association (CDA), the Federal Energy Regulatory Commission (FERC), and the United States Army Corps of Engineers (USACE). Work has been undertaken by Hydro-Quebec to develop an approach for structural stability evaluation of gravity dams based on recent developments. A series of stability analyses on section profiles based on existing Hydro-Quebec gravity dams is presented in this paper. The authors identified the main parameters controlling the safety assessment in various load combinations. They also proposed a few rational strategies to minimize the uncertainty of these parameters. The paper also discusses the consideration of monitoring data in the stability study. 8 refs., 9 tabs., 2 figs.
Precision missile guidance for systems intercepting at small attack angles : a H tracking approach
2003-01-01
This paper uses the H1 tracking ideas in the missile guidance problem. The controller performs as a Precision guidance controller for small desired attack angles although theoretically the formulas are valid (when intercepting a maneuvering target in a precision guidance point of view) only for the case of head on collision. The controller essentially navigates the missile in a unique relative arc that is de ned by the missile and target location and the desired attack angle. Publisher: CIRAS Organising Committee Contributor: Vadakkepat, Prahlad Relation: isMemberOf: ERA cluster 3 : Engineering and Environmental Sciences collection; isMemberOf: School of Engineering and Technology collection Coverage: 2003-01-01 Language: eng Rights: 2003, Center for Intelligent Control, National University of Singapore
Induction of cellular growth by the axon guidance regulators Netrin A and Semaphorin-1a
2010-01-01
Although neurite outgrowth has been linked to axon guidance regulators, the effects of guidance molecules on cellular growth are not well understood. Use of the Drosophila wing imaginal disc, an epithelial tissue and a well-characterized system for analysis of cellular growth regulation, permits analysis of the impacts of guidance molecules on cellular growth in a setting in which axon guidance is not a confounding factor. In this investigation, the impacts of Netrin A (NetA) and Semaphorin-1a (Sema1a) signaling on cellular growth are examined during wing development. Levels of these genes were modulated in somatic clones in the developing wing disc, and clone areas, as well as individual sizes of clonal cells were assessed. NetA and Sema1a signaling were found to induce cellular growth in...
SAFETY ENGINEERING FOR THE RELATIVISTIC HEAVY ION COLLIDER AT THE BROOKHAVEN NATIONAL LABORATORY
1999-01-01
THERE ARE ONLY A FEW OTHER HIGH ENERGY PARTICLE ACCELERATORS LIKE RHIC IN THE WORLD. THEREFORE, THE DESIGNERS OF THE MACHINE DO NOT ALWAYS HAVE CONSENSUS DESIGN STANDARDS AND REGULATORY GUIDANCE AVAILABLE TO ESTABLISH THE ENGINEERING PARAMETERS FOR SAFETY. SOME OF THE AREAS WHERE STANDARDS ARE NOT AVAILABLE RELATE TO THE CRYOGENIC SYSTEM, CONTAINMENT OF LARGE VOLUMES OF FLAMMABLE GAS IN FRAGILE VESSELS IN THE EXPERIMENTAL APPARATUS AND MITIGATION OF A DESIGN BASIS ACCIDENT WITH A STORED PARTICLE BEAM. UNIQUE BUT EQUIVALENT SAFETY ENGINEERING MUST BE DETERMINED. SPECIAL DESIGN CRITERIA FOR PROMPT RADIATION WERE DEVELOPED TO PROVIDE GUIDANCE FOR THE DESIGN OF RADIATION SHIELDING
RIVER BANK STABILISATION USING VEGETATION WITH SPECIAL REFERENCE TO WILLOWS
1997-04-30
ObjectivesObjectives Not AvailableDescriptionEmphasis in waterway bank protection is moving away from the use of hard engineering materials, such as sheet-piling and concrete, towards the use of soft protection based on flexible materials. Vegetation, often living, is widely advocated as part of a soft-engineering solution but detailed guidance for engineers and landowners wishing to use living vegetation does not exist. In this scoping research, the basis for development of design guidance would be established. This would involve colle [continued...]
Classification guide: Nuclear rocket engine program
1956-09-14
This guide deals with the classification of nuclear rocket engines and their development. Only very general guidance can be given on the classification of vehicles because their characteristics are not established, and because vehicle classification is essentially a military concern. Restricted Data as defined in the Atomic Energy Act of 1954 may be expected to occur in the nuclear rocket program only in the reactor itself (excepting the warhead, for which classification guidance is given in the AEC-DOD Classification Guide). Non-nuclear phases of the engine, propellant storage and handling systems, and the vehicle itself may require protection as Defense Information, but will not, in general, reveal Restricted Data.
Tailoring engineering activities to D and D projects - 16056
2009-01-01
Engineering is an important element of Deactivation and Decommissioning (D and D) project technical planning, scheduling, estimating, and execution. Understanding the scope of engineering and related design, deciding when in a project's schedule these activities should be conducted, and specifying the products to be generated from each engineering task are important management functions. These subjects are addressed in a guidance report developed by the U.S. Department of Energy (DOE) described in this paper. (authors)
Guidance Manual for Conducting Screening Level Ecological Risk Assessments at the INEL
This document presents reference material for conducting screening level ecological risk assessments (SLERAs)for the waste area groups (WAGs) at the Idaho National Engineering Laboratory. Included in this document are discussions of the objectives of and processes for conducting SLERAs. The Environmental Protection Agency ecological risk assessment framework is closely followed. Guidance for site characterization, stressor characterization, ecological effects, pathways of contaminant migration, the conceptual site model, assessment endpoints, measurement endpoints, analysis guidance, and risk characterization are included.
Guidance Manual for Conducting Screening Level Ecological Risk Assessments at the INEL
This document presents reference material for conducting screening level ecological risk assessments (SLERAs)for the waste area groups (WAGs) at the Idaho National Engineering Laboratory. Included in this document are discussions of the objectives of and processes for conducting SLERAs. The Environmental Protection Agency ecological risk assessment framework is closely followed. Guidance for site characterization, stressor characterization, ecological effects, pathways of contaminant migration, the conceptual site model, assessment endpoints, measurement endpoints, analysis guidance, and risk characterization are included.
Guidance Manual for Conducting Screening Level Ecological Risk Assessments at the INEL
1995-06-01
This document presents reference material for conducting screening level ecological risk assessments (SLERAs)for the waste area groups (WAGs) at the Idaho National Engineering Laboratory. Included in this document are discussions of the objectives of and processes for conducting SLERAs. The Environmental Protection Agency ecological risk assessment framework is closely followed. Guidance for site characterization, stressor characterization, ecological effects, pathways of contaminant migration, the conceptual site model, assessment endpoints, measurement endpoints, analysis guidance, and risk characterization are included.
Human factors review for Severe Accident Sequence Analysis (SASA)
1984-01-01
The paper will discuss work being conducted during this human factors review including: (1) support of the Severe Accident Sequence Analysis (SASA) Program based on an assessment of operator actions, and (2) development of a descriptive model of operator severe accident management. Research by SASA analysts on the Browns Ferry Unit One (BF1) anticipated transient without scram (ATWS) was supported through a concurrent assessment of operator performance to demonstrate contributions to SASA analyses from human factors data and methods. A descriptive model was developed called the Function Oriented Accident Management (FOAM) model, which serves as a structure for bridging human factors, operations, and engineering expertise and which is useful for identifying needs/deficiencies in the area of accident management. The assessment of human factors issues related to ATWS required extensive coordination with SASA analysts. The analysis was consolidated primarily to six operator actions identified in the Emergency Procedure Guidelines (EPGs) as being the most critical to the accident sequence. These actions were assessed through simulator exercises, qualitative reviews, and quantitative human reliability analyses. The FOAM descriptive model assumes as a starting point that multiple operator/system failures exceed the scope of procedures and necessitates a knowledge-based emergency response by the operators. The FOAM model provides a functionally-oriented structure for assembling human factors, operations, and engineering data and expertise into operator guidance for unconventional emergency responses to mitigate severe accident progression and avoid/minimize core degradation. Operators must also respond to potential radiological release beyond plant protective barriers. Research needs in accident management and potential uses of the FOAM model are described. 11 references, 1 figure.
NASA Space Flight Human System Standards
NASA has begun a new approach to human factors design standards. For years NASA-STD-3000, Manned Systems Integration Standards, has been a source of human factors design guidance for space systems. In order to ...
Planning aquatic ecosystem restoration monitoring programs
This study was conducted as part of the Evaluation of Environmental Investments Research Program (EEIRP). The EEIRP is sponsored by the US Army Corps of Engineers. The objectives of this work are to (1) identify relevant approaches and features for environmental investment measures to be applied throughout the project life; (2) develop methods to access the effectiveness of the approach or feature for providing the intended environmental output; (3) develop and provide guidance for formulating environmental projects; and (4) provide guidance for formulating and identifying relevant cost components of alternate restoration plans.
Planning aquatic ecosystem restoration monitoring programs
This study was conducted as part of the Evaluation of Environmental Investments Research Program (EEIRP). The EEIRP is sponsored by the US Army Corps of Engineers. The objectives of this work are to (1) identify relevant approaches and features for environmental investment measures to be applied throughout the project life; (2) develop methods to access the effectiveness of the approach or feature for providing the intended environmental output; (3) develop and provide guidance for formulating environmental projects; and (4) provide guidance for formulating and identifying relevant cost components of alternate restoration plans.
Planning aquatic ecosystem restoration monitoring programs
1997-01-01
This study was conducted as part of the Evaluation of Environmental Investments Research Program (EEIRP). The EEIRP is sponsored by the US Army Corps of Engineers. The objectives of this work are to (1) identify relevant approaches and features for environmental investment measures to be applied throughout the project life; (2) develop methods to access the effectiveness of the approach or feature for providing the intended environmental output; (3) develop and provide guidance for formulating environmental projects; and (4) provide guidance for formulating and identifying relevant cost components of alternate restoration plans.
Data Summary for the Pre Survey Interim Status Closure of the Area 514 Facility
The purpose of this document is to summarize the data obtained from the sampling and analysis of selected locations in the Area 514 Facility. The objective of this document is to evaluate the data in a manner that will provide guidance for the final closure document. This guidance will assist in designing a sampling and analysis plan that will be efficient, cost effective and meet the criteria for acceptance by a independent state certified engineer for completion of the closure activity.
Data Summary for the Pre Survey Interim Status Closure of the Area 514 Facility
2003-10-13
The purpose of this document is to summarize the data obtained from the sampling and analysis of selected locations in the Area 514 Facility. The objective of this document is to evaluate the data in a manner that will provide guidance for the final closure document. This guidance will assist in designing a sampling and analysis plan that will be efficient, cost effective and meet the criteria for acceptance by a independent state certified engineer for completion of the closure activity.
Collection of papers of the 31st Israel Annual Conference on Aviation and Astronautics
1992-02-01
Subjects covered by the 56 papers include: hypersonics and advanced aircraft design; control systems design and evaluation; aircraft and spacecraft navigation; rocket ramjet and turbine engine design and development; development, evaluation and applications of synthetic materials; design and construction of space structures; missile guidance, control and avoidance; spacecraft, aircraft and missile propulsion; guidance systems; and aerodynamics. Separate abstracts have been prepared for articles from this report.
Use of BWRVIP inspection and evaluation guidance at peach bottom atomic power station
2001-01-01
The full text follows. Peach Bottom Atomic Power Station (PBAPS) has always been proactive with respect to inspection of its boiling water reactors. Internal visual in-service inspections (IVVI) of the reactor vessel internals have been conducted at the PBAPS for many years. The scope and methods of these inspections were primarily driven by conservative interpretations of the American Society of Mechanical Engineers (ASME). Boiler and Pressure Vessel Code, Section XI, 'Rules for In-service Inspection of Nuclear Power Plant Components'. In addition, industry recommendations, regulatory requirements augmenting Code guidance, and investment protection were also used for guidance. With the formation of the Boiling Water Reactor Vessel and Internals Project in 1994, comprehensive and systematic guidance for the inspection of the reactor internals became available. ...
ENLIGHTENED PLANNING: BRINGING SOLAR ENERGY INTO THE URBAN PLANNING PROCESS
2000-11-23
ObjectivesThe aim is to produce computer tools linked to a GIS for evaluating the solar energy potential (SEP) of buildings in urban environments.~%~Objectives are:~%~i) to develop data collection and analysis techniques which will capture the key factors affecting the SEP of buildings.~%~ii) to produce a database structure and software which will enable the key factors to be entered.~%~iii) to create the core engine for calculating the solar energy available to buildings.~%~iv) to establish methods for c [continued...]DescriptionBy using solar energy the consumption of non-renewable energy in uildings can be significantly reduced. Local authorities and other have developed, or are in the process of developing, supplementary planning guidance aimed at harnessing this resource. There is no tool which enables the SEP of urban developments to be quantified, targets for solar energy utilisation will be set, policies to be enforced and their effect to be audited. This project will produce a SEP tools, compatible with oth [continued...]
TRAJECTORY OPTIMIZATION AND GUIDANCE FOR AN AEROSPACE PLANE
model of a hypersonic air-breathing single-stage-to-orbit vehicle ... by the added weight of the ramjet engine and the structural reinforcements required ..... OTIS needs an initial estimate, preferably a feasible trajectory. ...
NASA - Return to Flight Task Group Biographies
Joseph Cuzzupoli brings to the Task Group more than 40 years of aerospace ... of Science degree in Mechanical Engineering from the Maine Maritime Academy, .... guidance system; and an action officer on the Air Staff in the Pentagon. ...
1994-12-31
A short term district heat forecasting model based upon knowledge engineering has been developed. The knowledge base consists of both heuristic and through mathematical analyses of history data gathered knowledge. The developed program uses the gathered knowledge and produces, without any guidance of an operator, hourly forecasts for 1-2 days. The principle of the model is to find and use suitable comparison days from the history base. Comparison days give the forecast the right consumption rhythm and dynamics of effect changes. Three comparison days, which best portray the day-type and weather conditions of the forecast day, are chosen. A typical days, like christmas holidays or the Day of Independence, are especially differentiated in the search for matching comparison days. Outside factors, like outside temperature, are taken into consideration with a correlation matrix. The outside temperature correlation matrix is day-time, day-type and season-of-year dependable. Other weather factors, for example solar radiation or wind, can be connected to the forecast. The final forecast is achieved with the comparison days and the weather corrections. The use of knowledge engineering as programming environment is based on easy accomplishing of deduction paths and the possibility to insert qualitative factors in the decision making. Interactive use of the model is relatively simply attained with the Nexpert Object-software. To run the forecast program a Nexpert Object-runtime version is needed. The developed model is installed at the Electricity Board of Tampere. The application of the new programming technique in a practical environment and the analysis of the functionality of the forecasting model, as well as to make necessary corrections, are part of a follow-up study, from which there will be a separate report
The Engineering Compliance Program development process and its role in design
1997-12-01
This paper presents an overview of the Engineering Compliance Program (ECP) development process and its role in design. The ECP is a formal program to assess Nuclear Regulatory Commission (NRC) regulatory guidance in terms of precedence, industry experience documents, and codes and standards to determine their applicability to Mined Geologic Disposal System (MGDS) design. These determinations are documented in ECP Guidance Packages for MGDS Structures, Systems and Components (SSCs). This ensures that the license application appropriately reflects the MGDS design and facilitates NRC acceptance and compliance review.
In this report, the Idaho National Engineering Laboratory reviewers discuss related to requests for relief from the American Society of Mechanical Engineers code requirements for inservice testing (IST) of safety-related pumps and valves at commercial nuclear power plants. This report compiles information and examples that may be useful to licensees in developing relief requests submitted to US Nuclear Regulatory Commission (NRC) for their consideration and provides insights and recommendations on related IST issues. The report also gives specific guidance on relief requests acceptable and not acceptable to the NRC and advises licensees in the use of this information for application at their facilities.
Environmental restoration value engineering guidance document
1995-07-01
This document provides guidance on Value Engineering (VE). VE is an organized team effort led by a person trained in the methodology to analyze the functions of projects, systems, equipment, facilities, services, and processes for achieving the essential functions at the lowest life cycle cost while maintaining required performance, reliability, availability, quality, and safety. VE has proven to be a superior tool to improve up-front project planning, cut costs, and create a better value for each dollar spent. This document forms the basis for the Environmental Restoration VE Program, describes the VE process, and provides recommendations on when it can be most useful on ER projects.
1994-12-31
The integrated nuclear data evaluation system (INDES) is being made in order to support the nuclear data evaluation work. A guidance system in INDES, `Evaluation Tutor (ET)`, is under development in order to support users in selecting the most suitable set of theoretical calculation codes by applying knowledge engineering technology and the experiences of evaluation work for JENDL-3. In this paper, the function of ET is introduced as well as the functions and databases of INDES. An example run of ET for {sup 56}Fe in the 1-20 MeV neutron energy region is also explained. (author).
2002-01-01
Institute of Physics and Engineering in Medicine York: IPEM 225 pp, ISBN: 1-903613-09-4. This book is the much awaited replacement for the old yellow 'Guidance Notes' published in 1988 by the National Radiological Protection Board (NRPB). Since then nearly all Regulations covering the use of ionising radiation have been updated. The Institute of Physics and Engineering in Medicine (IPEM) established a working group in 1999 to produce a first draft for consultation (produced in April 2000) and to consider subsequent comments to this draft. The final document, published by IPEM, is therefore the end product of numerous contributions from professionals working in healthcare and wide consultation with professional bodies, the NRPB, UK Health Departments, Environment Agencies and the HSE. The notes provide general guidance on good practice - not just legal requirements. ...
This technical note provides initial guidance for interpreting the biological consequences of bioaccumulation in aquatic organisms. Specifically, the relationship between polychlorinated biphenyl (PCB) tissue residues and reproductive success in the fathead minnow, Pimephales promelas, is examined. The US Army Corps of Engineers often conducts, or requires to be conducted, an assessment of potential bioaccumulation of environmental contaminants from sediments scheduled for dredging and open-water disposal. At present, however, there is no generally accepted guidance to assist in the interpretation of the biological consequences of specific levels of bioacumulation. To provide an initial basis for such guidance, the Environmental Laboratory of the US Army Engineer Waterways Experiment Station is conducting both literature data base analyses and experimental laboratory studies as part of its Long-Term Effects of Dredging Operations (LEDO) Program. This technical note discusses a portion of the laboratory effort.
Enhancing the Guidance of the Intentional Model "MAP": Graph Theory Application
2009-11-04
The MAP model was introduced in information system engineering in order to model processes on a flexible way. The intentional level of this model helps an engineer to execute a process with a strong relationship to the situation of the project at hand. In the literature, attempts for having a practical use of maps are not numerous. Our aim is to enhance the guidance mechanisms of the process execution by reusing graph algorithms. After clarifying the existing relationship between graphs and maps, we improve the MAP model by adding qualitative criteria. We then offer a way to express maps with graphs and propose to use Graph theory algorithms to offer an automatic guidance of the map. We illustrate our proposal by an example and discuss its limitations.
Human Factors Considerations in New Nuclear Power Plants: Detailed Analysis.
This Nuclear Regulatory Commission (NRC) sponsored study has identified human-performance issues in new and advanced nuclear power plants. To identify the issues, current industry developments and trends were evaluated in the areas of reactor technology, instrumentation and control technology, human-system integration technology, and human factors engineering (HFE) methods and tools. The issues were organized into seven high-level HFE topic areas: Role of Personnel and Automation, Staffing and Training, Normal Operations Management, Disturbance and Emergency Management, Maintenance and Change Management, Plant Design and Construction, and HFE Methods and Tools. The issues where then prioritized into four categories using a 'Phenomena Identification and Ranking Table' methodology based on evaluations provided by 14 independent subject matter experts. The subject matter experts were knowledgeable in a variety of disciplines. Vendors, utilities, research organizations and regulators all participated. Twenty issues were categorized into the top priority category. This Brookhaven National Laboratory (BNL) technical report provides the detailed methodology, issue analysis, and results. A summary of the results of this study can be found in NUREG/CR-6947. The research performed for this project has identified a large number of human-performance issues for new control stations and new nuclear power plant designs. The information gathered in this project can serve as input to the development of a long-term strategy and plan for addressing human performance in these areas through regulatory research. Addressing human-performance issues will provide the technical basis from which regulatory review guidance can be developed to meet these challenges. The availability of this review guidance will help set clear expectations for how the NRC staff will evaluate new designs, reduce regulatory uncertainty, and provide a well-defined path to new nuclear power plant licensing.
Human Factors Considerations in New Nuclear Power Plants: Detailed Analysis.
2008-02-14
This Nuclear Regulatory Commission (NRC) sponsored study has identified human-performance issues in new and advanced nuclear power plants. To identify the issues, current industry developments and trends were evaluated in the areas of reactor technology, instrumentation and control technology, human-system integration technology, and human factors engineering (HFE) methods and tools. The issues were organized into seven high-level HFE topic areas: Role of Personnel and Automation, Staffing and Training, Normal Operations Management, Disturbance and Emergency Management, Maintenance and Change Management, Plant Design and Construction, and HFE Methods and Tools. The issues where then prioritized into four categories using a 'Phenomena Identification and Ranking Table' methodology based on evaluations provided by 14 independent subject matter experts. The subject matter experts were knowledgeable in a variety of disciplines. Vendors, utilities, research organizations and regulators all participated. Twenty issues were categorized into the top priority category. This Brookhaven National Laboratory (BNL) technical report provides the detailed methodology, issue analysis, and results. A summary of the results of this study can be found in NUREG/CR-6947. The research performed for this project has identified a large number of human-performance issues for new control stations and new nuclear power plant designs. The information gathered in this project can serve as input to the development of a long-term strategy and plan for addressing human performance in these areas through regulatory research. Addressing human-performance issues will provide the technical basis from which regulatory review guidance can be developed to meet these challenges. The availability of this review guidance will help set clear expectations for how the NRC staff will evaluate new designs, reduce regulatory uncertainty, and provide a well-defined path to new nuclear power plant licensing.
This report summarizes the consensus findings and recommendations emerging from 2007 Symposium, 'Quality Assurance of Radiation Therapy: Challenges of Advanced Technology.' The Symposium was held in Dallas February 20-22, 2007. The 3-day program, which was sponsored jointly by the American Society for Therapeutic Radiology and Oncology (ASTRO), American Association of Physicists in Medicine (AAPM), and National Cancer Institute (NCI), included >40 invited speakers from the radiation oncology and industrial engineering/human factor communities and attracted nearly 350 attendees, mostly medical physicists. A summary of the major findings follows. The current process of developing consensus recommendations for prescriptive quality assurance (QA) tests remains valid for many of the devices and software systems used in modern radiotherapy (RT), although for some technologies, QA guidance is incomplete or out of date. The current approach to QA does not seem feasible for image-based planning, image-guided therapies, or computer-controlled therapy. In these areas, additional scientific investigation and innovative approaches are needed to manage risk and mitigate errors, including a better balance between mitigating the risk of catastrophic error and maintaining treatment quality, complimenting the current device-centered QA perspective by a more process-centered approach, and broadening community participation in QA guidance formulation and implementation. Industrial engineers and human factor experts can make significant contributions toward advancing a broader, more process-oriented, risk-based formulation of RT QA. Healthcare administrators need to appropriately increase personnel and ancillary equipment resources, as well as capital resources, when new advanced technology RT modalities are implemented. The pace of formalizing clinical physics training must rapidly increase to provide an adequately trained physics workforce for advanced technology RT. The specific recommendations of the Symposium included the following. First, the AAPM, in cooperation with other advisory bodies, should undertake a systematic program to update conventional QA guidance using available risk-assessment methods. Second, the AAPM advanced technology RT Task Groups should better balance clinical process vs. device operation aspects-encouraging greater levels of multidisciplinary participation such as industrial engineering consultants and use-risk assessment and process-flow techniques. Third, ASTRO should form a multidisciplinary subcommittee, consisting of physician, physicist, vendor, and industrial engineering representatives, to better address modern RT quality management and QA needs. Finally, government and private entities committed to improved healthcare quality and safety should support research directed toward addressing QA problems in image-guided therapies.
1989-12-01
The semiconductor product engineers job requires knowledge and expertise related to many different subjects. This report provides guidance for newcomers to product engineering and is a consise reference for all others involved in product engineering. Subjects addressed are Customer/Supplier interactions, component development sequence, production schedule support, component characterization, product specifications, test equipment requirements, product qualification, characterization and development reports, preferred parts list, standard packaging, and finally, classification and security considerations. This guide is intended to help standardize and simplify the component development sequence presently used in the semiconductor product engineering department. 3 figs., 2 tabs.
Nuclear plant operators face a significant challenge designing and modifying control rooms. This report provides guidance on planning, designing, implementing and operating modernized control rooms and digital human-system interfaces.
Nuclear plant operators face a significant challenge designing and modifying control rooms. This report provides guidance on planning, designing, implementing and operating modernized control rooms and digital human-system interfaces.
2004-11-30
Nuclear plant operators face a significant challenge designing and modifying control rooms. This report provides guidance on planning, designing, implementing and operating modernized control rooms and digital human-system interfaces.
Local control stations: Human engineering issues and insights
The objective of this research project was to evaluate current human engineering at local control stations (LCSs) in nuclear power plants, and to identify good human engineering practices relevant to the design of these operator interfaces. General literature and reports of operating experience were reviewed to determine the extent and type of human engineering deficiencies at LCSs in nuclear power plants. In-plant assessments were made of human engineering at single-function as well as multifunction LCSs. Besides confirming the existence of human engineering deficiencies at LCSs, the in-plant assessments provided information about the human engineering upgrades that have been made at nuclear power plants. Upgrades were typically the result of any of three influences regulatory activity, broad industry initiatives such as INPO, and specific in-plant programs (e.g. activities related to training). It is concluded that the quality of LCSs is quite variable and might be improved if there were greater awareness of good practices and existing human engineering guidance relevant to these operator interfaces, which is available from a variety of sources. To make such human engineering guidance more readily accessible, guidelines were compiled from such sources and included in the report as an appendix.
Local control stations: Human engineering issues and insights
1994-09-01
The objective of this research project was to evaluate current human engineering at local control stations (LCSs) in nuclear power plants, and to identify good human engineering practices relevant to the design of these operator interfaces. General literature and reports of operating experience were reviewed to determine the extent and type of human engineering deficiencies at LCSs in nuclear power plants. In-plant assessments were made of human engineering at single-function as well as multifunction LCSs. Besides confirming the existence of human engineering deficiencies at LCSs, the in-plant assessments provided information about the human engineering upgrades that have been made at nuclear power plants. Upgrades were typically the result of any of three influences regulatory activity, broad industry initiatives such as INPO, and specific in-plant programs (e.g. activities related to training). It is concluded that the quality of LCSs is quite variable and might be improved if there were greater awareness of good practices and existing human engineering guidance relevant to these operator interfaces, which is available from a variety of sources. To make such human engineering guidance more readily accessible, guidelines were compiled from such sources and included in the report as an appendix.
Use of BWRVIP inspection and evaluation guidance at peach bottom atomic power station
2001-07-01
The full text follows. Peach Bottom Atomic Power Station (PBAPS) has always been proactive with respect to inspection of its boiling water reactors. Internal visual in-service inspections (IVVI) of the reactor vessel internals have been conducted at the PBAPS for many years. The scope and methods of these inspections were primarily driven by conservative interpretations of the American Society of Mechanical Engineers (ASME); Boiler and Pressure Vessel Code, Section XI, 'Rules for In-service Inspection of Nuclear Power Plant Components'. In addition, industry recommendations, regulatory requirements augmenting Code guidance, and investment protection were also used for guidance. With the formation of the Boiling Water Reactor Vessel and Internals Project in 1994, comprehensive and systematic guidance for the inspection of the reactor internals became available. Inspection recommendations, along with defendable methods for dealing with identified degradation were published on an ongoing basis. This consistent guidance enabled PBAPS to more crisply focus its resources on the appropriate inspections of its reactors. The guidance allowed retention of the proactive inspection effort, and provided the ability to develop a more proactive program for dealing with inspection results. The BWRVIP guidance also enabled sound decisions regarding repair or replacement of internal components, as well mitigation measures that could be undertaken to reduce or eliminate the internals degradation phenomenon. The objective of this paper is to explain the approach used by PBAPS to integrate the evolving BWRVIP guidance into its existing Inservice Inspection Programs. Additionally, the paper will describe specific scenarios that occurred during the implementation of this effort, and the approach used by PBAPS to apply the BWRVIP guidance toward resolution of the related issues. The paper will provide a model for successful use of BWRVIP products, and explain the process used to satisfy commitments made by this Industry Initiative on behalf of its participating utilities. (author)
Low-level radioactive waste disposal facility closure
Part I of this report describes and evaluates potential impacts associated with changes in environmental conditions on a low-level radioactive waste disposal site over a long period of time. Ecological processes are discussed and baselines are established consistent with their potential for causing a significant impact to low-level radioactive waste facility. A variety of factors that might disrupt or act on long-term predictions are evaluated including biological, chemical, and physical phenomena of both natural and anthropogenic origin. These factors are then applied to six existing, yet very different, low-level radioactive waste sites. A summary and recommendations for future site characterization and monitoring activities is given for application to potential and existing sites. Part II of this report contains guidance on the design and implementation of a performance monitoring program for low-level radioactive waste disposal facilities. A monitoring programs is described that will assess whether engineered barriers surrounding the waste are effectively isolating the waste and will continue to isolate the waste by remaining structurally stable. Monitoring techniques and instruments are discussed relative to their ability to measure (a) parameters directly related to water movement though engineered barriers, (b) parameters directly related to the structural stability of engineered barriers, and (c) parameters that characterize external or internal conditions that may cause physical changes leading to enhanced water movement or compromises in stability. Data interpretation leading to decisions concerning facility closure is discussed. 120 refs., 12 figs., 17 tabs.
Low-level radioactive waste disposal facility closure
1990-11-01
Part I of this report describes and evaluates potential impacts associated with changes in environmental conditions on a low-level radioactive waste disposal site over a long period of time. Ecological processes are discussed and baselines are established consistent with their potential for causing a significant impact to low-level radioactive waste facility. A variety of factors that might disrupt or act on long-term predictions are evaluated including biological, chemical, and physical phenomena of both natural and anthropogenic origin. These factors are then applied to six existing, yet very different, low-level radioactive waste sites. A summary and recommendations for future site characterization and monitoring activities is given for application to potential and existing sites. Part II of this report contains guidance on the design and implementation of a performance monitoring program for low-level radioactive waste disposal facilities. A monitoring programs is described that will assess whether engineered barriers surrounding the waste are effectively isolating the waste and will continue to isolate the waste by remaining structurally stable. Monitoring techniques and instruments are discussed relative to their ability to measure (a) parameters directly related to water movement though engineered barriers, (b) parameters directly related to the structural stability of engineered barriers, and (c) parameters that characterize external or internal conditions that may cause physical changes leading to enhanced water movement or compromises in stability. Data interpretation leading to decisions concerning facility closure is discussed. 120 refs., 12 figs., 17 tabs.
Advanced control room (ACR) concepts are being developed in the commercial nuclear industry as part of future reactor designs. The ACRs will use advanced human-system interface (HSI) technologies that may have significant implications for plant safety in that they will affect the operator`s overall role (function) in the system, the method of information presentation, the ways in which the operator interacts with the system, and the requirements on the operator to understand and supervise an increasingly complex system. The U.S. Nuclear Regulatory Commission (NRC) reviews the HSI aspects of control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported to protect public health and safety. The NRC is developing guidelines to support their review of these advanced designs. As part of this effort, a methodology for guidance development was established, and topics in need of further research were identified. Simulators of various kinds are likely to play important roles in the development of review guidelines and in the evaluation of ACRs. This paper describes a general approach to review criteria development, and discusses the role of simulators in addressing research needs.
1994-04-01
Advanced control room (ACR) concepts are being developed in the commercial nuclear industry as part of future reactor designs. The ACRs will use advanced human-system interface (HSI) technologies that may have significant implications for plant safety in that they will affect the operator`s overall role (function) in the system, the method of information presentation, the ways in which the operator interacts with the system, and the requirements on the operator to understand and supervise an increasingly complex system. The U.S. Nuclear Regulatory Commission (NRC) reviews the HSI aspects of control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported to protect public health and safety. The NRC is developing guidelines to support their review of these advanced designs. As part of this effort, a methodology for guidance development was established, and topics in need of further research were identified. Simulators of various kinds are likely to play important roles in the development of review guidelines and in the evaluation of ACRs. This paper describes a general approach to review criteria development, and discusses the role of simulators in addressing research needs.
Review of advanced control rooms: Methodological considerations for the use of HFE guidelines
1994-03-01
Control rooms for advanced nuclear power plants use advanced human-system interface (HSI) technologies that may have significant implications for plant safety in that they will affect the operator`s overall role in the system and the ways in which operators interact with the system. The US Nuclear Regulatory Commission (NRC) reviews HSIs to ensure that they are designed to accepted human factors engineering (HFE) principles. The principal review guidance, however, is more than ten-years old (US NRC, 1981). Accordingly, an Advanced HSI Design Review Guideline (DRG) was developed to provide criteria for these reviews. The DRG contains seven major sections: Information Display, User-System Interaction, Process Control and Input Devices, Alarms, Analysis and Decision Aids, Inter-Personnel Communication, and Workplace Design (see O`Hara & Brown, 1993). The purpose of this paper is to describe the methodology for DRG use.
Knowledge management stakes: a marathon, sprint or decathlon
2003-01-01
Organizations competing in dynamic environments must be able to effectively marshal their resources to survive and thrive. The most important resource most organizations have is their specialist knowledge and intellectual assets that tell them how to produce, trade, grow and react to environmental variations. Many organizations have become aware of the knowledge management (KM) discipline and understand that effective knowledge management can help them thrive and grow. A key success factor for organizations that are not already consciously practicing knowledge management is to develop a KM strategy for guidance and against which they can measure their progress. It is within the framework for the KM strategy that we discuss the functions and roles of a KM audit, and review the insights gained from performing KM audits for two large organizations, one of a state level social services organization, and the other of a multidivisional engineering company. Contributor: Monash University. Faculty of Information Technology.; Knowledge Management Challenge (2003 : Melbourne, Australia) Format: application/pdf Other identifier: Sussman, J.; Hall, B.; Burstein, F. Knowledge management stakes: a marathon, sprint or decathlon. Presented at: Knowledge Management Challenge; 2003 Apr 3-4; Melbourne, Australia. p. 65-75.; monash:7351 Language: eng
HIPERPAV - guidance to avoid early-age cracking in concrete pavements
2000-07-01
Development and principal features of a user-friendly Windows-based computer program -- HIPERPAV -- which uses job-specific input in the areas of material selection and mix proportioning, pavement design, environmental conditions and construction procedures, is described. The program is designed to predict the tensile stress and tensile strength development in the pavement over the first 72 hours and the resultant possibility for early-age uncontrolled cracking. The paper also includes a description of the scope of the problems addressed, the areas that have been considered for inputs to the program, and the incorporation of the inputs into the guidelines through a series of models. By completing four simple input screens prior to construction, the engineer should be in a position to avoid problems with uncontrolled cracking during construction. Other factors, such as early-age loading and long-term performance will be dealt with by other modules which are currently under development. A worked example of how HIPERPAV is to be used is also included. 4 refs., 5 figs.
ADVANCES IN HFE METHODS AND THEIR IMPLICATIONS FOR REGULATORY REVIEWS.
There is renewed interest in the United States (U.S.) to construct new Generation III and III+ reactors within the next decade and Generation IV reactors in the future. Licensing by the U.S. Nuclear Regulatory Commission (NRC) is a significant consideration and these new plants may pose new challenges. One such challenge is the advances in human factors engineering (HFE) methods that are used. These methods are used to design and evaluate the HFE aspects of a plant, such as the human-system interface (HSI). These methods are important because NRC HFE reviews are design process oriented, thus, the criteria are mostly technology neutral with regard to reactor design.[1] However, the HFE review criteria are not neutral with respect to the HFE methods that are used as part of the design process This will be important for new reactor reviews because the diversity of reactor types, HSIs, and operational concepts will increase, especially for Generation III+ and IV plants. Thus the NRC is conducting research to identify advances in HFE methods and to develop additional guidance to address their review.
ADVANCES IN HFE METHODS AND THEIR IMPLICATIONS FOR REGULATORY REVIEWS.
2006-03-21
There is renewed interest in the United States (U.S.) to construct new Generation III and III+ reactors within the next decade and Generation IV reactors in the future. Licensing by the U.S. Nuclear Regulatory Commission (NRC) is a significant consideration and these new plants may pose new challenges. One such challenge is the advances in human factors engineering (HFE) methods that are used. These methods are used to design and evaluate the HFE aspects of a plant, such as the human-system interface (HSI). These methods are important because NRC HFE reviews are design process oriented, thus, the criteria are mostly technology neutral with regard to reactor design.[1] However, the HFE review criteria are not neutral with respect to the HFE methods that are used as part of the design process This will be important for new reactor reviews because the diversity of reactor types, HSIs, and operational concepts will increase, especially for Generation III+ and IV plants. Thus the NRC is conducting research to identify advances in HFE methods and to develop additional guidance to address their review.
Human factors engineering program review model
The staff of the Nuclear Regulatory Commission is performing nuclear power plant design certification reviews based on a design process plan that describes the human factors engineering (HFE) program elements that are necessary and sufficient to develop an acceptable detailed design specification and an acceptable implemented design. There are two principal reasons for this approach. First, the initial design certification applications submitted for staff review did not include detailed design information. Second, since human performance literature and industry experiences have shown that many significant human factors issues arise early in the design process, review of the design process activities and results is important to the evaluation of an overall design. However, current regulations and guidance documents do not address the criteria for design process review. Therefore, the HFE Program Review Model (HFE PRM) was developed as a basis for performing design certification reviews that include design process evaluations as well as review of the final design. A central tenet of the HFE PRM is that the HFE aspects of the plant should be developed, designed, and evaluated on the basis of a structured top-down system analysis using accepted HFE principles. The HFE PRM consists of ten component elements. Each element in divided into four sections: Background, Objective, Applicant Submittals, and Review Criteria. This report describes the development of the HFE PRM and gives a detailed description of each HFE review element.
Human factors engineering program review model
1994-07-01
The staff of the Nuclear Regulatory Commission is performing nuclear power plant design certification reviews based on a design process plan that describes the human factors engineering (HFE) program elements that are necessary and sufficient to develop an acceptable detailed design specification and an acceptable implemented design. There are two principal reasons for this approach. First, the initial design certification applications submitted for staff review did not include detailed design information. Second, since human performance literature and industry experiences have shown that many significant human factors issues arise early in the design process, review of the design process activities and results is important to the evaluation of an overall design. However, current regulations and guidance documents do not address the criteria for design process review. Therefore, the HFE Program Review Model (HFE PRM) was developed as a basis for performing design certification reviews that include design process evaluations as well as review of the final design. A central tenet of the HFE PRM is that the HFE aspects of the plant should be developed, designed, and evaluated on the basis of a structured top-down system analysis using accepted HFE principles. The HFE PRM consists of ten component elements. Each element in divided into four sections: Background, Objective, Applicant Submittals, and Review Criteria. This report describes the development of the HFE PRM and gives a detailed description of each HFE review element.
R-Cadherin Is a Pax6-Regulated, Growth-Promoting Cue for Pioneer Axons
2003-10-29
The transcription factor Pax6 has been implicated in two processes that may be related in brain development: establishment of regional cell adhesion properties and axon guidance. In Pax6 mutant...Full Text Available
PROPOSED SUITE OF MODELS FOR ESTIMATING DOSE RESULTING FROM EXPOSURES BY THE DERMAL ROUTE
Recent risk assessment guidance emphasizes consideration of mechanistic factors for influencing disposition of a toxicant. To incorporate mechanistic information into risk assessment, a suite of models is proposed for use in characterizing and quantifying dosimetry of toxic age...
NASA NDE WORKING GROUP NEWSLETTER - NASA - Home
Headquarters interface for NI>E. Based 011 his guidance and the ... weld repairs to longitudinal and circumferential shell plate butt welds on .... measured by stress-wave-factor (SW}i), was sensitive to matrix cracking and the damage ...
Guideline for bolted joint design and analysis : version 1.0.
This document provides general guidance for the design and analysis of bolted joint connections. An overview of the current methods used to analyze bolted joint connections is given. Several methods for the design and analysis of bolted joint connections are presented. Guidance is provided for general bolted joint design, computation of preload uncertainty and preload loss, and the calculation of the bolted joint factor of safety. Axial loads, shear loads, thermal loads, and thread tear out are used in factor of safety calculations. Additionally, limited guidance is provided for fatigue considerations. An overview of an associated Mathcad{copyright} Worksheet containing all bolted joint design formulae presented is also provided.
Guideline for bolted joint design and analysis : version 1.0.
This document provides general guidance for the design and analysis of bolted joint connections. An overview of the current methods used to analyze bolted joint connections is given. Several methods for the design and analysis of bolted joint connections are presented. Guidance is provided for general bolted joint design, computation of preload uncertainty and preload loss, and the calculation of the bolted joint factor of safety. Axial loads, shear loads, thermal loads, and thread tear out are used in factor of safety calculations. Additionally, limited guidance is provided for fatigue considerations. An overview of an associated Mathcad{copyright} Worksheet containing all bolted joint design formulae presented is also provided.
Guideline for bolted joint design and analysis : version 1.0.
2008-01-01
This document provides general guidance for the design and analysis of bolted joint connections. An overview of the current methods used to analyze bolted joint connections is given. Several methods for the design and analysis of bolted joint connections are presented. Guidance is provided for general bolted joint design, computation of preload uncertainty and preload loss, and the calculation of the bolted joint factor of safety. Axial loads, shear loads, thermal loads, and thread tear out are used in factor of safety calculations. Additionally, limited guidance is provided for fatigue considerations. An overview of an associated Mathcad{copyright} Worksheet containing all bolted joint design formulae presented is also provided.
Evaluating the environmental consequences of contaminant bioaccumulation resulting from dredged material disposal is a complex technical and regulatory problem. This problem is exacerbated by the high cost of bioaccumulation testing and the lack of explicit guidance on how bioaccumulation data should be interpreted and used within a regulatory program. Bioaccumulation is a measurable phenomenon, rather than an effect. Without specific information about biological effects (e.g., reduced survival, growth, reproduction in animals, cancer risk in humans) resulting from bioaccumulation, it is difficult if not impossible from a regulatory standpoint to objectively determine what level of bioaccumulation constitutes an `unacceptable adverse effect.` Existing regulatory guidance attempts to overcome this with two approaches, both of which use low aquatic trophic level organisms and a reference-based comparison. In the first approach, the level of bioaccumulation of a specific contaminant is compared with a numerical effect limit, such as a Food and Drug Administration action level or a fish advisory. If the level of the contaminant in the organism exceeds the numerical limit, it is equated to an unacceptable adverse effect. If it does not, or there is no numerical limit, the second approach involves a comparison with animals exposed to a reference sediment. If bioaccumulation in the animals exposed to the dredged material exceeds that of animals exposed to the reference, a number of subjective factors are then evaluated to determine whether or not dredged material disposal will result in an `unacceptable adverse effect` (U.S. Environmental Protection Agency (USEPA)/U.S. Army Corps of Engineers (USACE) 1991, 1994).
1996-07-01
Evaluating the environmental consequences of contaminant bioaccumulation resulting from dredged material disposal is a complex technical and regulatory problem. This problem is exacerbated by the high cost of bioaccumulation testing and the lack of explicit guidance on how bioaccumulation data should be interpreted and used within a regulatory program. Bioaccumulation is a measurable phenomenon, rather than an effect. Without specific information about biological effects (e.g., reduced survival, growth, reproduction in animals, cancer risk in humans) resulting from bioaccumulation, it is difficult if not impossible from a regulatory standpoint to objectively determine what level of bioaccumulation constitutes an `unacceptable adverse effect.` Existing regulatory guidance attempts to overcome this with two approaches, both of which use low aquatic trophic level organisms and a reference-based comparison. In the first approach, the level of bioaccumulation of a specific contaminant is compared with a numerical effect limit, such as a Food and Drug Administration action level or a fish advisory. If the level of the contaminant in the organism exceeds the numerical limit, it is equated to an unacceptable adverse effect. If it does not, or there is no numerical limit, the second approach involves a comparison with animals exposed to a reference sediment. If bioaccumulation in the animals exposed to the dredged material exceeds that of animals exposed to the reference, a number of subjective factors are then evaluated to determine whether or not dredged material disposal will result in an `unacceptable adverse effect` (U.S. Environmental Protection Agency (USEPA)/U.S. Army Corps of Engineers (USACE) 1991, 1994).
2006-01-01
This guide explained the requirements for Off-Road Compression Ignition Engine Emission Regulations established under the Canadian Environmental Protection Act. The regulations are enforced by Environment Canada, which authorizes and monitors the use of the national emissions mark. The regulations prescribe standards for off-road engines that operate as reciprocating, internal combustion engines, other than those that operate under characteristics similar to the Otto combustion cycle and that use a spark plug or other sparking device. The regulations apply to engines that are typically diesel-fuelled and found in construction, mining, farming and forestry machines such as tractors, excavators and log skidders. Four different types of persons are potentially affected by the regulations: Canadian engine manufacturers. Distributors of Canadian engines or ...
Use of home grown wood poles for overhead line supports. Engineering Recommendation L. 41
1987-01-01
This engineering recommendation gives guidance on the use of a preferred range of home-grown wood pole sizes. The range of pole sizes is based upon the results given in ACE Report No. 97 and the experience of a number of Area Board users. The recommended range of home-grown wood poles is included in Table 1 of the document.
Update of Manual on Use of Rock in Hydraulic Engineering
2008-01-11
SummaryW5A(03)08 Rock in River and Coastal Engineering Update of Design ManualObjectivesTo update through extensive collaboration with industry in the UK and overseas the internationally recognised CIRIA / CUR Manual in order to deliver good practice guidance on the use of rock and armour stone for erosion and flood control on coasts and rivers. Environment Agency Copyright and or/ database right 2008. All rights reserved.
Systems engineering product description report for the Hanford Cleanup Mission: First issue
This document describes the upper level physical and administrative (nonphysical) products that, when delivered, complete the Hanford Cleanup Mission. Development of product descriptions is a continuation of the Sitewide Systems Engineering work described in the Sitewide functional analysis, the architecture synthesis, and is consistent with guidance contained in the mission plan. This document provides a bridge between all three documents and the products required to complete the mission of cleaning up the Hanford Site.
Systems engineering product description report for the Hanford Cleanup Mission: First issue
1994-06-01
This document describes the upper level physical and administrative (nonphysical) products that, when delivered, complete the Hanford Cleanup Mission. Development of product descriptions is a continuation of the Sitewide Systems Engineering work described in the Sitewide functional analysis, the architecture synthesis, and is consistent with guidance contained in the mission plan. This document provides a bridge between all three documents and the products required to complete the mission of cleaning up the Hanford Site.
Site Characterization Plan (SCP) conceptual design criteria document
This SCP Conceptual Design Criteria Document was developed to guide engineering effort for Engineering Study No. 10, the supporting document for Chapter 6 of the SCP. The document provides regulatory design guidance, design rationale derived from the Generic Requirements for a Mined Geological Disposal System document, site-specific criteria, and design assumptions. Appendices were added to provide additional information on geology and seals design. 24 figs., 15 tabs.
Site Characterization Plan (SCP) conceptual design criteria document
1986-05-19
This SCP Conceptual Design Criteria Document was developed to guide engineering effort for Engineering Study No. 10, the supporting document for Chapter 6 of the SCP. The document provides regulatory design guidance, design rationale derived from the Generic Requirements for a Mined Geological Disposal System document, site-specific criteria, and design assumptions. Appendices were added to provide additional information on geology and seals design. 24 figs., 15 tabs.
SCP (Site Characterization Plan) conceptual design criteria document
This SCP Conceptual Design Criteria Document was developed to guide engineering efforts for Engineering Study No. 10, the supporting document for Chapter 6 of the SCP. The document provides regulatory design guidance, design rationale derived from the Generic Requirements for a Mined Geological Disposal System document, site-specific criteria, and design assumptions. Appendices were added to provide additional information on geology and seals design.
SCP (Site Characterization Plan) conceptual design criteria document
1985-05-01
This SCP Conceptual Design Criteria Document was developed to guide engineering efforts for Engineering Study No. 10, the supporting document for Chapter 6 of the SCP. The document provides regulatory design guidance, design rationale derived from the Generic Requirements for a Mined Geological Disposal System document, site-specific criteria, and design assumptions. Appendices were added to provide additional information on geology and seals design.
Remedial design/remedial action strategy report
1994-06-30
This draft Regulatory Compliance Strategy (RCS) report will aid the ER program in developing and implementing Remedial Design/Remedial Action (RD/RA) projects. The intent of the RCS is to provide guidance for the implementation of project management requirements and to allow the implementation of a flexible, graded approach to design requirements depending on the complexity, magnitude, schedule, risk, and cost for any project. The RCS provides a functional management-level guidance document for the identification, classification, and implementation of the managerial and regulatory aspects of an ER project. The RCS has been written from the perspective of the ER Design Manager and provides guidance for the overall management of design processes and elements. The RCS does not address the project engineering or specification level of detail. Topics such as project initiation, funding, or construction are presented only in the context in which these items are important as sources of information or necessary process elements that relate to the design project phases.
2010-01-01
This study investigated the effects of synthetic vision system (SVS) concepts and advanced flight controls on the performance of pilots flying a light, single-engine general-aviation airplane. We evaluated the effects and interactions of 2 levels of terrain portrayal, guidance symbology, and flight control response type on pilot performance during the conduct of a relatively complex instrument approach procedure. The terrain and guidance presentations were evaluated as elements of an integrated primary flight display system. The approach procedure used in the study included a steeply descending, curved segment as might be encountered in emerging, required-navigation-performance-based procedures. Pilot performance measures consisted of flight technical performance, perceived workload, perce...
1996-05-01
A new draft document provides guidance for assessing and mitigating the effects of lightning hazards on a Department of Energy (or any other) facility. Written by two Lawrence Livermore Engineers, the document combines lightning hazard identification and facility categorization with a new concept, the Lightning Safety System, to help dispel the confusion and mystery surrounding lightning and its effects. The guidance is of particular interest to DOE facilities storing and handling nuclear and high-explosive materials. The concepts presented in the document were used to evaluate the lightning protection systems of the Device Assembly Facility at the Nevada Test Site.
Development of a guidance method for power system restoration
1989-08-01
This paper proposes a guidance method for the restorative control problem. It gives operators an appropriate restoration plan and restorative procedures by using the knowledge base of expertise and heuristics on power system operations. An approach that combines the knowledge engineering technology with conventional programming has been adopted. This architecture gives various kinds of flexibility. It is possible to modify the restoration plan automatically if unexpected occurrences such as new faults happen and to accept operator's changes to the proposed plan. A prototype has been developed to verify these functions.
A new main control-board system
1992-01-01
The corporation has developed a new main control-board that incorporates an operator guidance system for the next generation of nuclear power plants. The design objectives were to improve plant operation reliability operator workload and incidence of human error. Features include a compact operation console employing CRTs and a knowledge-engineering based operator-guidance system. The system was evaluated and passed testing by nuclear powerplant operators. The article introduces sytem features, validation methods and test results. (author)
IEEE guide for the application of human factors engineering
1987-01-01
This presentation discusses the need for an industry standard for applying human factors engineering (HFE) to nuclear power plants, the development of a draft Institute of Electrical and Electronics Engineers (IEEE) standard project, a summary of the content of the draft standard, and its status in the consensus process.
IEEE guide for the application of human factors engineering
1987-01-01
This presentation discusses the need for an industry standard for applying human factors engineering (HFE) to nuclear power plants, the development of a draft Institute of Electrical and Electronics Engineers (IEEE) standard project, a summary of the content of the draft standard, and its status in the consensus process
Remedial design and remedial action guidance for the Idaho National Engineering Laboratory
The US Department of Energy, Idaho Operations Office (DOE-ID), the US Environmental Protection Agency, Region X (EPA), and the Idaho Department of Health and Welfare (IDHW) have developed this guidance on the remedial design and remedial action (RD/RA) process. This guidance is applicable to activities conducted under the Idaho National Engineering Laboratory (INEL) Federal Facility Agreement and Consent Order (FFA/CO) and Action Plan. The INEL FFA/CO and Action Plan provides the framework for performing environmental restoration according to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). The guidance is intended for use by the DOE-ID, the EPA, and the IDHW Waste Area Group (WAG) managers and others involved in the planning and implementation of CERCLA environmental restoration activities. The scope of the guidance includes the RD/RA strategy for INEL environmental restoration projects and the approach to development and review of RD/RA documentation. Chapter 2 discusses the general process, roles and responsibilities, and other elements that define the RD/RA strategy. Chapters 3 through 7 describe the RD/RA documents identified in the FFA/CO and Action Plan. Chapter 8 provides examples of how this guidance can be applied to restoration projects. Appendices are included that provide excerpts from the FFA/CO pertinent to RD/RA (Appendix A), a applicable US Department of Energy (DOE) orders (Appendix B), and an EPA Engineering ``Data Gaps in Remedial Design`` (Appendix C).
Remedial design and remedial action guidance for the Idaho National Engineering Laboratory
1993-10-01
The US Department of Energy, Idaho Operations Office (DOE-ID), the US Environmental Protection Agency, Region X (EPA), and the Idaho Department of Health and Welfare (IDHW) have developed this guidance on the remedial design and remedial action (RD/RA) process. This guidance is applicable to activities conducted under the Idaho National Engineering Laboratory (INEL) Federal Facility Agreement and Consent Order (FFA/CO) and Action Plan. The INEL FFA/CO and Action Plan provides the framework for performing environmental restoration according to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). The guidance is intended for use by the DOE-ID, the EPA, and the IDHW Waste Area Group (WAG) managers and others involved in the planning and implementation of CERCLA environmental restoration activities. The scope of the guidance includes the RD/RA strategy for INEL environmental restoration projects and the approach to development and review of RD/RA documentation. Chapter 2 discusses the general process, roles and responsibilities, and other elements that define the RD/RA strategy. Chapters 3 through 7 describe the RD/RA documents identified in the FFA/CO and Action Plan. Chapter 8 provides examples of how this guidance can be applied to restoration projects. Appendices are included that provide excerpts from the FFA/CO pertinent to RD/RA (Appendix A), a applicable US Department of Energy (DOE) orders (Appendix B), and an EPA Engineering ``Data Gaps in Remedial Design`` (Appendix C).
1993-03-01
The paper studies problems on commercialization of Stirling engine heat pumps (SEHP) and the solution. The stirling engine is a small and fixed engine having a 30-40% thermal efficiency and a 1-100 kW output. It is a closed recipro type external combustion engine with non-condensable gas like helium as working fluid. Its theoretical efficiency agrees with that of the Carnot`s cycle. This is because the Stirling engine is often called a dream engine. However, the Stirling engine is legally restricted from a viewpoint of ensuring safety because high pressure gas as working fluid is sealed into the Stirling engine. It is feared that this point will be a condition that restricts spread/promotion of the equipment which uses the engine. Therefore, by guidance of MITI and support of organizations/enterprises concerned, a committee was started in 1992FY and has been studying safety of the Stirling engine and the related legal systems. 10 refs., 45 figs., 11 tabs.
Applied Research Staff: Susan Krebs-Smith
Susan Krebs-Smith, PhD, is the Chief of the Risk Factor Monitoring and Methods Branch of the Applied Research Program. In that capacity, she oversees a program of research on the surveillance of risk factors related to cancer, methodological issues to improve the assessment of those factors, and issues related to guidance and food policy.
A study on the quantification of organizational factors in periodic safety review
2001-05-01
Recently IAEA has issued a safety guidance entitled 'Periodic Safety Review (PSR)' to assess the safety of operating nuclear power plants. Based on this guideline, the PSR execution procedures have been developed in Korea. In this paper, the quantification methodology of organizational factors in PSR is suggested. It might contribute to assessing the organizational factor, which is an item of PSR, quantitatively at Kori unit 1.
Search for alternative automotive power sources
1973-02-15
A brief technology assessment is given of alternative propulsion systems for automobiles. Reciprocating and rotary (Wankel) spark ignition engines, diesel engines, gas turbines, Rankine cycle engines, and electric propulsion are discussed. Various research programs are reviewed with respect to engine design factors and emission control. (PMA)
Factors Affecting the Starting Characteristics of Gas-Turbine Engines
This report summarizes the effects of fuel volatility and engine design variables on the problem of starting gas-turbine engines at sea-level and altitude conditions. The starting operation for engines ...
16 CFR 1000.29 - Directorate for Engineering Sciences.
...broad array of engineering disciplines including chemical, electrical, fire protection, human factors, and mechanical engineering. It conducts and coordinates engineering research, testing, and evaluation activities with other...
Archive Collection of the Society of Women Engineers
"The SWE story is the history of the first society dedicated to the advancement of women in engineering - capturing pioneering experiences and celebrating groundbreaking accomplishments. SWE preserves its historical heritage through collections that document the national organization's origins, activities, and members. These collections reflect our main focuses on career guidance, using conferences, scholarships, awards and other programs to encourage women to enter or return to the engineering profession and to attain high levels of educational and professional achievement; publicizing the role of women in engineering, placing them in engineering jobs and promoting them in industry and professional circles; serving as a center of information on women in engineering; and allying itself with other organizations to promote equal opportunities and equal rights for women." The archive contains interviews, oral histories, publications, conference records and a photographic collection.
Full Text Available.BackgroundThe Chief Medical Officer for England has developed the first guidance in England and some of the first internationally on alcohol consumption by children. Using the most recent iteration of a large biennial survey of schoolchildren we measure the extent to which young people's drinking fell within the guidelines just prior to their introduction and the characteristics of individuals whose drinking does not; how alcohol related harms relate to compliance; and risk factors associated with behaving outside of the guidance.MethodsA cross-sectional survey was conducted utilising a self-completed questionnaire with closed questions. A total of 11,879 schoolchildren, aged 15-16 years, from secondary schools in North West England participated in the study. Data were analysed using chi square and conditional logistic regression.ResultsAlcohol consumption is an established norm by age 15 years (81.3%). Acute alcohol related violence, regretted sex and forgetfulness were experienced by significantly fewer children drinking within the guidance (than outside of it). Over half of drinkers (54.7%) reported routinely drinking more heavily than guidance suggests (here ≥5 drinks/session ≥1 month), or typically drinking unsupervised at home or at a friend's home when parents were absent (57.4%). Both behaviours were common across all deprivation strata. Children with greater expendable incomes were less likely to consume within guidance and reported higher measures for unsupervised, frequent and heavy drinking. Although drinking due to peer pressure was associated with some measures of unsupervised drinking, those reporting that they drank out of boredom were more likely to report risk-related drinking behaviours outside of the guidance.ConclusionsSuccessful implementation of guidance on alcohol consumption for children could result in substantial reductions in existing levels of alcohol related harms to young people. However, prolonged social marketing, educational and parental interventions will be required to challenge established social norms in heavy and unsupervised child drinking across all social strata. Policy measures to establish a minimum price for alcohol and provide children with entertaining alternatives to alcohol should also increase compliance with guidance.
Assessment of rope joints when changing winding ropes on engine sheaves
1980-06-01
When winding ropes on engine sheaves are changed with the aid of a friction winch, the old rope which is to be discarded has to be joined to the new rope by a load-bearing join. In the last few years, some of the possible connecting techniques have been examined from the point of view of their suitability for this rope changing duty. As compared with earlier published material which detailed the joins and offered practical guidance, the present paper looks at the different types of joints and analyses and compares them in terms of their suitability for rope changes on engine winding plant.
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