WorldWideScience

Sample records for revised safety instruction

  1. Revised Safety Instruction 41 (IS41 REV.)

    CERN Multimedia

    SC Secretariat

    2005-01-01

    Please note that the Revised Safety Instruction No. 41 (IS41 REV.), entitled 'The use of plastic and other non-metallic materials at CERN with respect to fire safety and radiation resistance' is available on the web at the following url: https://edms.cern.ch/document/335806/LAST_RELEASED Paper copies can also be obtained from the SC Unit Secretariat, e-mail: sc.secretariat@cern.ch SC Secretariat

  2. A prioritization of generic safety issues. Supplement 19, Revision insertion instructions

    International Nuclear Information System (INIS)

    1995-11-01

    The report presents the safety priority ranking for generic safety issues related to nuclear power plants. The purpose of these rankings is to assist in the timely and efficient allocation of NRC resources for the resolution of those safety issues that have a significant potential for reducing risk. The safety priority rankings are HIGH, MEDIUM, LOW, and DROP, and have been assigned on the basis of risk significance estimates, the ratio of risk to costs and other impacts estimated to result if resolution of the safety issues were implemented, and the consideration of uncertainties and other quantitative or qualitative factors. To the extent practical, estimates are quantitative. This document provides revisions and amendments to the report

  3. A prioritization of generic safety issues. Supplement 19, Revision insertion instructions

    Energy Technology Data Exchange (ETDEWEB)

    None

    1995-11-01

    The report presents the safety priority ranking for generic safety issues related to nuclear power plants. The purpose of these rankings is to assist in the timely and efficient allocation of NRC resources for the resolution of those safety issues that have a significant potential for reducing risk. The safety priority rankings are HIGH, MEDIUM, LOW, and DROP, and have been assigned on the basis of risk significance estimates, the ratio of risk to costs and other impacts estimated to result if resolution of the safety issues were implemented, and the consideration of uncertainties and other quantitative or qualitative factors. To the extent practical, estimates are quantitative. This document provides revisions and amendments to the report.

  4. A prioritization of generic safety issues. Supplement 21, Revision insertion instructions

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    1996-12-31

    The report presents the safety priority ranking for generic safety issues related to nuclear power plants. The purpose of these rankings is to assist in the timely and efficient allocation of NRC resources for the resolution of those safety issues that have a significant potential for reducing risk. The safety priority rankings are HIGH, MEDIUM, LOW, and DROP, and have been assigned on the basis of risk significance estimates, the ratio of risk to costs and other impacts estimated to result if resolution of the safety issues were implemented, and the consideration of uncertainties and other quantitative or qualitative factors. To the extent practical, estimates are quantitative.

  5. A prioritization of generic safety issues. Supplement 21, Revision insertion instructions

    International Nuclear Information System (INIS)

    1996-01-01

    The report presents the safety priority ranking for generic safety issues related to nuclear power plants. The purpose of these rankings is to assist in the timely and efficient allocation of NRC resources for the resolution of those safety issues that have a significant potential for reducing risk. The safety priority rankings are HIGH, MEDIUM, LOW, and DROP, and have been assigned on the basis of risk significance estimates, the ratio of risk to costs and other impacts estimated to result if resolution of the safety issues were implemented, and the consideration of uncertainties and other quantitative or qualitative factors. To the extent practical, estimates are quantitative.

  6. SAFETY INSTRUCTION AND SAFETY NOTE

    CERN Multimedia

    TIS Secretariat

    2002-01-01

    Please note that the SAFETY INSTRUCTION N0 49 (IS 49) and the SAFETY NOTE N0 28 (NS 28) entitled respectively 'AVOIDING CHEMICAL POLLUTION OF WATER' and 'CERN EXHIBITIONS - FIRE PRECAUTIONS' are available on the web at the following urls: http://edms.cern.ch/document/335814 and http://edms.cern.ch/document/335861 Paper copies can also be obtained from the TIS Divisional Secretariat, email: TIS.Secretariat@cern.ch

  7. New Directions in Reading Instruction--Revised.

    Science.gov (United States)

    Hinson, Bess, Ed.

    The gains in knowledge about the nature of reading and how to most effectively teach it come from cognitive research. This booklet (in the form of a flipchart) synthesizes and summarizes much of the current research on effective instruction for improved literacy and greater student achievement. The booklet, a revised edition of "New…

  8. Revised GCFR safety program plan

    International Nuclear Information System (INIS)

    Kelley, A.P.; Boyack, B.E.; Torri, A.

    1980-05-01

    This paper presents a summary of the recently revised gas-cooled fast breeder reactor (GCFR) safety program plan. The activities under this plan are organized to support six lines of protection (LOPs) for protection of the public from postulated GCFR accidents. Each LOP provides an independent, sequential, quantifiable risk barrier between the public and the radiological hazards associated with postulated GCFR accidents. To implement a quantitative risk-based approach in identifying the important technology requirements for each LOP, frequency and consequence-limiting goals are allocated to each. To ensure that all necessary tasks are covered to achieve these goals, the program plan is broken into a work breakdown structure (WBS). Finally, the means by which the plan is being implemented are discussed

  9. Safety Education in Driving. 2nd Revision.

    Science.gov (United States)

    Ohio State Univ., Columbus. Vocational Instructional Materials Lab.

    Intended for driving instruction students, this publication contains instructional materials for safety education. It contains six sections on facts and figures; defensive driving; safety devices; restraints; emergency situations; and other highway users. Each section consists of reading material followed by an activity or activities. A total of…

  10. Delivering Instruction to Adult Learners. Revised Edition.

    Science.gov (United States)

    Cantor, Jeffrey A.

    This one-stop guide for trainers and educators of adults in industry, business, or the professions details a results-oriented instructional strategy that is based on the following principles for instructing adults effectively: (1) act as a leader, helper, guide, change agent, coordinator, and facilitator of learning; (2) promote active…

  11. Nuclear safety guide. TID-7016, Revision 2

    International Nuclear Information System (INIS)

    Thomas, J.T.

    1978-01-01

    The Nuclear Safety Guide was first issued in 1956 as classified AEC report LA-2063 and was reprinted the next year, unclassified, as TID-7016. Revision 1, published in 1961, extended the scope and refined the guiding information. The present revision of the Guide differs significantly from its predecessor in that the latter was intentionally conservative in its recommendations. Firmly based on experimental evidence of criticality, the original Guide and the first revision were considered to be of most value to organizations whose activities with fissionable materials were not extensive and, secondarily, that it would serve as a point of departure for members of established nuclear safety teams, experienced in the field. The reader will find a significant change in the character of information presented in this version. Nuclear Criticality Safety has matured in the past twelve years. The advance of calculational capability has permitted validated calculations to extend and substitute for experimental data. The broadened data base has enabled better interpolation, extension, and understanding of available information, especially in areas previously addressed by undefined but adequate factors of safety. The content has been thereby enriched in qualitative guidance. The information inherently contains, and the user can recapture, the quantitative guidance characteristic of the formerGuides by employing appropriate safety factors. In fact, it becomes incumbent on the Criticality Safety Specialist to necessarily impose safety factors consistent with the possible normal and abnormal credible contingencies of an operation as revealed by his evaluation. In its present form the Guide easily becomes a suitable module in any compendium or handbook tailored for internal use by organizations. It is hoped the Guide will continue to serve immediate needs and will encourage continuing and more comprehensive efforts toward organizing nuclear criticality safety information

  12. Nuclear safety guide. TID-7016, Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Thomas, J T [ed.

    1978-05-01

    The Nuclear Safety Guide was first issued in 1956 as classified AEC report LA-2063 and was reprinted the next year, unclassified, as TID-7016. Revision 1, published in 1961, extended the scope and refined the guiding information. The present revision of the Guide differs significantly from its predecessor in that the latter was intentionally conservative in its recommendations. Firmly based on experimental evidence of criticality, the original Guide and the first revision were considered to be of most value to organizations whose activities with fissionable materials were not extensive and, secondarily, that it would serve as a point of departure for members of established nuclear safety teams, experienced in the field. The reader will find a significant change in the character of information presented in this version. Nuclear Criticality Safety has matured in the past twelve years. The advance of calculational capability has permitted validated calculations to extend and substitute for experimental data. The broadened data base has enabled better interpolation, extension, and understanding of available information, especially in areas previously addressed by undefined but adequate factors of safety. The content has been thereby enriched in qualitative guidance. The information inherently contains, and the user can recapture, the quantitative guidance characteristic of the formerGuides by employing appropriate safety factors. In fact, it becomes incumbent on the Criticality Safety Specialist to necessarily impose safety factors consistent with the possible normal and abnormal credible contingencies of an operation as revealed by his evaluation. In its present form the Guide easily becomes a suitable module in any compendium or handbook tailored for internal use by organizations. It is hoped the Guide will continue to serve immediate needs and will encourage continuing and more comprehensive efforts toward organizing nuclear criticality safety information.

  13. Nuclear safety guide: TID--7016, Revision 2

    International Nuclear Information System (INIS)

    Thomas, J.T.

    1978-01-01

    The Nuclear Safety Guide was first issued in 1956 as classified AEC report LA-2063 and was reprinted the next year, unclassified, as TID-7016. Revision 1, published in 1961, extended the scope and refined the guiding information. Revision 2 of the Guide differs significantly from its predecessor in that the latter was intentionally conservative in its recommendations. Firmly based on experimental evidence of criticality, the original Guide and the first revision were considered to be of most value to organizations whose activities with fissionable materials were not extensive and, secondarily, that it would serve as a point of departure for members of established nuclear safety teams experienced in the field. The advance of calculational capability has permitted validated calculations to extend and substitute for experimental data. The broadened data base has enabled better interpolation, extension, and understanding of available information, especially in areas previously addressed by undefined but adequate factors of safety. The content has been thereby enriched in qualitative guidance. The information inherently contains, and the user can recapture, the quantitative guidance characteristic of the former Guides by employing appropriate safety factors

  14. Human Factors and Safety Culture in Maritime Safety (revised

    Directory of Open Access Journals (Sweden)

    Heinz Peter Berg

    2013-09-01

    Full Text Available As in every industry at risk, the human and organizational factors constitute the main stakes for maritime safety. Furthermore, several events at sea have been used to develop appropriate risk models. The investigation on maritime accidents is, nowadays, a very important tool to identify the problems related to human factor and can support accident prevention and the improvement of maritime safety. Part of this investigation should in future also be near misses. Operation of ships is full of regulations, instructions and guidelines also addressing human factors and safety culture to enhance safety. However, even though the roots of a safety culture have been established, there are still serious barriers to the breakthrough of the safety management. One of the most common deficiencies in the case of maritime transport is the respective monitoring and documentation usually lacking of adequacy and excellence. Nonetheless, the maritime area can be exemplified from other industries where activities are ongoing to foster and enhance safety culture.

  15. Nuclear safety guide TID-7016 Revision 2

    International Nuclear Information System (INIS)

    Thomas, J.T.

    1980-01-01

    The present revision of TID-7016 Nuclear Safety Guide is discussed. This Guide differs significantly from its predecessor in that the latter was intentionally conservative in its recommendations. Firmly based on experimental evidence of criticality, the original Guide and the first revision were considered to be of most value to organizations whose activities with fissionable materials were not extensive and, secondarily, that it would serve as a point of departure for members of established nuclear safety teams, experienced in the field. The reader will find a significant change in the character of information presented in this version. Nuclear Criticality Safety has matured in the past twelve years. The advance of calculational capability has permitted validated calculations to extend and substitute for experimental data. The broadened data base has enabled better interpolation, extension, and understanding of available, information, especially in areas previously addressed by undefined but adequate factors of safety. The content has been thereby enriched in qualitative guidance. The information inherently contains, and the user can recapture, the quantitative guidance characteristic of the former Guides by employing appropriate safety factors. In fact, it becomes incumbent on the Criticality Safety Specialist to necessarily impose safety factors consistent with the possible normal and abnormal credible contingencies of an operation as revealed by his evaluation. In its present form the Guide easily becomes a suitable module in any compendium or handbook tailored for internal use by organizations. It is hoped the Guide will continue to serve immediate needs and will encourage continuing and more comprehensive efforts toward organizing nuclear criticality safety information

  16. Preliminary Study on the Revision of Nuclear Safety Policy Statement

    International Nuclear Information System (INIS)

    Lee, Y. E.; Lee, S. H.; Chang, H. S.; Choi, K. S.; Jung, S. J.

    2011-01-01

    Nuclear safety policy in Korea is currently declared in the Nuclear Safety Charter as the highest tier document and safety principles and directions are announced in the Nuclear Safety Policy Statement. As the circumstances affecting on the nuclear safety policy change, it needs to revise the Statement. This study aims to develop the revised Nuclear Safety Policy Statement to declare that securing safety is a prerequisite to the utilization of nuclear energy, and that all workers in nuclear industry and regulatory body must adhere to the principle of priority to safety. As a result, two different types of revision are being prepared as of August. One is based on the spirit of Nuclear Safety Charter as well as the direction of future-oriented safety policies including the changes in the environment after declaration of the Statement. The other is to declare the fundamental safety objective and safety principles as the top philosophy of national nuclear safety policy by adopting the '10 Safety Principles in IAEA Safety Fundamental' instead of the current Charter. Both versions of revision are subject to further in-depth discussion. However once the revision is finalized and declared, it would be useful to accomplish effectively the organizational responsibilities and to enhance the public confidence in nuclear safety by performing the regulatory activities in a planned and systematic manner and promulgating the government's dedication to priority to safety

  17. Revised health and safety compliance model for the Ghanaian ...

    African Journals Online (AJOL)

    The construction industry in Ghana is faced with employees' negligence in obeying rules and regulations, and acts that conflict with health and safety. The purpose of the paper was to present the revised health and safety (H&S) compliance model for the construction industry based on a developed theoretical six factor ...

  18. Tank safety screening data quality objective. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Hunt, J.W.

    1995-04-27

    The Tank Safety Screening Data Quality Objective (DQO) will be used to classify 149 single shell tanks and 28 double shell tanks containing high-level radioactive waste into safety categories for safety issues dealing with the presence of ferrocyanide, organics, flammable gases, and criticality. Decision rules used to classify a tank as ``safe`` or ``not safe`` are presented. Primary and secondary decision variables used for safety status classification are discussed. The number and type of samples required are presented. A tabular identification of each analyte to be measured to support the safety classification, the analytical method to be used, the type of sample, the decision threshold for each analyte that would, if violated, place the tank on the safety issue watch list, and the assumed (desired) analytical uncertainty are provided. This is a living document that should be evaluated for updates on a semiannual basis. Evaluation areas consist of: identification of tanks that have been added or deleted from the specific safety issue watch lists, changes in primary and secondary decision variables, changes in decision rules used for the safety status classification, and changes in analytical requirements. This document directly supports all safety issue specific DQOs and additional characterization DQO efforts associated with pretreatment and retrieval. Additionally, information obtained during implementation can assist in resolving assumptions for revised safety strategies, and in addition, obtaining information which will support the determination of error tolerances, confidence levels, and optimization schemes for later revised safety strategy documentation.

  19. Perspectives on reactor safety. Revision 1

    International Nuclear Information System (INIS)

    Haskin, F.E.; Hodge, S.A.

    1997-11-01

    The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor safety concepts. The course consists of five modules: (1) the development of safety concepts; (2) severe accident perspectives; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course

  20. Perspectives on reactor safety. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Haskin, F.E. [New Mexico Univ., Albuquerque, NM (United States). Dept. of Chemical and Nuclear Engineering; Camp, A.L. [Sandia National Labs., Albuquerque, NM (United States); Hodge, S.A. [Oak Ridge National Lab., TN (United States). Engineering Technology Div.

    1997-11-01

    The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor safety concepts. The course consists of five modules: (1) the development of safety concepts; (2) severe accident perspectives; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course.

  1. The Instructional Guide for Abbott Skills Enhancement Classes. Revised Edition.

    Science.gov (United States)

    Ballinger, Ronda; Gee, Mary Kay

    This guide, which integrates adult basic education (ABE) curriculum, job skills for Abbott Laboratories, and work-related foundation skills, is designed for an instructional program in the skill areas of reading, writing, oral communications, mathematics, and problem solving. In addition to creating a uniform process and product to promote…

  2. Instructional games and activities for criticality safety training

    International Nuclear Information System (INIS)

    Bullard, B.; McBride, J.

    1993-01-01

    During the past several years, the Training and Management Systems Division (TMSD) staff of Oak Ridge Institute for Science and Education (ORISE) has designed and developed nuclear criticality safety (NCS) training programs that focus on high trainee involvement through the use of instructional games and activities. This paper discusses the instructional game, initial considerations for developing games, advantages and limitations of games, and how games may be used in developing and implementing NCS training. It also provides examples of the various instructional games and activities used in separate courses designed for Martin Marietta Energy Systems (MMES's) supervisors and U.S. Nuclear Regulatory Commission (NRC) fuel facility inspectors

  3. Revising the IDEA Student Ratings of Instruction System 2002-2011 Data. IDEA Technical Report No. 18

    Science.gov (United States)

    Benton, Stephen L.; Li, Dan; Brown, Ron; Guo, Meixi; Sullivan, Patricia

    2015-01-01

    This report describes the processes undertaken to revise the IDEA Student Ratings of Instruction (SRI) system. The previous revision occurred in 1999, as described in IDEA Technical Report No. 11, "Revising the IDEA System for Obtaining Student Ratings of Instructors and Courses" (Hoyt, Chen, Pallett, & Gross, 1999). The procedures…

  4. DOE explosives safety manual. Revision 7

    Energy Technology Data Exchange (ETDEWEB)

    1994-08-01

    This manual prescribes the Department of Energy (DOE) safety rules used to implement the DOE safety policy for operations involving explosives. This manual is applicable to all DOE facilities engaged in operations of development, manufacturing, handling, storage, transportation, processing, or testing of explosives, pyrotechnics and propellants, or assemblies containing these materials. The standards of this manual deal with the operations involving explosives, pyrotechnics and propellants, and the safe management of such operations. The design of all new explosives facilities shall conform to the requirements established in this manual and implemented in DOE 6430.1A, ``General Design Criteria Manual.`` It is not intended that existing physical facilities be changed arbitrarily to comply with these provisions, except as required by law. Existing facilities that do not comply with these standards may continue to be used for the balance of their functional life, as long as the current operation presents no significantly greater risk than that assumed when the facility was originally designed and it can be demonstrated clearly that a modification to bring the facility into compliance is not feasible. However, in the case of a major renovation, the facility must be brought into compliance with current standards. The standards are presented as either mandatory or advisory. Mandatory standards, denoted by the words ``shall,`` ``must,`` or ``will,`` are requirements that must be followed unless written authority for deviation is granted as an exemption by the DOE. Advisory standards denoted by ``should`` or ``may`` are standards that may be deviated from with a waiver granted by facility management.

  5. Classroom instruction versus roadside training in traffic safety education

    NARCIS (Netherlands)

    van Schagen, I; Rothengatter, J.A.

    1997-01-01

    This study compares the effectiveness of different approaches to training complex cognitive and psychomotor skills within the framework of road safety education for primary school children. A method involving roadside behavioral training, a classroom instruction method and a method combining these

  6. 78 FR 34703 - Pipeline Safety: Information Collection Activities, Revision to Gas Distribution Annual Report

    Science.gov (United States)

    2013-06-10

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2013-0004] Pipeline Safety: Information Collection Activities, Revision to Gas Distribution Annual Report AGENCY: Pipeline and Hazardous Materials Safety Administration, DOT. ACTION: Notice and request...

  7. Teaching Critical Questions about Argumentation through the Revising Process: Effects of Strategy Instruction on College Students' Argumentative Essays

    Science.gov (United States)

    Song, Yi; Ferretti, Ralph P.

    2013-01-01

    The effects of self-regulated strategy development revising instruction for college students that targeted the use of argumentation schemes and critical questions were assessed in three conditions. In the first condition, students were taught to revise their essays by asking and answering critical questions about the "argument from consequences"…

  8. Instructions for preparation of data entry sheets for Licensee Event Report (LER) file. Revision 1. Instruction manual

    International Nuclear Information System (INIS)

    1977-07-01

    The manual provides instructions for the preparation of data entry sheets for the licensee event report (LER) file. It is a revision to an interim manual published in October 1974 in 00E-SS-001. The LER file is a computer-based data bank of information using the data entry sheets as input. These data entry sheets contain pertinent information in regard to those occurrences required to be reported to the NRC. The computer-based data bank provides a centralized source of data that may be used for qualitative assessment of the nature and extent of off-normal events in the nuclear industry and as an index of source information to which users may refer for more detail

  9. 77 FR 22387 - Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering...

    Science.gov (United States)

    2012-04-13

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2012-0024] Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering Pipeline Systems Annual Report, Gas Transmission and Gathering Pipeline Systems Incident Report...

  10. 77 FR 58616 - Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering...

    Science.gov (United States)

    2012-09-21

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2012-0024] Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering Pipeline Systems Annual Report, Gas Transmission and Gathering Pipeline Systems Incident Report...

  11. Safety assessment for the 118-B-1 Burial Ground excavation treatability tests. Revision 2

    International Nuclear Information System (INIS)

    Zimmer, J.J.; Frain, J.M.

    1994-12-01

    This revision of the Safety Assessment provides an auditable safety analysis of the hazards for the proposed treatability test activities per DOE-EM-STD-5502-94, DOE Limited Standard, Hazard Baseline Documentation (DOE 1994). The proposed activities are classified as radiological activities and as such, no longer require Operational Safety Limits (OSLs). The OSLS, Prudent Actions, and Institutional and Organization Controls have been removed from this revision and replaced with ''Administrative Actions Important to Safety,'' as determined by the hazards analysis. Those Administrative Actions Important to Safety are summarized in Section 1.1, ''Assessment Summary.''

  12. 30 CFR 77.1708 - Safety program; instruction of persons employed at the mine.

    Science.gov (United States)

    2010-07-01

    ... at the mine. 77.1708 Section 77.1708 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH MANDATORY SAFETY STANDARDS, SURFACE COAL MINES AND SURFACE WORK AREAS OF UNDERGROUND COAL MINES Miscellaneous § 77.1708 Safety program; instruction of persons...

  13. 78 FR 73692 - Revisions to Safety Standards for Infant Bath Seats, Toddler Beds, and Full-Size Baby Cribs

    Science.gov (United States)

    2013-12-09

    ... standard issued under the Danny Keysar Child Product Safety Notification Act was based, the revision... standard. Section 26(c) of the CPSA also provides that states or political subdivisions of states may apply... CONSUMER PRODUCT SAFETY COMMISSION 16 CFR Parts 1215, 1217 and 1219 Revisions to Safety Standards...

  14. Authentic Learning Experiences for Educators through Summer Internships: Revising the DIG Texas Instructional Blueprints

    Science.gov (United States)

    Martinez, A. O.; Bohls-Graham, E.; Jacobs, B. E.; Ellins, K. K.

    2014-12-01

    Texas teachers have expressed a need for engaging activities for use in high school Earth science courses. With funding from the NSF, geoscience and education faculty from different institutions around the state collaborated with ten Earth science teachers to create five online Earth science instructional blueprints. The work is part of the DIG (Diversity and Innovation for Geosciences) Texas Instructional Blueprint project. A blueprint stitches together nine units for a yearlong Earth science course (scope and sequence). Each unit covers three weeks of teaching and contains lectures, readings, visualizations, lab investigations, learning activities, and other educational materials from credible sources, which are aligned with Texas state science standards for Earth and Space Science and the Earth Science Literacy Principles. Taken together, the collection of activities address the Next Generation Science Standards (NGSS). During summer 2014, three minority-serving secondary teachers completed a six-week internship at The University of Texas Institute for Geophysics (UTIG). As DIG Texas Education Interns, we organized and revised the content of the units, created scaffolding notes, and built blueprints by selecting groups of nine units from the project's current collection of twenty-one units. Because fieldwork is an important element of geoscience learning, we integrated virtual field trips into each unit. We (1) gained expertise in selecting high quality activities that directly correlate with state standards and address the Earth Science Literacy Principles; (2) developed a keen awareness of the value of the NGSS; (3) learned how to navigate through the NGSS website to track the relationships between the Science and Engineering Practices, Disciplinary Core Ideas, and Crosscutting Concepts for Earth science, as well as connections to other disciplines in the same grade level. Collaborating with other secondary Earth science teachers introduced each of us to new

  15. Safety analysis report for the Waste Storage Facility. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Bengston, S.J.

    1994-05-01

    This safety analysis report outlines the safety concerns associated with the Waste Storage Facility located in the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The three main objectives of the report are: define and document a safety basis for the Waste Storage Facility activities; demonstrate how the activities will be carried out to adequately protect the workers, public, and environment; and provide a basis for review and acceptance of the identified risk that the managers, operators, and owners will assume.

  16. Revision of AESJ standard 'the code of implemnetation of periodic safety review of nuclear power plants'

    International Nuclear Information System (INIS)

    Hirano, Masashi; Narumiya, Yoshiyuki

    2010-01-01

    The Periodic Safety Review (PSR) was launched in June 1992, when the Agency for Natural Resources and Energy issued a notification that required licensees to conduct comprehensive review on the safety of each existing nuclear power plant (NPP) once approximately every ten years based on the latest technical findings for the purpose of improving the safety of the NPP. In 2006, the Standard Committee of the Atomic Energy Society of Japan established the first version of 'The Standard of Implementation for Periodic Safety Review of Nuclear Power Plants: 2006'. Taking into account developments in safety regulation of PSR after the issuance of the first version, the Standard Committee has revised the Standard. This paper summarizes background on PSR, such developments are major contents of the Standard as well as the focal points of the revision. (author)

  17. 75 FR 38432 - Railroad Safety Appliance Standards, Miscellaneous Revisions

    Science.gov (United States)

    2010-07-02

    ...: Stephen J. Carullo, Railroad Safety Specialist, Office of Safety, FRA, 1200 New Jersey Avenue, SE..., Office of Chief Counsel, FRA, 1200 New Jersey Avenue, SE., Mail Stop 10, Washington, DC 20590 (telephone... government (FRA and Transport Canada participate as non-voting members), as well as ergonomics experts. The...

  18. Revised

    DEFF Research Database (Denmark)

    Johannsen, Vivian Kvist; Nord-Larsen, Thomas; Riis-Nielsen, Torben

    This report is a revised analysis of the Danish data on CO2 emissions from forest, afforestation and deforestation for the period 1990 - 2008 and a prognosis for the period until 2020. Revision have included measurements from 2009 in the estimations. The report is funded by the Ministry of Climate...

  19. Tank farm health and safety plan. Revision 2

    International Nuclear Information System (INIS)

    Mickle, G.D.

    1995-01-01

    This Tank Farm Health and Safety Plan (HASP) for the conduct of all operations and work activities at the Hanford Site 200 Area Tank Farms is provided in order to minimize health and safety risks to workers and other onsite personnel. The HASP accomplishes this objective by establishing requirements, providing general guidelines, and conveying farm and facility-specific hazard communication information. The HASP, in conjunction with the job-specific information required by the HASP, is provided also as a reference for use during the planning of work activities at the tank farms. This HASP applies to Westinghouse Hanford Company (WHC), other prime contractors to the U.S. Department of Energy (DOE), and subcontractors to WHC who may be involved in tank farm work activities. This plan is intended to be both a requirements document and a useful reference to aid tank farm workers in understanding the safety and health issues that are encountered in routine and nonroutine work activities. The HASP defines the health and safety responsibilities of personnel working at the tank farms. It has been prepared in recognition of and is consistent with National Institute of Safety and Health (NIOSH), and Occupational Safety and Health Administration (OSHA)/Unlimited State Coast Guard (USCG)/U.S. Environmental Protection Agency (EPA), Occupational Safety and Health Guidance Manual for Hazardous Waste Site Activities (NIOSH 1985); WHC-CM-4-3, Industrial Safety Manual, Volume 4, open-quotes Health and Safety Programs for Hazardous Waste Operations;close quotes 29 CFR 1910.120, Hazardous Waste Operations and Emergency Response; WHC-CM-1-1, Management Policies; and WHC-CM-1-3, Management Requirements and Procedures. When differences in governing regulations or policies exist, the more stringent requirements shall apply until the discrepancy can be resolved

  20. Tank farm health and safety plan. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Mickle, G.D.

    1995-03-29

    This Tank Farm Health and Safety Plan (HASP) for the conduct of all operations and work activities at the Hanford Site 200 Area Tank Farms is provided in order to minimize health and safety risks to workers and other onsite personnel. The HASP accomplishes this objective by establishing requirements, providing general guidelines, and conveying farm and facility-specific hazard communication information. The HASP, in conjunction with the job-specific information required by the HASP, is provided also as a reference for use during the planning of work activities at the tank farms. This HASP applies to Westinghouse Hanford Company (WHC), other prime contractors to the U.S. Department of Energy (DOE), and subcontractors to WHC who may be involved in tank farm work activities. This plan is intended to be both a requirements document and a useful reference to aid tank farm workers in understanding the safety and health issues that are encountered in routine and nonroutine work activities. The HASP defines the health and safety responsibilities of personnel working at the tank farms. It has been prepared in recognition of and is consistent with National Institute of Safety and Health (NIOSH), and Occupational Safety and Health Administration (OSHA)/Unlimited State Coast Guard (USCG)/U.S. Environmental Protection Agency (EPA), Occupational Safety and Health Guidance Manual for Hazardous Waste Site Activities (NIOSH 1985); WHC-CM-4-3, Industrial Safety Manual, Volume 4, {open_quotes}Health and Safety Programs for Hazardous Waste Operations;{close_quotes} 29 CFR 1910.120, Hazardous Waste Operations and Emergency Response; WHC-CM-1-1, Management Policies; and WHC-CM-1-3, Management Requirements and Procedures. When differences in governing regulations or policies exist, the more stringent requirements shall apply until the discrepancy can be resolved.

  1. Nuclear Criticality Safety Organization qualification program. Revision 4

    International Nuclear Information System (INIS)

    Carroll, K.J.; Taylor, R.G.; Worley, C.A.

    1997-01-01

    The Nuclear Criticality Safety Organization (NCSO) is committed to developing and maintaining a staff of highly qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. This document defines the Qualification Program to address the NCSO technical and managerial qualification as required by the Y-12 Training Implementation Matrix (TIM). It is implemented through a combination of LMES plant-wide training courses and professional nuclear criticality safety training provided within the organization. This Qualification Program is applicable to technical and managerial NCSO personnel, including temporary personnel, sub-contractors and/or LMES employees on loan to the NCSO, who perform the NCS tasks or serve NCS-related positions as defined in sections 5 and 6 of this program

  2. Nuclear Criticality Safety Organization training implementation. Revision 4

    Energy Technology Data Exchange (ETDEWEB)

    Carroll, K.J.; Taylor, R.G.; Worley, C.A.

    1997-05-19

    The Nuclear Criticality Safety Organization (NCSO) is committed to developing and maintaining a staff of qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. This document provides a listing of the roles and responsibilities of NCSO personnel with respect to training and details of the Training Management System (TMS) programs, Mentoring Checklists and Checksheets, as well as other documentation utilized to implement the program. This Training Implementation document is applicable to all technical and managerial NCSO personnel, including temporary personnel, sub-contractors and/or LMES employees on loan to the NCSO, who are in a qualification program.

  3. Nuclear Criticality Safety Organization training implementation. Revision 4

    International Nuclear Information System (INIS)

    Carroll, K.J.; Taylor, R.G.; Worley, C.A.

    1997-01-01

    The Nuclear Criticality Safety Organization (NCSO) is committed to developing and maintaining a staff of qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. This document provides a listing of the roles and responsibilities of NCSO personnel with respect to training and details of the Training Management System (TMS) programs, Mentoring Checklists and Checksheets, as well as other documentation utilized to implement the program. This Training Implementation document is applicable to all technical and managerial NCSO personnel, including temporary personnel, sub-contractors and/or LMES employees on loan to the NCSO, who are in a qualification program

  4. Using a safety net and following the safety instructions could prevent half the paediatric trampoline injuries.

    Science.gov (United States)

    Rättyä, J; Serlo, W

    2008-08-01

    The number of recreational trampolines in Finnish households has increased. There also appears to be a drastic increase in trampoline-related injuries among paediatric patients. The aim of this study was to quantify and describe trampoline-related injuries in North Finnish paediatric patients. A retrospective analysis of medical data was used in the study, covering children 16 years and younger treated for trampoline-related injuries at Oulu University Hospital over a five-month period of time from May 1 to September 30, 2005. Medical records were reviewed and additional details regarding the injuries were obtained by questionnaire. Altogether 76 patients were treated for trampoline-related injuries, which represented 13.4 % of all paediatric accidental trauma patients. In 57 accidents (86 %), there had been multiple jumpers on the trampoline. Twenty-five of the injuries (38 %) had occurred on the trampoline, in 25 cases (38 %) a child had fallen off, in 8 cases (12 %) there had been a collision with another jumper and the person had jumped onto a trampoline from a high platform in 5 incidents (8 %). Only 3 children (5 %) hurt themselves on the trampoline when jumping alone. Orthopaedic procedures requiring general anaesthesia were necessary in a total of 31 cases (41 %). The study shows that 50 % of traumas (falling off and collisions) could have been avoided by using a safety net and by jumping one at a time. The importance of following safety instructions and the need for a safety net should be emphasised to both the supervising adults and the children.

  5. Safety assessment of discharge chute isolation barrier preparation and installation activities. Revision 3

    International Nuclear Information System (INIS)

    Meichle, R.H.

    1994-01-01

    This revision adds a section addressing impacts of dropping surfacing tool and rack cutter on the basin floor, and corrects typographical errors. The safety assessment is made for the activities for the preparation and installation of the discharge chute isolation barriers. The safety assessment includes a hazard assessment and comparisons of potential accidents/events to those addressed by the current safety basis documentation. No significant hazards were identified. An evaluation against the USQ evaluation questions was made and the determination made that the activities do not represent a USQ. Hazard categorization techniques were used to provide a basis for readiness review classifications

  6. Idaho National Engineering Laboratory (INEL) Environmental Restoration Program (ERP), Baseline Safety Analysis File (BSAF). Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-20

    This document was prepared to take the place of a Safety Evaluation Report since the Baseline Safety Analysis File (BSAF)and associated Baseline Technical Safety Requirements (TSR) File do not meet the requirements of a complete safety analysis documentation. Its purpose is to present in summary form the background of how the BSAF and Baseline TSR originated and a description of the process by which it was produced and approved for use in the Environmental Restoration Program.The BSAF is a facility safety reference document for INEL environmental restoration activities including environmental remediation of inactive waste sites and decontamination and decommissioning (D&D) of surplus facilities. The BSAF contains safety bases common to environmental restoration activities and guidelines for performing and documenting safety analysis. The common safety bases can be incorporated by reference into the safety analysis documentation prepared for individual environmental restoration activities with justification and any necessary revisions. The safety analysis guidelines in BSAF provide an accepted method for hazard analysis; analysis of normal, abnormal, and accident conditions; human factors analysis; and derivation of TSRS. The BSAF safety bases and guidelines are graded for environmental restoration activities.

  7. Idaho National Engineering Laboratory (INEL) Environmental Restoration Program (ERP), Baseline Safety Analysis File (BSAF). Revision 1

    International Nuclear Information System (INIS)

    1994-01-01

    This document was prepared to take the place of a Safety Evaluation Report since the Baseline Safety Analysis File (BSAF)and associated Baseline Technical Safety Requirements (TSR) File do not meet the requirements of a complete safety analysis documentation. Its purpose is to present in summary form the background of how the BSAF and Baseline TSR originated and a description of the process by which it was produced and approved for use in the Environmental Restoration Program.The BSAF is a facility safety reference document for INEL environmental restoration activities including environmental remediation of inactive waste sites and decontamination and decommissioning (D ampersand D) of surplus facilities. The BSAF contains safety bases common to environmental restoration activities and guidelines for performing and documenting safety analysis. The common safety bases can be incorporated by reference into the safety analysis documentation prepared for individual environmental restoration activities with justification and any necessary revisions. The safety analysis guidelines in BSAF provide an accepted method for hazard analysis; analysis of normal, abnormal, and accident conditions; human factors analysis; and derivation of TSRS. The BSAF safety bases and guidelines are graded for environmental restoration activities

  8. Seismic safety margin research program. Program plan, Revision II

    International Nuclear Information System (INIS)

    Smith, P.D.; Tokarz, F.J.; Bernreuter, D.L.; Cummings, G.E.; Chou, C.K.; Vagliente, V.N.; Johnson, J.J.; Dong, R.G.

    1978-01-01

    The document has been prepared pursuant to the second meeting of the Senior Research Review Group of the Seismic Safety Margin Research Program (SSMRP), which was held on June 15, 16, 1978. The major portion of the material contained in the document is descriptions of specific subtasks to be performed on the SSMRP. This is preceded by a brief discussion of the objective of the SSMRP and the approach to be used. Specific subtasks to be performed in Phase I of the SSMRP are as follows: (1) plant/site selection, (2) seismic input, (3) soil structure interaction, (4) structural building response, (5) structural sub-system response, (6) fragility, (7) system analysis, and (8) Phase II task definition

  9. Seismic safety margin research program. Program plan, Revision I

    International Nuclear Information System (INIS)

    Smith, P.D.; Tokarz, F.J.; Bernreuter, D.L.; Cummings, G.E.; Chou, C.K.; Vagliente, V.N.

    1978-01-01

    The overall objective of the SSMRP is to develop mathematical models that realistically predict the probability of radioactive releases from seismically induced events in nuclear power plants. These models will be used for four purposes: (1) To perform sensitivity studies to determine the weak links in seismic methodology. The weak links will then be improved by research and development. (2) To estimate the probability of release for a plant. It is believed that the major difficulty in the program will be to obtain acceptably small confidence limits on the probability of release. (3) To estimate the conservatisms in the Standard Review Plan (SRP) seismic design methodology. This will be done by comparing the results of the SRP methodology and the methodology resulting from the research and development in (1). (4) To develop an improved seismic design methodology based on probability. The Phase I objective proposed in this report is to develop mathematical models which will accomplish the purposes No. 1 and No. 2 with simplified assumptions such as linear elastic analysis, limited assessment on component fragility (considering only accident sequences leading to core melt), and simplified safety system

  10. Safety basis for selected activities in single-shell tanks with flammable gas concerns. Revision 1

    International Nuclear Information System (INIS)

    Schlosser, R.L.

    1996-01-01

    This is full revision to Revision 0 of this report. The purpose of this report is to provide a summary of analyses done to support activities performed for single-shell tanks. These activities are encompassed by the flammable gas Unreviewed Safety Question (USQ). The basic controls required to perform these activities involve the identification, elimination and/or control of ignition sources and monitoring for flammable gases. Controls are implemented through the Interim Safety Basis (ISB), IOSRs, and OSDs. Since this report only provides a historical compendium of issues and activities, it is not to be used as a basis to perform USQ screenings and evaluations. Furthermore, these analyses and others in process will be used as the basis for developing the Flammable Gas Topical Report for the ISB Upgrade

  11. Efficacy of Web-Based Instruction to Provide Training on Federal Motor Carrier Safety Regulations

    Science.gov (United States)

    2011-05-01

    This report presents an evaluation of the current state-of-the-art Web-based instruction (WBI), reviews the current computer platforms of potential users of WBI, reviews the current status of WBI applications for Federal Motor Carrier Safety Administ...

  12. Vault Safety and Inventory System users manual, PRIME 2350. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Downey, N.J.

    1994-12-14

    This revision is issued to request review of the attached document: VSIS User Manual, PRIME 2350, which provides user information for the operation of the VSIS (Vault Safety and Inventory System). It describes operational aspects of Prime 2350 minicomputer and vault data acquisition equipment. It also describes the User`s Main Menu and menu functions, including REPORTS. Also, system procedures for the Prime 2350 minicomputer are covered.

  13. Vault Safety and Inventory System users manual, PRIME 2350. Revision 1

    International Nuclear Information System (INIS)

    Downey, N.J.

    1994-01-01

    This revision is issued to request review of the attached document: VSIS User Manual, PRIME 2350, which provides user information for the operation of the VSIS (Vault Safety and Inventory System). It describes operational aspects of Prime 2350 minicomputer and vault data acquisition equipment. It also describes the User's Main Menu and menu functions, including REPORTS. Also, system procedures for the Prime 2350 minicomputer are covered

  14. Safety instruction for execution tasks involving ionizing radiations

    International Nuclear Information System (INIS)

    Fonseca, G.

    1985-01-01

    Basic directives are presented allow operations with ionizing radiations in industrial areas with high levels of safety. Contractual, technical, operational and administrative criteria are established for the safe performance of x-rays and gamographies and the use of fixed radiation based equipment (indicators of level, density, flow, etc) as well as precautions to be taken during project, procurement, transportation, assembly and maintenance of such equipment. Finally procedures are suggested for emergencies involving radioactive sources. (author)

  15. Revised IAEA Code of Conduct on the Safety and Security of Radioactive Sources

    International Nuclear Information System (INIS)

    Wheatley, J. S.

    2004-01-01

    The revised Code of Conduct on the Safety and Security of Radioactive Sources is aimed primarily at Governments, with the objective of achieving and maintaining a high level of safety and security of radioactive sources through the development, harmonization and enforcement of national policies, laws and regulations; and through the fostering of international co-operation. It focuses on sealed radioactive sources and provides guidance on legislation, regulations and the regulatory body, and import/export controls. Nuclear materials (except for sources containing 239Pu), as defined in the Convention on the Physical Protection of Nuclear Materials, are not covered by the revised Code, nor are radioactive sources within military or defence programmes. An earlier version of the Code was published by IAEA in 2001. At that time, agreement was not reached on a number of issues, notably those relating to the creation of comprehensive national registries for radioactive sources, obligations of States exporting radioactive sources, and the possibility of unilateral declarations of support. The need to further consider these and other issues was highlighted by the events of 11th September 2001. Since then, the IAEA's Secretariat has been working closely with Member States and relevant International Organizations to achieve consensus. The text of the revised Code was finalized at a meeting of technical and legal experts in August 2003, and it was submitted to IAEA's Board of Governors for approval in September 2003, with a recommendation that the IAEA General Conference adopt it and encourage its wide implementation. The IAEA General Conference, in September 2003, endorsed the revised Code and urged States to work towards following the guidance contained within it. This paper summarizes the history behind the revised Code, its content and the outcome of the discussions within the IAEA Board of Governors and General Conference. (Author) 8 refs

  16. Your Credit Rights: An Instructional Unit on Consumer Credit Protection. Revised.

    Science.gov (United States)

    Jensen, Barbara J.; And Others

    This instructional guide adds two new sections to the original guide published in May 1982. The guide was designed to assist educators in teaching the topics of consumer credit and consumer credit protection to secondary and postsecondary students in various economics and business courses, as well as in adult and community education courses. The…

  17. Articulated, Performance-Based Instruction Objectives Guide for Automotive Mechanics. Final Document. Revised.

    Science.gov (United States)

    Henderson, William Edward, Jr.

    Developed during a project designed to provide continuous, performance-based vocational training at the secondary and postsecondary levels, this instructional guide is intended to help teachers implement a laterally and vertically articulated secondary level automotive mechanics program. Introductory materials include descriptions of Automotive…

  18. Revision of the Euratom basic safety standards directive-current status

    International Nuclear Information System (INIS)

    Mundig, S.

    2011-01-01

    The European Commission is currently developing a revised Euratom Basic Safety Standards (BSS) Directive covering two major objectives: the consolidation of existing Euratom Radiation Protection legislation and the revision of the Euratom BSS. The consolidation will merge the following five Directives into one single Directive: the BSS Directive, the Medical Exposures Directive, the Public Information Directive, the Outside Workers Directive and the Directive on the Control of high-activity sealed radioactive sources and orphan sources. The revision of the Euratom BSS will take account of the latest recommendations by the International Commission on Radiological Protection and shall improve clarity of the requirements where appropriate. It is planned to introduce more binding requirements on natural radiation sources, on criteria for exemption and clearance, and on the cooperation between Member States for emergency planning and response. The provisions for regulatory control of planned exposure situations foresee a graded approach commensurate to the magnitude and likelihood of exposures from a practice. Finally, the new BSS shall take account of recent scientific developments. One additional goal is to achieve greater harmonisation between the Euratom BSS and the international BSS. While the requirements on the protection of workers, apprentices and students remain nearly unchanged, the revised BSS will clarify the roles and responsibilities of services and experts involved in technical and practical aspects of radiation protection, such as the occupational health services, the dosimetry services, the radiation protection expert and the medical physics expert. The requirements in the BSS on individual monitoring of category A workers remain unchanged, but the existing guidance on individual monitoring was revised and updated-the technical recommendations for monitoring individuals occupationally exposed to external radiation are published by the European

  19. Site-specific waste management instruction for the 100-KR-4 Operable Unit drilling. Revision 1

    International Nuclear Information System (INIS)

    Hadley, J.T.

    1996-08-01

    This site-specific waste management instruction provides guidance for the management of waste generated as a result of groundwater well installations in the 100-KR-4 Operable Unit (OU). The well installations are necessary to implement the Remedial Action (RA) option (pump-and-treat using ion exchange) to prevent discharge of hexavalent chromium at levels above those considered protective of aquatic life in the Columbia River and riverbed sediments

  20. Education and training requirements in the revised European Basic Safety Standards Directive

    International Nuclear Information System (INIS)

    Mundigl, S.

    2009-01-01

    The European Commission is currently developing a modified European Basic Safety Standards Directive covering two major objectives: the consolidation of existing European Radiation Protection legislation, and the revision of the European Basic Safety Standards. The consolidation will merge the following five Directives into one single Directive: the Basic Safety Standards Directive, the Medical Exposures Directive, the Public Information Directive, the Outside Workers Directive, and the Directive on the Control of high-activity sealed radioactive sources and orphan sources. The revision of the European Basic Safety Standards will take account of the latest recommendations by the International Commission on Radiological Protection (ICRP) and shall improve clarity of the requirements where appropriate. It is planned to introduce more binding requirements on natural radiation sources, on criteria for clearance, and on the cooperation between Member States for emergency planning and response, as well as a graded approach for regulatory control. One additional goal is to achieve greater harmonisation between the European BSS and the international BSS. Following a recommendation from the Article 31 Group of Experts, the current draft of the modified BSS will highlight the importance of education and training by dedicating a specific title to radiation protection education, training and information. This title will include a general requirement on the Member States to ensure the establishment of an adequate legislative and administrative framework for providing appropriate radiation protection education, training and information. In addition, there will be specific requirements on training in the medical field, on information and training of workers in general, of workers potentially exposed to orphan sources, and to emergency workers. The revised BSS directive will include requirements on the competence of a radiation protection expert (RPE) and of a radiation protection

  1. Governmental, Legal and Regulatory Framework for Safety. General Safety Requirements. Part 1, Revision 1 (Chinese Edition)

    International Nuclear Information System (INIS)

    2016-01-01

    This publication establishes requirements in respect of the governmental, legal and regulatory framework for safety. It covers the essential aspects of the framework for establishing a regulatory body and taking other actions necessary to ensure the effective regulatory control of facilities and activities utilized for peaceful purposes. Other responsibilities and functions, such as liaison within the global safety regime and on support services for safety (including radiation protection), emergency preparedness and response, nuclear security, and the State system of accounting for and control of nuclear material, are also covered. A review of Safety Requirements publications was commenced in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan. The review revealed no significant areas of weakness and resulted in just a small set of amendments to strengthen the requirements and facilitate their implementation, which are contained in the present publication.

  2. Revised technical regulations on radiation protection and safety of 30 September 1975

    International Nuclear Information System (INIS)

    1975-01-01

    These revised technical regulations were made in implementation of Section 4 of Decree No 7/9038 of 30 November 1974 on radiation health and safety and lay down in detail the requirements to be met in Turkey for the use of all types of radiation sources. They set out protection plans and specify the protective equipment to be used as well as the controlled areas, i.e. areas in which radiation sources are used and which must be subject to special safety measures. Finally to obtain a license, users of radiation sources must fill in forms, the models of which are provided, giving their particulars and the specifications of the intended use and activity of the sources. (NEA) [fr

  3. The revision of the safety standards for protection against ionizing radiation

    International Nuclear Information System (INIS)

    Wei Li Chen; Hsiao Ping Wang; Chia Chun Liao; Chin Shiun Yeh

    1994-01-01

    The Chinese Safety Standards for Protection Against Ionizing Radiation was issued on July 29, 1970, and has been used for more than thirteen years. In 1983, the Atomic Energy Council (AEC) decided to revise it accordingly to the recommendations of the International Commission on Radiological Protection and the experiences of regulation enforcement in Taiwan and other countries. The AEC assembled a task group of eight members from academic institutions, licensees, government agency, and senior health physics to be in charge of the revision. In this presentation the major changes of the Safety Standards are summarized. They refer to the adoption of the system of dose limitation recommended by ICRP publication 26 and 30, the use of the units of the International System as the primary units with the old units being noted in parentheses, the adoption of the minimums levels recommended by the International Atomic Energy Agency and the setting up of an executive regulatory system for the implementation of the ALARA concept. 6 refs

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

    International Nuclear Information System (INIS)

    Batchelor, K.

    1996-03-01

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

  5. Performance and safety to NAVSEA instruction 9310.1A of lithium-thionyl chloride reserve batteries

    Science.gov (United States)

    Hall, J. C.

    1984-09-01

    The design, performance and safety of a fully engineered, selfcontained Li/SOCl2 battery as the power source for underwater applications. In addition to meeting the performance standards of the end user this battery is successfully tested under the rigorous safety conditions of NAVSEA Instruction 9310.1A for use on land, aircraft and surface ships.

  6. Safety analysis on Non-LOCA events for the revision of Wolsong NPP unit 2,3,4 sar

    International Nuclear Information System (INIS)

    Kim, Jong Hyun; Jin, Dong Sik; Ryu, Eui Seung; Kho, Dong Wook; Kim, Sung Min

    2015-01-01

    Korean Wolsong Nuclear Power Plant Units 2,3,4 (CANDU-6 Type) has prepared the revision of safety analysis report (Final Safety Analysis Report (FSAR) chapter 15) from the original performed in the year of 1990s, using the updated and state-of-the-art methodology and tools including IST safety analysis codes and more detail modelling. Compared with the original FSAR15, the revised FSAR15 has significant improvement in both the scope and the depth of safety analysis, which has demonstrated the safety analysis results have complied with the safety requirements(acceptance criteria). This paper will present the analysis scope for Non-LOCA events re-analyzed or added for the FSAR15 revision, methodologies applied such as codes and modelling and some important analysis results will be demonstrated with comparison to acceptance criteria. Application of more detail and near-realistic assumptions and method including Dev-PDO options and uncertainty related to the CHF correlations has altogether brought about more safety margin compared with the original FSAR15 with respect to SDS trip effectiveness etc. (author)

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

    International Nuclear Information System (INIS)

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

    1985-08-01

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

  8. Standard Review Plan for the review of safety analysis reports for nuclear power plants, Revision No. 7 to Section 9

    International Nuclear Information System (INIS)

    1978-03-01

    Revision No. 1 to Section 9 of the Standard Review Plan incorporates changes that have been developed since the original issuance in September 1975, many of which are editorial in nature, to reflect current staff practice in the review of safety analysis reports for nuclear power plants

  9. Food Safety Instruction Improves Knowledge and Behavior Risk and Protection Factors for Foodborne Illnesses in Pregnant Populations.

    Science.gov (United States)

    Kendall, Patricia; Scharff, Robert; Baker, Susan; LeJeune, Jeffrey; Sofos, John; Medeiros, Lydia

    2017-08-01

    Objective This study compared knowledge and food-handling behavior after pathogen-specific (experimental treatment) versus basic food safety instruction (active control) presented during nutrition education classes for low-income English- and Spanish-language pregnant women. Methods Subjects (n = 550) were randomly assigned to treatment groups in two different locations in the United States. Food safety instruction was part of an 8-lesson curriculum. Food safety knowledge and behavior were measured pre/post intervention. Descriptive data were analyzed by Chi-Square or ANOVA; changes after intervention were analyzed by regression analysis. Results Knowledge improved after intervention in the pathogen-specific treatment group compared to active control, especially among Spanish-language women. Behavior change after intervention for the pathogen-specific treatment group improved for thermometer usage, refrigeration and consumption of foods at high risk for safety; however, all other improvements in behavior were accounted for by intervention regardless of treatment group. As expected, higher pre-instruction behavioral competency limited potential gain in behavior post-instruction due to a ceiling effect. This effect was more dominant among English-language women. Improvements were also linked to formal education completed, a partner at home, and other children in the home. Conclusions for Practice This study demonstrated that pathogen-specific food safety instruction leads to enhance knowledge and food handling behaviors that may improve the public health of pregnant women and their unborn children, especially among Spanish-language women. More importantly, food safety instruction, even at the most basic level, benefited pregnant women's food safety knowledge and food-handling behavior after intervention.

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

    International Nuclear Information System (INIS)

    2013-01-01

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

  11. Safety warnings and first aid instructions on consumer and pharmaceutical products in Nigeria: has there been an improvement?

    Science.gov (United States)

    Nonyelum, Stanley Catherine; Nkem, Nwachukwu; Ifeyinwa, Chijoke-Nwauche; Orisakwe, Orish Ebere

    2010-10-01

    To investigate the adequacy of safety warnings and first aid instructions on the labels of pharmaceutical and consumer products in Nigeria. A market basket method (total collection of all available samples) was used to investigate the adequacy of safety warnings and first aid instructions on the labels of 600 pharmaceutical and consumer products in Nigeria. The results showed that 69.8% of the products had adequate warnings whereas 385 (64.1%) of the products screened had legible product warnings. Only 52 (8.7%) of the total number of products had appropriate first aid instructions while only 25 (4.12%) of the products described symptoms and full treatment of poisoning by the product and 319 (53.2%) products surveyed recommended calling a health professional. A total of 31 (5.2%) products had labels that were considered too technical (non English). Of the 600 products, 386 (64.3%) had dosage instructions that were considered adequate while 538 (89.6%) had adequate storage instructions. About 68% of the products had partially correct warnings while 44 or 7.3% had partially correct first aid instructions. Some products had neither warnings nor first aid instructions. This study suggests a not too impressive improvement in the correctness and appropriateness of label information.

  12. Containment Emergency Sump Performance. Technical findings related to Unresolved Safety Issue A-43. Revision 1

    International Nuclear Information System (INIS)

    1985-10-01

    This report summarizes key technical findings related to Unresolved Safety Issue (USI) A-43, Containment Emergency Sump Performance. Both BWRs and PWRs are considered in this report. Emergency core cooling systems require a clean, reliable water source to maintain long-term recirculation following a loss-of-coolant accident (LOCA). PWRs rely on the containment emergency sump to provide such a water supply to residual heat removal pumps and containment spray pumps. BWRs rely on pump suction intakes in the suppression pool or wet well to provide water to residual heat removal and core spray systems. Thus, the technical findings in this report provide information on post-LOCA recirculation. These findings have been derived from extensive experimental studies, generic plant studies, and assessments of sumps used for long-term cooling. Results of hydraulic tests have shown that the potential for air ingestion is less severe than previously hypothesized. The effects of debris blockage on NPSH margin must be dealt with on a plant-specific basis. These findings have been used to develop revisions to Regulatory Guide 1.82 and Standard Review Plan Section 6.2.2 (NUREG-0800)

  13. New Safety rules

    CERN Multimedia

    Safety Commission

    2008-01-01

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

  14. Review on the seismic safety of JRR-3 according to the revised regulatory code on seismic design for nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kobayashi, Tetsuya; Araki, Masaaki; Ohba, Toshinobu; Torii, Yoshiya [Japan Atomic Energy Agency, Tokai, Ibaraki (Japan); Takeuchi, Masaki [Nuclear Safety Commission (Japan)

    2012-03-15

    JRR-3(Japan Research Reactor No.3) with the thermal power of 20MW is a light water moderated and cooled, swimming pool type research reactor. JRR-3 has been operated without major troubles. This paper presents about review on the seismic safety of JRR-3 according to the revised regulatory code on seismic design for nuclear reactors. In addition, some topics concerning damages in JRR-3 due to the Great East Japan Earthquake are presented. (author)

  15. Assessment of CFD Codes for Nuclear Reactor Safety Problems - Revision 2

    International Nuclear Information System (INIS)

    Smith, B.L.; Andreani, M.; Bieder, U.; Ducros, F.; Bestion, D.; Graffard, E.; Heitsch, M.; Scheuerer, M.; Henriksson, M.; Hoehne, T.; Houkema, M.; Komen, E.; Mahaffy, J.; Menter, F.; Moretti, F.; Morii, T.; Muehlbauer, P.; Rohde, U.; Krepper, E.; Song, C.H.; Watanabe, T.; Zigh, G.; Boyd, C.F.; Archambeau, F.; Bellet, S.; Munoz-Cobo, J.M.; Simoneau, J.P.

    2015-01-01

    Following recommendations made at an 'Exploratory Meeting of Experts to Define an Action Plan on the Application of Computational Fluid Dynamics (CFD) Codes to Nuclear Reactor Safety (NRS) Problems', held in Aix-en-Provence, France, 15-16 May, 2002, and a follow-up meeting 'Use of Computational Fluid Dynamics (CFD) Codes for Safety Analysis of Reactor Systems including Containment', which took place in Pisa on 11-14 Nov., 2002, a CSNI action plan was drawn up which resulted in the creation of three Writing Groups, with mandates to perform the following tasks: (1) Provide a set of guidelines for the application of CFD to NRS problems; (2) Evaluate the existing CFD assessment bases, and identify gaps that need to be filled; (3) Summarise the extensions needed to CFD codes for application to two-phase NRS problems. Work began early in 2003. In the case of Writing Group 2 (WG2), a preliminary report was submitted to Working Group on the Analysis and Management of Accidents (WGAMA) in September 2004 that scoped the work needed to be carried out to fulfil its mandate, and made recommendations on how to achieve the objective. A similar procedure was followed by the other two groups, and in January 2005 all three groups were reformed to carry out their respective tasks. In the case of WG2, this resulted in the issue of a CSNI report (NEA/CSNI/R(2007)13), issued in January 2008, describing the work undertaken. The writing group met on average twice per year during the period March 2005 to May 2007, and coordinated activities strongly with the sister groups WG1 (Best Practice Guidelines) and WG3 (Multiphase Extensions). The resulting document prepared at the end of this time still represents the core of the present revised version, though updates have been made as new material has become available. After some introductory remarks, Chapter 3 lists twenty-three (23) NRS issues for which it is considered that the application of CFD would bring real benefits

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1999-12-01

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

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

    International Nuclear Information System (INIS)

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

    1999-12-01

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

  18. 78 FR 71033 - Pipeline Safety: Information Collection Activities, Revisions to Incident and Annual Reports for...

    Science.gov (United States)

    2013-11-27

    ... Reduction Act of 1995, PHMSA published a notice in the Federal Register of its intent to revise six forms... the failure of a piece of equipment is always due to a flaw in the equipment and never due to a...

  19. Alignment of Assessment Objectives with Instructional Objectives Using Revised Bloom's Taxonomy--The Case for Food Science and Technology Education

    Science.gov (United States)

    Jideani, V. A.; Jideani, I. A.

    2012-01-01

    Nine food science and technology (FST) subjects were assessed for alignment between the learning outcomes and assessment using revised Bloom's taxonomy (RBT) of cognitive knowledge. Conjoint analysis was used to estimate the utilities of the levels of cognitive, knowledge, and the attribute importance (cognitive process and knowledge dimension)…

  20. The Effects of Computer-Aided Instruction on Learning and Attitudes in Economic Principles Courses: Revised Results.

    Science.gov (United States)

    Henry, Mark

    1979-01-01

    Recounts statistical inaccuracies in an article on computer-aided instruction in economics courses on the college level. The article, published in the J. Econ. Ed (Fall 1978), erroneously placed one student in the TIPS group instead of the control group. Implications of this alteration are discussed. (DB)

  1. The "Kairotic" Moment: Pragmatic Revision of Basic Writing Instruction at Indiana University-Purdue University Fort Wayne

    Science.gov (United States)

    Webb-Sunderhaus, Sara; Amidon, Stevens

    2011-01-01

    This profile articulates the authors' response to a statewide mandate to eliminate "remedial" writing instruction at four-year public universities, including their own. The profile describes the difficulties the authors faced in responding to this initiative, given the context of their regional comprehensive university and its specific…

  2. Can "Withitness Skills" Improve Instruction and Safety for Those Who Coach or Train?

    Science.gov (United States)

    McDaniel, Larry W.

    2009-01-01

    "Withitness skills" developed by Kounin in the 1970's have been emphasized as an important classroom tool for student management and instruction. (Kounin, 1970) "Withit" instructors develop the ability to know what is going on in the classroom. Improving awareness in the classroom may reduce misbehavior and improve instruction.…

  3. 78 FR 38803 - Pipeline Safety: Information Collection Activities, Revisions to Incident and Annual Reports for...

    Science.gov (United States)

    2013-06-27

    ... Reports for Gas Pipeline Operators AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... (OMB) Control No. 2137-0522, titled ``Incident and Annual Reports for Gas Pipeline Operators.'' PHMSA...

  4. 75 FR 22678 - Pipeline Safety: Implementation of Electronic Filing for Recently Revised Incident/Accident...

    Science.gov (United States)

    2010-04-29

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... Liquid Systems AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Notice; Issuance of Advisory Bulletin. SUMMARY: This notice advises owners and operators of gas pipeline...

  5. A cascade method of training for the revised CEGB Radiological Safety Rules and the Ionising Radiations Regulations 1985

    International Nuclear Information System (INIS)

    Jackson, J.R.; John, P.G.L.

    1986-01-01

    In order to achieve compliance with the Ionising Radiations Regulations 1985 the CEGB has introduced a revised set of Radiological Safety Rule. These Rules are for implementation at all sites under the Board's control where ionising radiations are used. It was a requirement that the new Safety Rules be brought into operation on a common date and to a consistent standard of performance throughout the industry; this necessitated a considerable training programme to familiarise and inform some 8,000 staff working at a large number of locations. The training week of identified groups of staff varied widely, according to their different levels of authority and responsibility. The paper sets out the means by which the chosen cascade method of training was selected and developed, and gives details of the modular package of training material which was produced. It also relates how the management objectives were met within the constraints of an uncompromising time schedule. (author)

  6. Status report on resolution of Waste Tank Safety Issues at the Hanford Site. Revision 1

    International Nuclear Information System (INIS)

    Dukelow, G.T.; Hanson, G.A.

    1995-05-01

    The purpose of this report is to provide and update the status of activities supporting the resolution of waste tank safety issues and system deficiencies at the Hanford Site. This report provides: (1) background information on safety issues and system deficiencies; (2) a description of the Tank Waste Remediation System and the process for managing safety issues and system deficiencies; (3) changes in safety issue description, prioritization, and schedules; and (4) a summary of the status, plans, order of magnitude, cost, and schedule for resolving safety issues and system deficiencies

  7. Safety and effectiveness of a polyvinyl alcohol barrier in reducing risks of vascular tissue damage during anterior spinal revision surgery.

    Science.gov (United States)

    Jeffords, Paul; Li, Jinsheng; Panchal, Deepal; Denoziere, Guilhem; Fetterolf, Donald

    2012-05-01

    This study was conducted as a controlled, prospective investigation to show the safety and efficacy of a polyvinyl alcohol (PVA) device in a sheep model. To evaluate the ability of a permanent PVA hydrogel barrier to reduce the risk of potential vessel damage during anterior vertebral revision surgery, to provide a nonadhesive barrier at the surgical site, and to create a surgical revision plane of dissection. The development of scar tissue and adhesions presents a significant postoperative problem in spine surgery, where adhesion involvement of overlying structures can cause pain, neurovascular complications, and present a difficult surgical environment during revisions. The devices were implanted onto the ventral surface of exposed lumbar intervertebral discs using an anterolateral approach. One disc separated from the study site was also exposed to serve as a control. Three sheep each were then evaluated with an explant procedure at 30 and 90 days. Extensive sampling was undertaken to evaluate gross anatomic, micropathologic, and biochemical environments and properties of the device. The structural properties and appearance of the device remained intact at both 30 and 90 days. The material remained flexible, hydrophilic, and soft, without visible resorption or decomposition. The material was well tolerated by the animal, with minimal histologic signs of inflammation or rejection. Tissue planes were easily able to be localized by the surgeon attempting to locate the prior surgical site at the time of resection. The PVA vessel shield effectively protected the structures overlying the sheep spine during revision, providing a clear dissection plane for resection at repeat surgery. The overlying structures separated from the previous surgical site with no adhesion, and allowed safe separation of adjacent tissues without the use of sharp dissection.

  8. Microcomputers and the Improvement of Revision Skills.

    Science.gov (United States)

    Balajthy, Ernest; And Others

    1987-01-01

    Discusses use of word processing software as an effective tool in writing and revision instruction, and describes the role of the teacher. Examples of exercises that encourage revision and of software designed to teach effective revision skills are reviewed. (MBR)

  9. [Development and effect analysis of web-based instruction program to prevent elementary school students from safety accidents].

    Science.gov (United States)

    Chung, Eun-Soon; Jeong, Ihn-Sook; Song, Mi-Gyoung

    2004-06-01

    This study was aimed to develop a WBI(Web Based Instruction) program on safety for 3rd grade elementary school students and to test the effects of it. The WBI program was developed using Macromedia flash MX, Adobe Illustrator 10.0 and Adobe Photoshop 7.0. The web site was http://www.safeschool.co.kr. The effect of it was tested from Mar 24, to Apr 30, 2003. The subjects were 144 students enrolled in the 3rd grade of an elementary school in Gyungju. The experimental group received the WBI program lessons while each control group received textbook-based lessons with visual presenters and maps, 3 times. Data was analyzed with descriptive statistics, and chi2 test, t-test, and repeated measure ANOVA. First, the WBI group reported a longer effect on knowledge and practice of accident prevention than the textbook-based lessons, indicating that the WBI is more effective. Second, the WBI group was better motivated to learn the accident prevention lessons, showing that the WBI is effective. As a result, the WBI group had total longer effects on knowledge, practice and motivation of accident prevention than the textbook-based instruction. We recommend that this WBI program be used in each class to provide more effective safety instruction in elementary schools.

  10. Safety. Unit 8: A Core Curriculum of Related Instruction for Apprentices.

    Science.gov (United States)

    New York State Education Dept., Albany. Bureau of Occupational and Career Curriculum Development.

    The safety education unit is presented to assist apprentices to acquire a general knowledge of procedures for insuring safety on the job. The unit consists of 10 modules: (1) the Occupational Safety and Health Act: safety and health bill of rights for workers; (2) accident prevention; (3) first aid; (4) accident reports; importance, use, and how…

  11. Validation of nuclear criticality safety software and 27 energy group ENDF/B-IV cross sections. Revision 1

    International Nuclear Information System (INIS)

    Lee, B.L. Jr.; D'Aquila, D.M.

    1996-01-01

    The original validation report, POEF-T-3636, was documented in August 1994. The document was based on calculations that were executed during June through August 1992. The statistical analyses in Appendix C and Appendix D were completed in October 1993. This revision is written to clarify the margin of safety being used at Portsmouth for nuclear criticality safety calculations. This validation gives Portsmouth NCS personnel a basis for performing computerized KENO V.a calculations using the Lockheed Martin Nuclear Criticality Safety Software. The first portion of the document outlines basic information in regard to validation of NCSS using ENDF/B-IV 27-group cross sections on the IBM3090 at ORNL. A basic discussion of the NCSS system is provided, some discussion on the validation database and validation in general. Then follows a detailed description of the statistical analysis which was applied. The results of this validation indicate that the NCSS software may be used with confidence for criticality calculations at the Portsmouth Gaseous Diffusion Plant. For calculations of Portsmouth systems using the specified codes and systems covered by this validation, a maximum k eff including 2σ of 0.9605 or lower shall be considered as subcritical to ensure a calculational margin of safety of 0.02. The validation of NCSS on the IBM 3090 at ORNL was extended to include NCSS on the IBM 3090 at K-25

  12. Problems encountered in embodying the principles of ICRP-26 and the revised IAEA safety standards into UK national legislation

    International Nuclear Information System (INIS)

    Beaver, P.F.

    1979-01-01

    This paper describes the United Kingdom procedures and format for safety legislation and goes on to show how the necessary legislation for radiological protection will fit into the general framework. The United Kingdom, as a member of the European Community and EURATOM, is bound to implement the Euratom Directive on radiological protection within the next few years. The latest draft of the Directive takes account of the recommendations of ICRP-26 and further, a recent draft of the revised IAEA Basic Safety Standards is a composite of both the Directive and ICRP-26. Thus, the effect of embodying the principles of the Directive is to embody the principles of ICRP-26 and the Basic Safety Standards. Some of the problems which have been met are described and in particular there is discussion of the problems arising from the incorporation of the three ICRP-26 facets of dose control, namely justification, optimization and limitation, into a legislative package. The UK system of evolving safety legislation now requires considerable participation by all the parties affected (or by their representatives). This paper indicates that the involvement of persons affected, coupled with a legislative package which consists of a hierarchy of (a) regulations; (b) codes of practice; and (c) guidance notes, will result in the fundamental principles of ICRP-26 being incorporated into UK legislation in a totally acceptable way. (author)

  13. Safety Evaluation Report on Tennessee Valley Authority: Revised Corporate Nuclear Performance Plan

    International Nuclear Information System (INIS)

    1987-07-01

    The TVA Corporate Nuclear Performance Plan addresses those corporate concerns identified by the NRC staff. Because much of the TVA corporate plan is programmatic, its effectiveness depends on its implementation, and the NRC staff plans to closely monitor this implementation. The NRC staff will address site-specific concerns in subsequent SERs on each volume of the Nuclear Performance Plan. On the basis of its review, the NRC staff finds TVA's revised Corporate Nuclear Performance Plan (Revision 4) acceptable. The NRC staff concludes that the organization and staffing of TVA's Office of Nuclear Power and the programmatic improvements in place or under way are sufficient, if implemented properly, to resolve the problems at the corporate level that led to issuance of the 10 CFR 50.54(f) letter dated September 17, 1985, and to support continuing TVA nuclear activities, including plant operations. 19 refs., 3 figs

  14. Revision of the energy conservation requirements in the manufactured home construction and safety standards

    Energy Technology Data Exchange (ETDEWEB)

    Conner, C C; Lee, A D; Lucas, R G; Taylor, Z T

    1992-02-01

    Thermal requirements were developed for manufactured (mobile) homes in response to legislation requiring the US Department of Housing and Urban Development (HUD) to revise its thermal standards for manufactured homes. A life-cycle cost minimization from the home owner's perspecetive was used to establish an optimum in a large number of cities for several prototype homes. The development of the economic, financial, and energy conservation measure parameters input into the life-cycle cost analysis was documented. The optimization results were aggregated to zones which were expressed as a maximum overall home U-value (thermal transmittance) requirement. The revised standard's costs, benefits, and net value to the consumer were quantified. 50 refs.

  15. High-heat tank safety issue resolution program plan. Revision 2

    International Nuclear Information System (INIS)

    Wang, O.S.

    1994-12-01

    The purpose of this program plan is to provide a guide for selecting corrective actions that will mitigate and/or remediate the high-heat waste tank safety issue for single-shell tank 241-C-106. The heat source of approximately 110,000 Btu/hr is the radioactive decay of the stored waste material (primarily 90 Sr) inadvertently transferred into the tank in the later 1960s. Currently, forced ventilation, with added water to promote thermal conductivity and evaporation cooling, is used for heat removal. The method is very effective and economical. At this time, the only viable solution identified to permanently resolve this safety issue is the removal of heat-generating waste in the tank. This solution is being aggressively pursued as the only remediation method to this safety issue, and tank 241-C-106 has been selected as the first single-shell tank for retrieval. The current cooling method and other alternatives are addressed in this program as means to mitigate this safety issue before retrieval. This program plan has three parts. The first part establishes program objectives and defines safety issue, drivers, and resolution criteria and strategy. The second part evaluates the high-heat safety issue and its mitigation and remediation methods and other alternatives according to resolution logic. The third part identifies major tasks and alternatives for mitigation and resolution of the safety issue. A table of best-estimate schedules for the key tasks is also included in this program plan

  16. Site safety plan for Lawrence Livermore National Laboratory CERCLA investigations at site 300. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Kilmer, J.

    1997-08-01

    Various Department of Energy Orders incorporate by reference, health and safety regulations promulgated by the Occupational Safety and Health Administration (OSHA). One of the OSHA regulations, 29 CFR 1910.120, Hazardous Waste Operations and Emergency Response, requires that site safety plans are written for activities such as those covered by work plans for Site 300 environmental investigations. Based upon available data, this Site Safety Plan (Plan) for environmental restoration has been prepared specifically for the Lawrence Livermore National Laboratory Site 300, located approximately 15 miles east of Livermore, California. As additional facts, monitoring data, or analytical data on hazards are provided, this Plan may need to be modified. It is the responsibility of the Environmental Restoration Program and Division (ERD) Site Safety Officer (SSO), with the assistance of Hazards Control, to evaluate data which may impact health and safety during these activities and to modify the Plan as appropriate. This Plan is not `cast-in-concrete.` The SSO shall have the authority, with the concurrence of Hazards Control, to institute any change to maintain health and safety protection for workers at Site 300.

  17. Training and qualification program for nuclear criticality safety technical staff. Revision 1

    International Nuclear Information System (INIS)

    Taylor, R.G.; Worley, C.A.

    1997-01-01

    A training and qualification program for nuclear criticality safety technical staff personnel has been developed and implemented. All personnel who are to perform nuclear criticality safety technical work are required to participate in the program. The program includes both general nuclear criticality safety and plant specific knowledge components. Advantage can be taken of previous experience for that knowledge which is portable such as performance of computer calculations. Candidates step through a structured process which exposes them to basic background information, general plant information, and plant specific information which they need to safely and competently perform their jobs. Extensive documentation is generated to demonstrate that candidates have met the standards established for qualification

  18. Written instructions for the transport of hazardous materials: Accident management instruction sheets

    International Nuclear Information System (INIS)

    Ridder, K.

    1988-01-01

    In spite of the regulations and the safety provisions taken, accidents are not entirely avoidable in the transport of hazardous materials. For managing an accident and preventing further hazards after release of dangerous substances, the vehicle drivers must carry with them the accident management instruction sheets, which give instructions on immediate counter measures to be taken by the driver, and on information to be given to the police and the fire brigades. The article in hand discusses the purpose, the contents, and practice-based improvement of this collection of instruction sheets. Particular reference is given to the newly revised version of June 15, 1988 (Verkehrsblatt 1/88) of the 'Directives for setting up accident management instruction sheets - written instructions - for road transport of hazardous materials', as issued by the Federal Ministry of Transport. (orig./HP) [de

  19. Changes in safety climate and teamwork in the operating room after implementation of a revised WHO checklist: a prospective interventional study.

    Science.gov (United States)

    Erestam, Sofia; Haglind, Eva; Bock, David; Andersson, Annette Erichsen; Angenete, Eva

    2017-01-01

    Inter-professional teamwork in the operating room is important for patient safety. The World Health Organization (WHO) checklist was introduced to improve intraoperative teamwork. The aim of this study was to evaluate the safety climate in a Swedish operating room setting before and after an intervention, using a revised version of the WHO checklist to improve teamwork. This study is a single center prospective interventional study. Participants were personnel working in operating room teams including surgeons, anesthesiologists, scrub nurses, nurse anaesthetists and nurse assistants. The study started with pre-interventional observations of the WHO checklist use followed by education on safety climate, the WHO checklist, and non-technical skills in the operating room. Thereafter a revised version of the WHO checklist was introduced. Post-interventional observations regarding the performance of the WHO checklist were carried out. The Safety Attitude Questionnaire was used to assess safety climate at baseline and post-intervention. At baseline we discovered a need for improved teamwork and communication. The participants considered teamwork to be important for patient safety, but had different perceptions of good teamwork between professions. The intervention, a revised version of the WHO checklist, did not affect teamwork climate. Adherence to the revision of the checklist was insufficient, dominated by a lack of structure. There was no significant change in teamwork climate by use of the revised WHO checklist, which may be due to insufficient implementation, as a lack of adherence to the WHO checklist was detected. We found deficiencies in teamwork and communication. Further studies exploring how to improve safety climate are needed. NCT02329691.

  20. 75 FR 5640 - Pipeline Safety: Implementation of Revised Incident/Accident Report Forms for Distribution...

    Science.gov (United States)

    2010-02-03

    ... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... Distribution Systems, Gas Transmission and Gathering Systems, and Hazardous Liquid Systems AGENCY: Pipeline and.... SUMMARY: This notice advises owners and operators of gas pipeline facilities and hazardous liquid pipeline...

  1. Manual of functions, assignments, and responsibilities for nuclear safety: Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    1994-10-15

    The FAR Manual is a convenient easy-to-use collection of the functions, assignments, and responsibilities (FARs) of DOE nuclear safety personnel. Current DOE directives, including Orders, Secretary of Energy Notices, and other assorted policy memoranda, are the source of this information and form the basis of the FAR Manual. Today, the majority of FARs for DOE personnel are contained in DOE`s nuclear safety Orders. As these Orders are converted to rules in the Code of Federal Regulations, the FAR Manual will become the sole source for information relating to the functions, assignments, responsibilities of DOE nuclear safety personnel. The FAR Manual identifies DOE directives that relate to nuclear safety and the specific DOE personnel who are responsible for implementing them. The manual includes only FARs that have been extracted from active directives that have been approved in accordance with the procedures contained in DOE Order 1321.1B.

  2. Fact Sheet: Revisions to the Occupational Safety and Health Administration Hazard Communication Standards (HCS)

    Science.gov (United States)

    On March 26, 2012, Occupational Safety and Health Administration (OSHA) modified its HCS to conform to the United Nations’ (UN) Globally Harmonized System of Classification and Labeling of Chemicals (GHS), to improve consistency and quality of information.

  3. Savannah River Site management response plan for chemical safety vulnerability field assessment. Revision 1

    International Nuclear Information System (INIS)

    Kahal, E.J.; Murphy, S.L.; Salaymeh, S.R.

    1994-09-01

    As part of the U.S. Department of Energy's (DOE) initiative to identify potential chemical safety vulnerabilities in the DOE complex, the Chemical Safety Vulnerability Core Working Group issued a field verification assessment report. While the report concluded that Savannah River Site (SRS) is moving in a positive direction, the report also identified five chemical safety vulnerabilities with broad programmatic impact that are not easily nor quickly remedied. The May 1994 SRS Management Response Plan addressed the five SRS vulnerabilities identified in the field assessment report. The SRS response plan listed observations supporting the vulnerabilities and any actions taken or planned toward resolution. Many of the observations were resolved by simple explanations, such as the existence of implementation plans for Safety Analysis Report updates. Recognizing that correcting individual observations does not suffice in remedying the vulnerabilities, a task team was assembled to address the broader programmatic issues and to recommend corrective actions

  4. Revision of nuclear power plants safety systems' routine testing assigned periodicity during the design extension period

    International Nuclear Information System (INIS)

    Skalozubov, V.I.; Kozlov, Yi.L.; Chulkyin, O.O.

    2017-01-01

    When nuclear power plants safety systems thermal equipment operation extending, a necessary requirement shall rely on revising the scheduled equipment tests frequency to optimize those tests schedule taking into account the equipment remained lifespan. On the one hand, there exists a need for tests frequency increase to detect ''hidden'' failures, and on the another, frequent tests cause a premature wear of the equipment. Proposed is an original method for optimizing the frequency of NPPs safety systems thermal engineering equipment testing. Essential in the proposed method is the optimization criterion chosen: index of security system failure probability non-exceedance during the beyond-design operating period as referred to the failure probability expected considering the equipment residual resource during the design operating period. The developed method implementation when applied to NPPs safety systems operated beyond the design service life at nuclear power plants with WWER-1000 series reactors, allowed to establish that the optimal tests frequency makes half the designed one when the equipment service life is extended by five years and three times less that the designed frequency when subject lifespan extended by 10 years.

  5. Radiation protection of medical staff in the latest draft of the revised Euratom Basic Safety Standards directive

    International Nuclear Information System (INIS)

    Simeonov, Georgi; Mundigl, Stefan; Janssens, Augustin

    2011-01-01

    The European Union has a long and successful history of legislating in the area of radiation protection of the public, workers and individuals submitted to medical exposure, the first Euratom “Basic Safety Standards” (BSS) adopted in 1959 and subsequently updated and supplemented with other Directives. The recent revision of this legislation aims to update it in the light of the latest knowledge and experience and to simplify it by consolidating the current legal acts into one Directive. The draft of the revised Euratom BSS Directive has been approved by the group of scientific experts under Euratom Treaty Article 31 and is currently undergoing the European Commission’s procedures. This draft contains several new or amended provisions relating to protection of medical staff, among them: (i) a streamlining of the annual dose limit provisions, (ii) enhancing the use of dose constraints in optimization of protection, and (iii) ensuring better recording and transfer of occupational dose data including in cases of trans-border movement of workers. The Community action to radiation protection of workers is not restricted to passing relevant legislation but also includes ‘soft action’ as issuing guidance, supporting research and stakeholders’ involvement, etc. In August 2010 the Commission issued a Communication to the Council and the European Parliament dealing with the issues in the medical uses of ionizing radiation, including those relating to radiation protection of medical staff.

  6. Nuclear Criticality Safety Organization guidance for the development of continuing technical training. Revision 1

    International Nuclear Information System (INIS)

    Carroll, K.J.; Taylor, R.G.; Worley, C.A.

    1997-01-01

    The Nuclear Criticality Safety Organization (NCSO) is committed to developing and maintaining a staff of highly qualified personnel to meet the current and anticipated needs in nuclear criticality safety at the Oak Ridge Y-12 Plant and throughout the DOE complex. Continuing technical training is training outside of the initial qualification program to address identified organization-wide needs. Typically, this training is used to improve organization performance in the conduct of business. This document provides guidelines for the development of the technical portions of the Continuing Training Program. It is not a step-by-step procedure, but a collection of considerations to be used during the development process

  7. Safety analysis report for the Mixed Waste Storage Facility and portable storage units at the Idaho National Engineering Laboratory. Revision 4

    International Nuclear Information System (INIS)

    Peatross, R.

    1997-01-01

    This revision contains Section 2 only which gives a description of the Mixed Waste Storage Facility (MWSF) and its operations. Described are the facility location, services and utilities, process description and operation, and safety support systems. The MWSF serves as a storage and repackaging facility for low-level mixed waste

  8. Addendum to the Safety Analysis Report for the Steel Waste Packaging. Revision 1

    International Nuclear Information System (INIS)

    Crow, S.R.

    1996-01-01

    The Battelle Pacific Northwest National Laboratory Safety Analysis Report (SAR) for the Steel Waste Package requires additional analyses to support the shipment of remote-handled radioactive waste and special-case waste from the 324 building hot cells to PUREX for interim storage. This addendum provides the analyses required to show that this waste can be safely shipped onsite in the configuration shown

  9. Independent Safety Assessment of the TOPAZ-II space nuclear reactor power system (Revised)

    International Nuclear Information System (INIS)

    1993-09-01

    The Independent Safety Assessment described in this study report was performed to assess the safety of the design and launch plans anticipated by the U.S. Department of Defense (DOD) in 1993 for a Russian-built, U.S.-modified, TOPAZ-II space nuclear reactor power system. Its conclusions, and the bases for them, were intended to provide guidance for the U.S. Department of Energy (DOE) management in the event that the DOD requested authorization under section 91b. of the Atomic Energy Act of 1954, as amended, for possession and use (including ground testing and launch) of a nuclear-fueled, modified TOPAZ-II. The scientists and engineers who were engaged to perform this assessment are nationally-known nuclear safety experts in various disciplines. They met with participants in the TOPAZ-II program during the spring and summer of 1993 and produced a report based on their analysis of the proposed TOPAZ-II mission. Their conclusions were confined to the potential impact on public safety and did not include budgetary, reliability, or risk-benefit analyses

  10. 78 FR 28987 - Revisions to Transportation Safety Requirements and Harmonization With International Atomic...

    Science.gov (United States)

    2013-05-16

    .... 115, ``International Basic Safety Standards for Protection against Ionizing Radiation and for the... paragraph 107(f) of TS-R-1, which addresses non-radioactive solid objects with radioactive substances..., ``Radiation protection--Sealed radioactive sources-- General requirements and classification,'' Second Edition...

  11. 75 FR 57081 - Revised Draft Safety Culture Policy Statement: Request for Comments

    Science.gov (United States)

    2010-09-17

    ... culture. Experience has shown that certain personal and organizational traits are present in a positive safety culture. A trait, in this case, is a pattern of thinking, feeling, and behaving that emphasizes... organizational environments. IV. Changes to the Initial Draft Statement of Policy Like the initial draft SOP, the...

  12. Packaging review guide for reviewing safety analysis reports for packagings: Revision 0

    International Nuclear Information System (INIS)

    Fischer, L.E.; Chou, C.K.; Lloyd, W.R.; Mount, M.E.; Nelson, T.A.; Schwartz, M.W.; Witte, M.C.

    1987-09-01

    The Department of Energy (DOE) has established procedures for obtaining certification of packagings used by DOE and its contractors for the transport of radioactive materials. These certification review policies and procedures are established to ensure that DOE packaging designs and operations meet safety criteria at least equivalent to the standards prescribed by the Nuclear Regulatory Commission (NRC) certification process for packaging. The Packaging Review Guide (PRG) is not a DOE order, but has been prepared as guidance for the Packaging Certification Staff (PCS) under the Certifying Official, Office of Security Evaluations, or designated representatives. The principal purpose of the PRG is to assure the quality and uniformity of PCS reviews, and to present a well-defined base from which to evaluate proposed changes in the scope and requirements of reviews. The PRG also sets forth solutions and approaches determined to be acceptable in the past by the PCS in dealing with a specific safety issue or safety-related design area. These solutions and approaches are presented in this form so that reviewers can take consistent and well-understood positions as the same safety issues arise in future cases. An applicant submitting a SARP does not have to follow the solutions or approaches presented in the PRG. However, applicants should recognize that the PCS has spent substantial time and effort in reviewing and developing their positions for the issues. A corresponding amount of time and effort will probably be required to review and accept new or different solutions and approaches. Finally, it is also a purpose of the PRG to make information about DOE certification policy and procedures widely available to DOE field offices, DOE contractors, federal agencies, and interested members of the public. 7 refs., 15 figs., 14 tabs

  13. Safety evaluation of the ESP sludge washing baselines runs. Revision 2

    International Nuclear Information System (INIS)

    Gupta, M.K.

    1993-01-01

    Purpose is to provide the technical basis for evaluation of unreviewed safety question for the Extended Sludge Processing (ESP) Sludge Washing Baseline Runs, which are necessary to resolve technical questions associated with process control (sludge suspension, sludge settling, heat transfer, temperature control). The sludge is currently stored in below-ground tanks and will be prepared for processing at the Defense Waste Processing Facility as part of the Integrated Waste Removal Program for Savannah River Site

  14. Testing existing software for safety-related applications. Revision 7.1

    International Nuclear Information System (INIS)

    Scott, J.A.; Lawrence, J.D.

    1995-12-01

    The increasing use of commercial off-the-shelf (COTS) software products in digital safety-critical applications is raising concerns about the safety, reliability, and quality of these products. One of the factors involved in addressing these concerns is product testing. A tester's knowledge of the software product will vary, depending on the information available from the product vendor. In some cases, complete source listings, program structures, and other information from the software development may be available. In other cases, only the complete hardware/software package may exist, with the tester having no knowledge of the internal structure of the software. The type of testing that can be used will depend on the information available to the tester. This report describes six different types of testing, which differ in the information used to create the tests, the results that may be obtained, and the limitations of the test types. An Annex contains background information on types of faults encountered in testing, and a Glossary of pertinent terms is also included. This study is pertinent for safety-related software at reactors

  15. Packaging review guide for reviewing safety analysis reports for packagings: Revision 1

    International Nuclear Information System (INIS)

    Fisher, L.E.; Chou, C.K.; Lloyd, W.R.; Mount, M.E.; Nelson, T.A.; Schwartz, M.W.; Witte, M.C.

    1988-10-01

    The Department of Energy (DOE) has established procedures for obtaining certification of packagings used by DOE and its contractors for the transport of radioactive materials. The principal purpose of this document is to assure the quality and uniformity of PCS reviews and to present a well-defined base from which to evaluate proposed changes in the scope and requirements of reviews. The Packaging Review Guide (PRG) also sets forth solutions and approaches determined to be acceptable in the past in dealing with a specific safety issue or safety-related design area. These solutions and approaches are presented in this form so that reviewers can take consistent and well-understood positions as the same safety issues arise in future cases. An applicant submitting a SARP does not have to follow the solutions or approaches presented. It is also a purpose of the PRG to make information about DOE certification policy and procedures widely available to DOE field offices, DOE contractors, federal agencies, and interested members of the public. 77 refs., 16 figs., 15 tabs

  16. Safety Evaluation of the ESP Sludge Washing Baselines Runs. Revision 1

    International Nuclear Information System (INIS)

    Gupta, M.K.

    1994-08-01

    The purpose is to provide the technical basis for the evaluation of Unreviewed Safety Question for the Extended Sludge Processing (ESP) Sludge Washing Baseline Runs. The Baseline runs are necessary: to ascertain the mechanical fitness of the equipment and modifications not operated since 1988 and to resolve technical questions associated with process control; i.e., sludge suspension, sludge settling, heat transfer, and temperature control. These issues need to be resolved prior to resumption of normal ESP operations. The equipment used for the Baseline runs are Tanks 42H and 51H and their associated equipment

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

    International Nuclear Information System (INIS)

    Conner, J.C.

    1994-01-01

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

  18. Demonstration testing and evaluation of in situ soil heating. Health and safety plan (Revision 2)

    Energy Technology Data Exchange (ETDEWEB)

    Dev, H.

    1994-12-28

    This document is the Health and Safety Plan (HASP) for the demonstration of IITRI`s EM Treatment Technology. In this process, soil is heated in situ by means of electrical energy for the removal of hazardous organic contaminants. This process will be demonstrated on a small plot of contaminated soil located in the Pit Area of Classified Burial Ground K-1070-D, K-25 Site, Oak Ridge, TN. The purpose of the demonstration is to remove organic contaminants present in the soil by heating to a temperature range of 85{degrees} to 95{degrees}C. The soil will be heated in situ by applying 60-Hz AC power to an array of electrodes placed in boreholes drilled through the soil. In this section a brief description of the process is given along with a description of the site and a listing of the contaminants found in the area.

  19. Introductory user's manual for the US Nuclear Regulatory Commission Reactor Safety Research Data Bank. Revision 3

    International Nuclear Information System (INIS)

    Hardy, H.A.; Laats, E.T.

    1985-03-01

    The United States Nuclear Regulatory Commission (USNRC) has established the NRC/Division of Accident Evaluation (DAE) Data Bank Program to collect, store, and make available data from the many domestic and foreign water reactor safety research programs. Local direction of the program is provided by EG and G Idaho, Inc., prime contractor for the Department of Energy (DOE) at the Idaho National Engineering Laboratory (INEL). The NRC/DAE Data Bank Program provides a central computer storage mechanism and access software for data to be used by code development and assessment groups in meeting the code correlation needs of the nuclear industry. The administrative portion of the program provides data entry, documentation, training, and advisory services to users and the USNRC. The NRC/DAE Data Bank and the capabilities of the data access software are described in this document

  20. Structural Design Requirements and Factors of Safety for Spaceflight Hardware: For Human Spaceflight. Revision A

    Science.gov (United States)

    Bernstein, Karen S.; Kujala, Rod; Fogt, Vince; Romine, Paul

    2011-01-01

    This document establishes the structural requirements for human-rated spaceflight hardware including launch vehicles, spacecraft and payloads. These requirements are applicable to Government Furnished Equipment activities as well as all related contractor, subcontractor and commercial efforts. These requirements are not imposed on systems other than human-rated spacecraft, such as ground test articles, but may be tailored for use in specific cases where it is prudent to do so such as for personnel safety or when assets are at risk. The requirements in this document are focused on design rather than verification. Implementation of the requirements is expected to be described in a Structural Verification Plan (SVP), which should describe the verification of each structural item for the applicable requirements. The SVP may also document unique verifications that meet or exceed these requirements with NASA Technical Authority approval.

  1. Demonstration testing and evaluation of in situ soil heating. Health and safety plan (Revision 2)

    International Nuclear Information System (INIS)

    Dev, H.

    1994-01-01

    This document is the Health and Safety Plan (HASP) for the demonstration of IITRI's EM Treatment Technology. In this process, soil is heated in situ by means of electrical energy for the removal of hazardous organic contaminants. This process will be demonstrated on a small plot of contaminated soil located in the Pit Area of Classified Burial Ground K-1070-D, K-25 Site, Oak Ridge, TN. The purpose of the demonstration is to remove organic contaminants present in the soil by heating to a temperature range of 85 degrees to 95 degrees C. The soil will be heated in situ by applying 60-Hz AC power to an array of electrodes placed in boreholes drilled through the soil. In this section a brief description of the process is given along with a description of the site and a listing of the contaminants found in the area

  2. Knowledge Assessment of Food Safety Managers in Utah and Its Implications on the Exam and Instruction

    Science.gov (United States)

    Nummer, Brian A.; Guy, Stanley M.; Bentley, Joanne P. H.

    2010-01-01

    Food Safety Manager's Certification is offered through a state-local Extension partnership in Utah using an online course management system. Exams and course materials were created by an Extension Specialist at Utah State Univ. Extension Agents provide exam and curriculum facilitation in each county. This form of distance education enables access…

  3. Description of the retest instruction for the safety injection system in a German PWR

    International Nuclear Information System (INIS)

    Buettner, W.E.

    1982-01-01

    This report is a detailed supplement to the report 'Retests for a Safety System in a German Nuclear Power Plant' presented at the CSNI Meeting of the Group of Experts on Human Error Data and Assessment, Paris, Sept. 1979. (orig./RW)

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

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  5. Instruction of 27 March 1973 concerning implementation of Decree No 73-278 of 13 March 1973 setting up a Higher Council for Nuclear Safety and a Central Service for the Safety of Nuclear Installations

    International Nuclear Information System (INIS)

    1973-01-01

    This Instruction specifies, on the basis of the 1973 Decree, the duties, in particular regarding licensing, of the Central Service for the Safety of Nuclear Installations. The Service is assisted in its work by the Atomic Energy Commission (CEA) and advisory groups.(NEA) [fr

  6. Technical Review Report for the Model 9975-96 Package Safety Analysis Report for Packaging (S-SARP-G-00003, Revision 0, January 2008)

    International Nuclear Information System (INIS)

    West, M.

    2009-01-01

    This Technical Review Report (TRR) documents the review, performed by the Lawrence Livermore National Laboratory (LLNL) Staff, at the request of the U.S. Department of Energy (DOE), on the Safety Analysis Report for Packaging, Model 9975, Revision 0, dated January 2008 (S-SARP-G-00003, the SARP). The review includes an evaluation of the SARP, with respect to the requirements specified in 10 CFR 71, and in International Atomic Energy Agency (IAEA) Safety Standards Series No. TS-R-1. The Model 9975-96 Package is a 35-gallon drum package design that has evolved from a family of packages designed by DOE contractors at the Savannah River Site. Earlier package designs, i.e., the Model 9965, the Model 9966, the Model 9967, and the Model 9968 Packagings, were originally designed and certified in the early 1980s. In the 1990s, updated package designs that incorporated design features consistent with the then newer safety requirements were proposed. The updated package designs at the time were the Model 9972, the Model 9973, the Model 9974, and the Model 9975 Packagings, respectively. The Model 9975 Package was certified by the Packaging Certification Program, under the Office of Safety Management and Operations. The safety analysis of the Model 9975-85 Packaging is documented in the Safety Analysis Report for Packaging, Model 9975, B(M)F-85, Revision 0, dated December 2003. The Model 9975-85 Package is certified by DOE Certificate of Compliance (CoC) package identification number, USA/9975/B(M)F-85, for the transportation of Type B quantities of uranium metal/oxide, 238 Pu heat sources, plutonium/uranium metals, plutonium/uranium oxides, plutonium composites, plutonium/tantalum composites, 238 Pu oxide/beryllium metal.

  7. Licensing of safety critical software for nuclear reactors - Common position of seven European nuclear regulators and authorised technical support organisations - Revision 2013

    International Nuclear Information System (INIS)

    2013-01-01

    This report is the 5th revision of the report. The task force was formed in 1994 as a group of experts on safety critical software. The members come from regulatory authorities and/or their technical support organization. Bo Liwaang, SSM, has been a member since the work started in 1994. For full information of the historical background, previous revisions of the report and objectives, see the Introduction of the report. The conclusions and viewpoints presented in the report are those of the authors and do not necessarily coincide with those of the SSM. The report, without the SSM cover and this page, will be published by or available at the websites of the other participating organizations. Effect on SSM supervisory and regulatory task: The effect of the report is high as it presents a common view on important issues by experts from seven European regulatory organizations, even though the report is not a regulation or guide

  8. Technical note: Erroneous data in open-quotes Nuclear Safety Guide, TID-7016, Revision 2,close quotes NUREG/CR-0095, ORNL/NUREG/CSD-6 (1978)

    International Nuclear Information System (INIS)

    Whitesides, G.E.

    1991-01-01

    Nuclear Safety Guide, TID-7016 Rev 2 was issued as NUREG/CR-0095 in 1978. Table 2.8 of this report has been found to contain errors. The table was designed to indicate configurations with effective multipliction factors of 0.95. Because of an error in configuration descriptions, some of the configurations have multiplication factors as high as 1.09. A corrected table is available from the undersigned, and Revision 3 of the report is being prepared. Norman L. Pruvost, LANL HSE-6, P. O. Box 1663, M/S-F691, Los Alamos, NM 87545

  9. A study on the revision of nuclear safety act to build the foundation of nuclear export and import control system in Korea

    International Nuclear Information System (INIS)

    Yang, Seung Hyo; Choi, Sun Do

    2012-01-01

    Nuclear related items require export and import control beyond the multilateral export control system according to Safeguard Agreement, Additional Protocol and bilateral agreements. Besides Korea as a nuclear supplier is needed to actively cope with its export control system, which is being reinforced internationally. In regard to this trend, this study drew the revision plan of present Nuclear Safety Act to found the nuclear export and import control system in Korea by examining the related legislations and analyzing the implementation status of nuclear export and import control

  10. A study on the revision of nuclear safety act to build the foundation of nuclear export and import control system in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Seung Hyo; Choi, Sun Do [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

    2012-10-15

    Nuclear related items require export and import control beyond the multilateral export control system according to Safeguard Agreement, Additional Protocol and bilateral agreements. Besides Korea as a nuclear supplier is needed to actively cope with its export control system, which is being reinforced internationally. In regard to this trend, this study drew the revision plan of present Nuclear Safety Act to found the nuclear export and import control system in Korea by examining the related legislations and analyzing the implementation status of nuclear export and import control.

  11. 78 FR 20423 - Oil and Gas and Sulphur Operations in the Outer Continental Shelf-Revisions to Safety and...

    Science.gov (United States)

    2013-04-05

    ... Enforcement (BSEE); Interior. ACTION: Final rule. SUMMARY: This final rule will revise and add several new... 63610). That rule established a new Subpart S in 30 CFR part 250, requiring all OCS operators to have a... to developing and implementing stop work authority (SWA) and ultimate work authority (UWA), requiring...

  12. Compilation of comments concerning the 3rd draft revision of the IAEA regulations for safety transport of radioactive materials

    International Nuclear Information System (INIS)

    1983-08-01

    The report contains comments made by Member States and International Organizations to the third draft revision of the International Energy Agency's regulations for the safe transport of radioactive materials. The comments are compiled in logical groups referring to various aspects of the regulations

  13. 78 FR 11907 - Notice of Forthcoming Workshop To Discuss Revisions to NUREG/BR-0204, Rev. 2 “Instructions for...

    Science.gov (United States)

    2013-02-20

    ... radioactive waste disposal facilities if over-estimated. Additionally, the NRC staff received comments from... Performance Assessment Methodology for Low-Level Radioactive Waste Disposal Facilities'' (ADAMS Accession No..., Rev. 2 ``Instructions for Completing NRC's Uniform Low-Level Radioactive Waste Manifest.'' Information...

  14. Definition and means of maintaining the supply ventilation system seismic shutdown portion of the PFP safety envelope. Revision 2

    International Nuclear Information System (INIS)

    Keck, R.D.

    1995-01-01

    This report describes the modifications to the ventilation system for the Plutonium Finishing Plant. Topics discussed in this report include; system functional requirements, evaluations of equipment, a list of drawings showing the safety envelope boundaries; list of safety envelope equipment, functional requirements for individual safety envelope equipment, and a list of the operational, maintenance and surveillance procedures necessary to operate and maintain the system equipment

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

    International Nuclear Information System (INIS)

    1996-01-01

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

  16. Safety in conducting subcritical neutron-multiplication measurements in situ (Revision of N16.3-1969) - approved 1975

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    The standard provides safety guidance for conducting subcritical neutron-multiplication measurements where physical protection of personnel against the consequences of a criticality accident is not provided. The objectives of in situ measurements are either to confirm an adequate safety margin or to improve an estimate of such a margin. The first objective may constitute a test of the criticality safety of a design that is based on calculations. The second may effect improved operating conditions by reducing the uncertainty of safety margins and providing guidance to new designs

  17. Toxic chemical release inventory reporting form R and instructions. Revised 1992 version. Section 313 of the Emergency Planning and Community Right-to-Know Act

    International Nuclear Information System (INIS)

    1993-01-01

    Reporting is required to provide the public with information on the releases of listed toxic chemicals in their communities and to provide EPA with release information to assist the Agency in determining the need for future regulations. Facilities must report the quantities of both routine and accidental releases of listed toxic chemicals, as well as the maximum amount of the listed toxic chemical on-site during the calendar year and the amount contained in wastes transferred off-site. These instructions supplement and elaborate on the requirements in the reporting rule (40 CFR Part 372). Together with the reporting rule, they constitute the reporting requirements. All references in these instructions are to sections in the reporting rule unless otherwise indicated

  18. BASIC Instructional Program: System Documentation.

    Science.gov (United States)

    Dageforde, Mary L.

    This report documents the BASIC Instructional Program (BIP), a "hands-on laboratory" that teaches elementary programming in the BASIC language, as implemented in the MAINSAIL language, a machine-independent revision of SAIL which should facilitate implementation of BIP on other computing systems. Eight instructional modules which make up…

  19. Writing for Safety. Facilitating a Team Approach to Writing Operating Instructions. ANTA Leading Edge Training Case Study.

    Science.gov (United States)

    Serle, Oenone

    The Australian engineering company, Jaques, and Swinburne University of Technology conducted a joint project to write more than 190 operating instructions for the company's 77 employees. First, the university's Workplace Skills Unit (WSU) interviewed 75 production workers to identify their language, literacy, and training needs. The WSU negotiated…

  20. Road Safety Education in a Science Course: Evaluation of "Science and the Road."

    Science.gov (United States)

    Gardner, Paul L.

    1989-01-01

    A traffic safety instructional package--"Science and the Road"--was assessed. It was designed by the Road Traffic Authority of Victoria (Australia) for use in tenth-grade science courses. Evaluation findings resulted in revision of the unit and implementation of more inservice courses for teachers lacking relevant biology and physics…

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-10-01

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

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

    International Nuclear Information System (INIS)

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

    1997-10-01

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

  3. Safety Analysis Report for Packaging (SARP) of the Oak Ridge National Laboratory Garden Carrier No. 2. Revision 1

    International Nuclear Information System (INIS)

    Box, W.D.; Klima, B.B.; Seagren, R.D.; Shappert, L.B.; Watson, C.D.; Aramayo, G.A.

    1979-08-01

    An analytical evaluation of the Oak Ridge National Laboratory Garden Carrier No. 2 was made to demonstrate its compliance with the regulations governing off-site radioactive material shipping packages. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of the evaluation show that the cask complies with the applicable regulations

  4. Safety Analysis Report for Packaging (SARP) of the Oak Ridge National Laboratory Shipping Cask D-38. Revision 1

    International Nuclear Information System (INIS)

    Box, W.D.; Shappert, L.B.; Seagren, R.D.; Watson, C.D.; Hammond, C.R.; Klima, B.B.

    1979-09-01

    An analytical evaluation of the Oak Ridge National Laboratory Shipping Cask D-38 (solids shipments) was made to demonstrate its compliance with the regulations governing off-site radioactive material shipping packages. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of the evaluation show that the cask complies with the applicable regulations

  5. Engineering task plan for the annual revision of the rotary mode core sampling system safety equipment list

    International Nuclear Information System (INIS)

    BOGER, R.M.

    1999-01-01

    This Engineering Task Plan addresses an effort to provide an update to the RMCS Systems 3 and 4 SEL and DCM in order to incorporate the changes to the authorization basis implemented by HNF-SD-WM-BIO-001, Rev. 0 (Draft), Addendum 5 , Safety Analysis for Rotary Mode Core Sampling. Responsibilities, task description, cost estimate, and schedule are presented

  6. Safety Analysis Report for Packaging (SARP) of the Oak Ridge National Laboratory Garden Carrier No. 2. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Box, W.D.; Klima, B.B.; Seagren, R.D.; Shappert, L.B.; Watson, C.D.; Aramayo, G.A.

    1979-08-01

    An analytical evaluation of the Oak Ridge National Laboratory Garden Carrier No. 2 was made to demonstrate its compliance with the regulations governing off-site radioactive material shipping packages. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of the evaluation show that the cask complies with the applicable regulations.

  7. Safety Analysis Report for Packaging (SARP) of the Oak Ridge National Laboratory Shipping Cask D-38. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Box, W.D.; Shappert, L.B.; Seagren, R.D.; Watson, C.D.; Hammond, C.R.; Klima, B.B.

    1979-09-01

    An analytical evaluation of the Oak Ridge National Laboratory Shipping Cask D-38 (solids shipments) was made to demonstrate its compliance with the regulations governing off-site radioactive material shipping packages. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of the evaluation show that the cask complies with the applicable regulations.

  8. Safety

    International Nuclear Information System (INIS)

    1998-01-01

    A brief account of activities carried out by the Nuclear power plants Jaslovske Bohunice in 1997 is presented. These activities are reported under the headings: (1) Nuclear safety; (2) Industrial and health safety; (3) Radiation safety; and Fire protection

  9. Pre-title I safety evaluation for the retrieval operations of transuranic waste drums in the Solid Waste Disposal Facility. Revision 2

    International Nuclear Information System (INIS)

    Rabin, M.S.

    1992-08-01

    Phase I of the Transuranic (TRU) Waste Facility Line Item Project includes the retrieval and safe storage of the pad drums that are stored on TRU pads 2-6 in the Solid Waste Disposal Facility (SWDF). Drums containing TRU waste were placed on these pads as early as 1974. The pads, once filled, were mounded with soil. The retrieval activities will include the excavation of the soil, retrieval of the pad drums, placing the drums in overpacks (if necessary) and venting and purging the retrieved drums. Once the drums have been vented and purged, they will be transported to other pads within the SWDF or in a designated area until they are eventually treated as necessary for ultimate shipment to the Waste Isolation Pilot Plant in Carlsbad, New Mexico. This safety evaluation provides a bounding assessment of the radiological risk involved with the drum retrieval activities to the maximally exposed offsite individual and the co-located worker. The results of the analysis indicate that the risk to the maximally exposed offsite individual and the co-located worker using maximum frequencies and maximum consequences are within the acceptance criteria defined in WSRC Procedural Manual 9Q. The purpose of this evaluation is to demonstrate the incremental risk from the SWDF due to the retrieval activities for use as design input only. As design information becomes available, this evaluation can be revised to satisfy the safety analysis requirements of DOE Orders 4700 and 5480.23

  10. Tank waste compositions and atmospheric dispersion coefficients for use in accelerated safety analysis consequence assessments. Revision 1

    International Nuclear Information System (INIS)

    Savino, A.V.

    1995-11-01

    This topical report contains technical support information used to determine accident consequences for the Tank Farms Accelerated Safety Analysis (ASA) Interim Chapter 3, Hazard and Accident Analysis: Potential for Releases and Required Mitigation and Prevention and the Tank Waste Remediation System (TWRS) environmental impact statement (EIS) accident consequence report. It does not determine accident consequences or describe specific accident scenarios, but instead provides generic information used to calculate radiological and toxic chemical consequences for postulated tank farms accident releases

  11. 16 CFR 436.7 - Instructions for updating disclosures.

    Science.gov (United States)

    2010-01-01

    ... AND PROHIBITIONS CONCERNING FRANCHISING Instructions § 436.7 Instructions for updating disclosures. (a... this part need not be audited for quarterly revisions; provided, however, that the franchisor states in...

  12. Safety evaluation of the ITP filter/stripper test runs and quiet time runs using simulant solution. Revision 3

    International Nuclear Information System (INIS)

    Gupta, M.K.

    1994-06-01

    The purpose is to provide the technical bases for the evaluation of Unreviewed Safety Question for the In-Tank Precipitation (ITP) Filter/Stripper Test Runs (Ref. 7) and Quiet Time Runs Program (described in Section 3.6). The Filter/Stripper Test Runs and Quiet Time Runs program involves a 12,000 gallon feed tank containing an agitator, a 4,000 gallon flush tank, a variable speed pump, associated piping and controls, and equipment within both the Filter and the Stripper Building

  13. White paper: Preliminary assessment of LNG vehicle technology, economics, and safety issues (Revision 1). Topical report, April-August 1991

    International Nuclear Information System (INIS)

    Powars, C.; Lucher, D.; Moyer, C.; Browning, L.

    1992-01-01

    The objective of the study is to evaluate the potential of LNG as a vehicle fuel, to determine market niches, and to identify needed technology improvements. The white paper is being issued when the work is approximately 30 percent complete to preview the study direction, draw preliminary conclusions, and make initial recommendations. Interim findings relative to LNG vehicle technology, economics, and safety are presented. It is important to decide if heavier hydrocarbons should be allowed in LNG vehicle fuel. Development of suitable refueling couplings and vehicle fuel supply pressure systems are recommended. Initial economics analyses considered transit buses and pickup and delivery trucks fueled via onsite liquefiers and imported LNG. Net user costs were more than (but in some cases close to) those for diesel fuel and gasoline. Lowering the cost of small-scale liquefiers would significantly improve the economics of LNG vehicles. New emissions regulations may introduce considerations beyond simple cost comparisons. LNG vehicle safety and available accident data are reviewed. Consistent codes for LNG vehicles and refueling facilities are needed

  14. Improvement way for mobile X-ray examinations by rule revision about safety management of diagnosis radiation occurrence system

    International Nuclear Information System (INIS)

    Choi, Jun Gu; Kim, Gyeong Su; Kim, Byeong Gi; Ahn, Nam Jun; Kim, Hyeong Sun; Kim, Sang Geon; Lim, Si Eun

    2007-01-01

    A safety management rule of the diagnosis radiation system which opened a court 2006 February 10th was promulgated for safety of the radiation worker, patients and patients' family members. The purpose of this study is to minimize injury by radiation that can happen to patients and people around a sick ward when managing mobile X-ray system. This study analyzed sickroom environment of mobile X-ray examination and the statistical data of the Konkuk medical Information System (KIS) and the Picture Archiving Communication System (PACS). This study also investigated patient conditions, infection, relation information and related data, when the sickroom mobile X-ray examination is used. Through data analysis, many problems were expected such as restriction of space side, manpower and expense of business side, satisfaction degree decline of patient and protector of operation side. Therefore, we tried to restrict examination of multi bed sickroom, and to use treatment room in each ward to solve problem mentioned. As a result, the whole sickroom mobile X-ray examination rate decreased to near 50%, and mobile X-ray examination rate for inpatients decreased to more than 85%. This study shows that several attempts we did should be helpful for manpower, patients satisfaction and expenses. Also, they should protect patients in sickroom from unnecessary radiation exposure and could minimize inconvenience of patients and their family members from x-ray examination

  15. Safety Standard for Hydrogen and Hydrogen Systems: Guidelines for Hydrogen System Design, Materials Selection, Operations, Storage and Transportation. Revision

    Science.gov (United States)

    1997-01-01

    The NASA Safety Standard, which establishes a uniform process for hydrogen system design, materials selection, operation, storage, and transportation, is presented. The guidelines include suggestions for safely storing, handling, and using hydrogen in gaseous (GH2), liquid (LH2), or slush (SLH2) form whether used as a propellant or non-propellant. The handbook contains 9 chapters detailing properties and hazards, facility design, design of components, materials compatibility, detection, and transportation. Chapter 10 serves as a reference and the appendices contained therein include: assessment examples; scaling laws, explosions, blast effects, and fragmentation; codes, standards, and NASA directives; and relief devices along with a list of tables and figures, abbreviations, a glossary and an index for ease of use. The intent of the handbook is to provide enough information that it can be used alone, but at the same time, reference data sources that can provide much more detail if required.

  16. Safety analysis--200 Area Savannah River Site: Separations Area operations Building 211-H Outside Facilities. Supplement 11, Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    1993-01-01

    The H-Area Outside Facilities are located in the 200-H Separations Area and are comprised of a number of processes, utilities, and services that support the separations function. Included are enriched uranium loadout, bulk chemical storage, water handling, acid recovery, general purpose evaporation, and segregated solvent facilities. In addition, services for water, electricity, and steam are provided. This Safety Analysis Report (SAR) documents an analysis of the H-Area Outside Facilities and is one of a series of documents for the Separations Area as specified in the SR Implementation Plan for DOE order 5481.1A. The primary purpose of the analysis was to demonstrate that the facility can be operated without undue risk to onsite or offsite populations, to the environment, and to operating personnel. In this report, risks are defined as the expected frequencies of accidents, multiplied by the resulting radiological consequences in person-rem. Following the summary description of facility and operations is the site evaluation including the unique features of the H-Area Outside Facilities. The facility and process design are described in Chapter 3.0 and a description of operations and their impact is given in Chapter 4.0. The accident analysis in Chapter 5.0 is followed by a list of safety related structures and systems (Chapter 6.0) and a description of the Quality Assurance program (Chapter 7.0). The accident analysis in this report focuses on estimating the risk from accidents as a result of operation of the facilities. The operations were evaluated on the basis of three considerations: potential radiological hazards, potential chemical toxicity hazards, and potential conditions uniquely different from normal industrial practice.

  17. Safety analysis--200 Area Savannah River Site: Separations Area operations Building 211-H Outside Facilities. Supplement 11, Revision 1

    International Nuclear Information System (INIS)

    1993-01-01

    The H-Area Outside Facilities are located in the 200-H Separations Area and are comprised of a number of processes, utilities, and services that support the separations function. Included are enriched uranium loadout, bulk chemical storage, water handling, acid recovery, general purpose evaporation, and segregated solvent facilities. In addition, services for water, electricity, and steam are provided. This Safety Analysis Report (SAR) documents an analysis of the H-Area Outside Facilities and is one of a series of documents for the Separations Area as specified in the SR Implementation Plan for DOE order 5481.1A. The primary purpose of the analysis was to demonstrate that the facility can be operated without undue risk to onsite or offsite populations, to the environment, and to operating personnel. In this report, risks are defined as the expected frequencies of accidents, multiplied by the resulting radiological consequences in person-rem. Following the summary description of facility and operations is the site evaluation including the unique features of the H-Area Outside Facilities. The facility and process design are described in Chapter 3.0 and a description of operations and their impact is given in Chapter 4.0. The accident analysis in Chapter 5.0 is followed by a list of safety related structures and systems (Chapter 6.0) and a description of the Quality Assurance program (Chapter 7.0). The accident analysis in this report focuses on estimating the risk from accidents as a result of operation of the facilities. The operations were evaluated on the basis of three considerations: potential radiological hazards, potential chemical toxicity hazards, and potential conditions uniquely different from normal industrial practice

  18. The effectiveness of different instruction methods for risk and safety management in relation to medical profession and seniority

    NARCIS (Netherlands)

    Navot Pikkel, Dvora

    2017-01-01

    The study, which was guided by Prof.dr J.b. Rijsman as promotor and by Dr. Y.T. Tal as co- promotor, was a comparative interventional study that was designed to evaluate the effectiveness of different teaching & educational strategies of risk management and patient's safety in medicine. Eventually,

  19. Analysis of human tissue management models for medical research: preparation for implementation of the 2012 revision of the Bioethics and Safety Act of Korea.

    Science.gov (United States)

    Ryu, Young-Joon; Kim, Hankyeom; Jang, Sejin; Koo, Young-Mo

    2013-06-01

    Efficient management of human tissue samples is a critical issue; the supply of samples is unable to satisfy the current demands for research. Lack of informed consent is also an ethical problem. One of the goals of the 2012 revision of Korea's Bioethics and Safety Act was to implement regulations that govern the management of human tissue samples. To remain competitive, medical institutions must prepare for these future changes. In this report, we review two tissue management models that are currently in use; model 1 is the most common system utilized by hospitals in Korea and model 2 is implemented by some of the larger institutions. We also propose three alternative models that offer advantages over the systems currently in use. Model 3 is a multi-bank model that protects the independence of physicians and pathologists. Model 4 utilizes a comprehensive single bioresource bank; although in this case, the pathologists gain control of the samples, which may make it difficult to implement. Model 5, which employs a bioresource utilization steering committee (BUSC), is viable to implement and still maintains the advantages of Model 4. To comply with the upcoming law, we suggest that physicians and pathologists in an institution should collaborate to choose one of the improved models of tissue management system that best fits for their situation.

  20. Final safety analysis report for the Galileo mission: Volume 3 (Book 2), Nuclear risk analysis document: Appendices: Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    1989-01-25

    It is the purpose of the NRAD to provide an analysis of the range of potential consequences of accidents which have been identified that are associated with the launching and deployment of the Galileo mission spacecraft. The specific consequences analyzed are those associated with the possible release of radioactive material (fuel) of the Radioisotope Thermoelectric Generators (RTGs). They are in terms of radiation doses to people and areas of deposition of radioactive material. These consequence analyses can be used in several ways. One way is to identify the potential range of consequences which might have to be dealt with if there were to be an accident with a release of fuel, so as to assure that, given such an accident, the health and safety of the public will be reasonably protected. Another use of the information, in conjunction with accident and release probabilities, is to estimate the risks associated with the mission. That is, most space launches occur without incident. Given an accident, the most probable result relative to the RTGs is complete containment of the radioactive material. Only a small fraction of accidents might result in a release of fuel and subsequent radiological consequences. The combination of probability with consequence is risk, which can be compared to other human and societal risks to assure that no undue risks are implied by undertaking the mission. Book 2 contains eight appendices.

  1. Phenomenological analyses and their application to the Defense Waste Processing Facility probabilistic safety analysis accident progression event tree. Revision 1

    International Nuclear Information System (INIS)

    Kalinich, D.A.; Thomas, J.K.; Gough, S.T.; Bailey, R.T.; Kearnaghan, D.P.

    1995-01-01

    In the Defense Waste Processing Facility (DWPF) Safety Analysis Reports (SARs) for the Savannah River Site (SRS), risk-based perspectives have been included per US Department of Energy (DOE) Order 5480.23. The NUREG-1150 Level 2/3 Probabilistic Risk Assessment (PRA) methodology was selected as the basis for calculating facility risk. The backbone of this methodology is the generation of an Accident Progression Event Tree (APET), which is solved using the EVNTRE computer code. To support the development of the DWPF APET, deterministic modeling of accident phenomena was necessary. From these analyses, (1) accident progressions were identified for inclusion into the APET; (2) branch point probabilities and any attendant parameters were quantified; and (3) the radionuclide releases to the environment from accidents were determined. The phenomena of interest for accident progressions included explosions, fires, a molten glass spill, and the response of the facility confinement system during such challenges. A variety of methodologies, from hand calculations to large system-model codes, were used in the evaluation of these phenomena

  2. SAFETY

    CERN Multimedia

    Niels Dupont

    2013-01-01

    CERN Safety rules and Radiation Protection at CMS The CERN Safety rules are defined by the Occupational Health & Safety and Environmental Protection Unit (HSE Unit), CERN’s institutional authority and central Safety organ attached to the Director General. In particular the Radiation Protection group (DGS-RP1) ensures that personnel on the CERN sites and the public are protected from potentially harmful effects of ionising radiation linked to CERN activities. The RP Group fulfils its mandate in collaboration with the CERN departments owning or operating sources of ionising radiation and having the responsibility for Radiation Safety of these sources. The specific responsibilities concerning "Radiation Safety" and "Radiation Protection" are delegated as follows: Radiation Safety is the responsibility of every CERN Department owning radiation sources or using radiation sources put at its disposition. These Departments are in charge of implementing the requi...

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

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  4. Manpower development for safe operation of nuclear power plant. China. Revision of final safety analysis report. Activity: 5.1.3-Task-08. Technical report

    International Nuclear Information System (INIS)

    Almeida, C.; Elias, D.

    1994-01-01

    The objectives of this mission included providing assistance for the revision of the FSAR including: national practices, administrative procedures, required staffing level, other resources, planning, scheduling, content, and organization of the revision. Activities included several days of lectures regarding worldwide practices including the United States and Commonwealth Edison Company (ComEd), interaction with Chinese counterparts re. their FSAR and Technical Specification revision and two visits to the Qin Shan NPP

  5. Revising Translations

    DEFF Research Database (Denmark)

    Rasmussen, Kirsten Wølch; Schjoldager, Anne

    2011-01-01

    The paper explains the theoretical background and findings of an empirical study of revision policies, using Denmark as a case in point. After an overview of important definitions, types and parameters, the paper explains the methods and data gathered from a questionnaire survey and an interview...... survey. Results clearly show that most translation companies regard both unilingual and comparative revisions as essential components of professional quality assurance. Data indicate that revision is rarely fully comparative, as the preferred procedure seems to be a unilingual revision followed by a more...... or less comparative rereading. Though questionnaire data seem to indicate that translation companies use linguistic correctness and presentation as the only revision parameters, interview data reveal that textual and communicative aspects are also considered. Generally speaking, revision is not carried...

  6. Practical implications of the ICRP recommendations (1977) and the revised IAEA basic safety standards for radiation protection

    International Nuclear Information System (INIS)

    1979-01-01

    Full text: The Seminar provided a forum for exchange of views concerning the practical problems associated with the implementation of the recommendations published in ICRP report No. 26 The papers presented and the discussions which followed will greatly help the IAEA, WHO, ILO and OECD/NEA to finalize the draft of the Basic Safety Standards for Radiation Protection. The papers and discussions centered mainly on three items - risk assessments and the associated detriment which might result from exposure to ionizing radiation as encountered in radiation work, optimization of protection; and some practical difficulties associated with the implementation of the recommendations Examples of the application of optimization were presented which helped clarify the methodology of optimizing protection. General and panel discussions helped to clarify the question of intuitive versus quantitative optimization. The consensus was that optimization of protection is mainly an intuitive operation, the quantitative tools being an aid to the process. These tools are more important in optimizing the design of installations and equipment, while the process is less quantitative in the case of optimization of operations. The value of the man-rem was discussed in a few papers and in panel and other discussions. It became clear that its value can be different in different cases of justification and different again in justification and optimization assessments. Therefore a range of values is needed rather than a single universal value. However, for optimization assessments where parts of the collective dose occur in different countries, the principal of geographical equity was advocated, implying the same value to the man-rem in all countries. Some papers and discussions centered around the identification and evaluation of detriment. Two types of detriment were identified, namely 'objective' detriment (composed of stochastic effects which could be assessed f r om knowledge of the

  7. Safety

    International Nuclear Information System (INIS)

    2001-01-01

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

  8. CERN's new safety policy

    CERN Multimedia

    2014-01-01

    The documents below, published on 29 September 2014 on the HSE website, together replace the document SAPOCO 42 as well as Safety Codes A1, A5, A9, A10, which are no longer in force. As from the publication date of these documents any reference made to the document SAPOCO 42 or to Safety Codes A1, A5, A9 and A10 in contractual documents or CERN rules and regulations shall be deemed to constitute a reference to the corresponding provisions of the documents listed below.   "The CERN Safety Policy" "Safety Regulation SR-SO - Responsibilities and organisational structure in matters of Safety at CERN" "General Safety Instruction GSI-SO-1 - Departmental Safety Officer (DSO)" "General Safety Instruction GSI-SO-2 - Territorial Safety Officer (TSO)" "General Safety Instruction GSI-SO-3 - Safety Linkperson (SLP)" "General Safety Instruction GSI-SO-4 - Large Experiment Group Leader In Matters of Safety (LEXGLI...

  9. 30 CFR 48.25 - Training of new miners; minimum courses of instruction; hours of instruction.

    Science.gov (United States)

    2010-07-01

    ...; minimum courses of instruction; hours of instruction. (a) Each new miner shall receive no less than 24...: Provided, That no less than 8 hours of training shall in all cases be given to new miners before they are... instruction; hours of instruction. 48.25 Section 48.25 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION...

  10. Visit safety

    CERN Document Server

    2012-01-01

    Experiment areas, offices, workshops: it is possible to have co-workers or friends visit these places.     You already know about the official visits service, the VIP office, and professional visits. But do you know about the safety instruction GSI-OHS1, “Visits on the CERN site”? This is a mandatory General Safety Instruction that was created to assist you in ensuring safety for all your visits, whatever their nature—especially those that are non-official. Questions? The HSE Unit will be happy to answer them. Write to safety-general@cern.ch.   The HSE Unit

  11. 75 FR 57597 - Revised Proposal for Revisions to the Schedules of Civil Penalties for a Violation of a Federal...

    Science.gov (United States)

    2010-09-21

    ... Revisions to the Schedules of Civil Penalties for a Violation of a Federal Railroad Safety Law or Federal... railroad safety laws and regulations are necessary because many of FRA's civil penalties have not been..., et al. Revised Proposal for Revisions to the Schedules of Civil Penalties for a Violation of a...

  12. Designing Preclinical Instruction of Psychomotor Skills (IV)--Instructional Engineering: Evaluation Phase.

    Science.gov (United States)

    Guenzel, Pamela J.; And Others

    1995-01-01

    The fourth article in a four-part series on instructional design discusses evaluation of a psychomotor skills unit taught in preclinical dental education. Issues examined include piloting of instructional materials, analysis and revision of materials based on student performance, syllabus design and content, influence of faculty characteristics,…

  13. SAFETY

    CERN Multimedia

    M. Plagge, C. Schaefer and N. Dupont

    2013-01-01

    Fire Safety – Essential for a particle detector The CMS detector is a marvel of high technology, one of the most precise particle measurement devices we have built until now. Of course it has to be protected from external and internal incidents like the ones that can occur from fires. Due to the fire load, the permanent availability of oxygen and the presence of various ignition sources mostly based on electricity this has to be addressed. Starting from the beam pipe towards the magnet coil, the detector is protected by flooding it with pure gaseous nitrogen during operation. The outer shell of CMS, namely the yoke and the muon chambers are then covered by an emergency inertion system also based on nitrogen. To ensure maximum fire safety, all materials used comply with the CERN regulations IS 23 and IS 41 with only a few exceptions. Every piece of the 30-tonne polyethylene shielding is high-density material, borated, boxed within steel and coated with intumescent (a paint that creates a thick co...

  14. SAFETY

    CERN Multimedia

    C. Schaefer and N. Dupont

    2013-01-01

      “Safety is the highest priority”: this statement from CERN is endorsed by the CMS management. An interpretation of this statement may bring you to the conclusion that you should stop working in order to avoid risks. If the safety is the priority, work is not! This would be a misunderstanding and misinterpretation. One should understand that “working safely” or “operating safely” is the priority at CERN. CERN personnel are exposed to different hazards on many levels on a daily basis. However, risk analyses and assessments are done in order to limit the number and the gravity of accidents. For example, this process takes place each time you cross the road. The hazard is the moving vehicle, the stake is you and the risk might be the risk of collision between both. The same principle has to be applied during our daily work. In particular, keeping in mind the general principles of prevention defined in the late 1980s. These principles wer...

  15. Safety

    International Nuclear Information System (INIS)

    Jones, P.M.S.

    1987-01-01

    Aspects of fission reactors are considered - control, heat removal and containment. Brief descriptions of the reactor accidents at the SL-1 reactor (1961), Windscale (1957), Browns Ferry (1975), Three Mile Island (1979) and Chernobyl (1986) are given. The idea of inherently safe reactor designs is discussed. Safety assessment is considered under the headings of preliminary hazard analysis, failure mode analysis, event trees, fault trees, common mode failure and probabalistic risk assessments. These latter can result in a series of risk distributions linked to specific groups of fault sequences and specific consequences. A frequency-consequence diagram is shown. Fatal accident incidence rates in different countries including the United Kingdom for various industries are quoted. The incidence of fatal cancers from occupational exposure to chemicals is tabulated. Human factors and the acceptability of risk are considered. (U.K.)

  16. Best practices in writing instruction

    CERN Document Server

    Fitzgerald, Jill; MacArthur, Charles A

    2014-01-01

    An indispensable teacher resource and course text, this book presents evidence-based practices for helping all K-12 students develop their skills as writers. Every chapter draws clear connections to the Common Core State Standards (CCSS). Leading authorities describe how to teach the skills and strategies that students need to plan, draft, evaluate, and revise multiple types of texts. Also addressed are ways for teachers to integrate technology into the writing program, use assessment to inform instruction, teach writing in the content areas, and tailor instruction for English language learner

  17. Revising REACH guidance on information requirements and chemical safety assessment for engineered nanomaterials for aquatic ecotoxicity endpoints: recommendations from the EnvNano project

    DEFF Research Database (Denmark)

    Hansen, Steffen Foss; Sørensen, Sara Nørgaard; Skjolding, Lars Michael

    2017-01-01

    be made applicable to nanomaterials. European Research Council project EnvNano—Environmental Effects and Risk Evaluation of Engineered, which ran from 2011 to 2016, took another outset by assuming that: “The behaviour of nanoparticles in suspension is fundamentally different from that of chemicals......The European Chemical Agency (ECHA) is in the process of revising its guidance documents on how to address the challenges of ecotoxicological testing of nanomaterials. In these revisions, outset is taken in the hypothesis that ecotoxicological test methods, developed for soluble chemicals, can...... in solution”. The aim of this paper is to present the findings of the EnvNano project and through these provide the scientific background for specific recommendations on how ECHA guidance could be further improved. Key EnvNano findings such as the need to characterize dispersion and dissolution rates in stock...

  18. New and revised standards for coke production

    Energy Technology Data Exchange (ETDEWEB)

    G.A. Kotsyuba; M.I. Alpatov; Y.G. Shapoval [Giprokoks, the State Institute for the Design of Coke-Industry Enterprises, Kharkov (Ukraine)

    2009-07-15

    The need for new and revised standards for coke production in Ukraine and Russia is outlined. Such standards should address improvements in plant operation, working conditions, environmental protection, energy conservation, fire and explosion safety, and economic indices.

  19. Civilian use transport of radioactive substances on public road. Volume 1: Shipment accreditation and approval requests. Guide Nr 7, Revision 2 of 15 February 2016. Volume 2: safety file of package models, European guide 'Package Design Safety Report'. Civilian use transport of radioactive packages or substances on public road. Volume 3: Compliance of package models not subject to accreditation. Guide Nr 7, Revision 7 of the 2015/11/13

    International Nuclear Information System (INIS)

    2016-01-01

    After having recalled the regulatory context and sanctions susceptible to be applied, the first volume presents the accreditation process for a package model: file content, tests programme, safety file, certification studies, documents to be produced, accreditation prorogation request, accreditation extension or package model modifications, instruction delays. Some peculiar cases are described. Models of accreditation certificate are provided, and obligations concerning packaging design, fabrication, use and maintenance are briefly discussed. The second volume is a European technical guide which is intended to assist in the preparation of the Package Design Safety Report (PDSR) to demonstrate compliance of a package design for the transport of radioactive material with the regulatory requirements. It covers package designs requiring competent authority approval, and also covers package designs not requiring competent authority approval. In its first two chapters, this document provides a generic structure and contents of a PDSR which applies to all package types. The contents are described in a comprehensive way to cover all important aspects. Some of these aspects may not be applicable to specific package type and details can be found in the annexes which provide further guidance for the scope of the contents of a PDSR, specifically for each package type. The third volume presents recommendations made by the ASN for all stakeholders to guarantee the compliance to regulation of package models which are 'not submitted to competent authority approval'. After an indication and a comment of the regulatory context, it presents requirements to be applied for the design of those package models, and then describes and comments the structure and content of a safety file for such package models (generalities, authorised contents, packaging description, safety demonstration, receipt, use and maintenance instruction, management system). The last part presents the

  20. RPP-PRT-58489, Revision 1, One Systems Consistent Safety Analysis Methodologies Report. 24590-WTP-RPT-MGT-15-014

    Energy Technology Data Exchange (ETDEWEB)

    Gupta, Mukesh [URS Professional Solutions LLC, Aiken, SC (United States); Niemi, Belinda [Washington River Protection Solutions, LLC, Richland, WA (United States); Paik, Ingle [Washington River Protection Solutions, LLC, Richland, WA (United States)

    2015-09-02

    In 2012, One System Nuclear Safety performed a comparison of the safety bases for the Tank Farms Operations Contractor (TOC) and Hanford Tank Waste Treatment and Immobilization Plant (WTP) (RPP-RPT-53222 / 24590-WTP-RPT-MGT-12-018, “One System Report of Comparative Evaluation of Safety Bases for Hanford Waste Treatment and Immobilization Plant Project and Tank Operations Contract”), and identified 25 recommendations that required further evaluation for consensus disposition. This report documents ten NSSC approved consistent methodologies and guides and the results of the additional evaluation process using a new set of evaluation criteria developed for the evaluation of the new methodologies.

  1. 76 FR 2291 - TRICARE Reimbursement Revisions

    Science.gov (United States)

    2011-01-13

    ... rule revises the regulation by removing references to specific numeric Diagnosis Related Group (DRG... following methods: Federal eRulemaking Portal: http://www.regulations.gov . Follow the instructions for... descriptions became obsolete, so we are removing the numeric references in the regulation and utilizing only...

  2. The present condition of the radiation safety control education in training schools for radiological technologists

    International Nuclear Information System (INIS)

    Takahashi, Yasuyuki; Saito, Kyoko; Hirai, Shoko; Igarashi, Hiroshi; Negishi, Tooru; Hirano, Kunihiro; Kawaharada, Yasuhiro

    2010-01-01

    We made a detailed study on the course of study in radiation safety control prescribed on March 28, 2003. Questionnaires were sent to 39 training schools for radiological technology, to which 66.7% replied (26/39). Subjects on radiation safety control must include knowledge and technology in both radiation control and medical safety. The contents for instruction of radiation control were in accordance with those given in the traditional program; however, some discrepancies were found in the contents of medical safety. As medical safety, emphasized by the revised Medical Service Law, is regarded as very important by many hospitals, safety control education that include medical ethics should be required as part of the curriculum in the training schools for radiological technologists. (author)

  3. Safety: Preventive Medicine.

    Science.gov (United States)

    Kotula, John R.; Digenakis, Anthony

    1985-01-01

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

  4. Better Science Through Safety.

    Science.gov (United States)

    Gerlovich, Jack A.; Downs, Gary E.

    Following a brief description of the major components found effective in school safety programs (safety management, education, and services) and data on school accidents in Iowa, this book addresses various aspects of safety related to science instruction, emphasizing that responsibility for safety must be shared by both teacher and students.…

  5. Environmental, Safety, and Health Plan for the remedial investigation/feasibility study at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Revision 1, Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    Davis, C. M.; El-Messidi, O. E.; Cowser, D. K.; Kannard, J. R.; Carvin, R. T.; Will, III, A. S.; Clark, Jr., C.; Garland, S. B.

    1993-05-01

    This Environmental, Safety, and Health (ES&H) Plan presents the concepts and methodologies to be followed during the remedial investigation/feasibility study (RI/FS) for Oak Ridge National Laboratory (ORNL) to protect the health and safety of employees, the public, and the environment. This ES&H Plan acts as a management extension for ORNL and Martin Marietta Energy Systems, Inc. (Energy Systems) to direct and control implementation of the project ES&H program. The subsections that follow describe the program philosophy, requirements, quality assurance measures, and methods for applying the ES&H program to individual waste area grouping (WAG) remedial investigations. Hazardous work permits (HWPs) will be used to provide task-specific health and safety requirements.

  6. Editorial - Instructions

    DEFF Research Database (Denmark)

    Kastberg, Peter; Grinsted, Annelise

    2007-01-01

    Why you may wonder - have we chosen a topic which at first glance may seem trivial, and even a bit dull? Well, looks can be deceiving, and in this case they are! There are many good reasons for taking a closer look at instructions.......Why you may wonder - have we chosen a topic which at first glance may seem trivial, and even a bit dull? Well, looks can be deceiving, and in this case they are! There are many good reasons for taking a closer look at instructions....

  7. LIBRARY SKILL INSTRUCTION IN NIGERIAN ACADEMIC LIBRARIES

    African Journals Online (AJOL)

    DJFLEX

    www.globaljournalseries.com; Info@globaljournalseries.com. LIBRARY SKILL INSTRUCTION IN NIGERIAN ACADEMIC. LIBRARIES. P. C. AZIAGBA AND E. H. UZOEZI. (Received 10, September 2009; Revision Accepted 8, February 2010). ABSTRACT. This survey was undertaken to portray the level of library involvement ...

  8. Safety for Older Consumers: Home Safety Checklist

    Science.gov (United States)

    ... and switches have cover plates installed so no wiring is exposed. U nused receptacles have safety covers ... pour gasoline into a kerosene heater. Review the installation and operating instructions. Call the manufacturer or your ...

  9. Cement Mason's Curriculum. Instructional Units.

    Science.gov (United States)

    Hendirx, Laborn J.; Patton, Bob

    To assist cement mason instructors in providing comprehensive instruction to their students, this curriculum guide treats both the skills and information necessary for cement masons in commercial and industrial construction. Ten sections are included, as follow: related information, covering orientation, safety, the history of cement, and applying…

  10. CSER 90-006, addendum 1: Criticality safety control for source term reduction project in the scrubber glovebox of Building 232-Z. Revision 1

    International Nuclear Information System (INIS)

    Hess, A.L.

    1995-01-01

    This Criticality Safety Evaluation Report addendum extends the coverage of the original CSER (90-006) about dismantling the ductwork in 232-Z to include cleanout of the Scrubber Glovebox, with an estimated residual Pu holdup of less than 200 grams. For conservatism and containment considerations, the provisions about waste packaging and water exclusion from the original work are retained, even though it is not credible for the Scrubber Pu content to be made critical with water added (NDA gives about 1/3 a minimum critical mass)

  11. Resource description and access 2013 revision

    CERN Document Server

    2013-01-01

    This e-book contains the 2013 Revision of RDA: Resource Description and Access, and includes the July 2013 Update. This e-book offers links within the RDA text and the capability of running rudimentary searches of RDA, but please note that this e-book does not have the full range of content or functionality provided by the subscription product RDA Toolkit. Included: A full accumulation of RDA- the revision contains a full set of all current RDA instructions. It replaces the previous version of RDA Print as opposed to being an update packet to that version. RDA has gone through many changes sin

  12. Instructional Partners, Principals, Teachers, and Instructional Assistants.

    Science.gov (United States)

    Indiana State Dept. of Public Instruction, Indianapolis.

    This handbook examines various topics of interest and concern to teachers as they work with instructional assistants forming a classroom instructional partnership and functioning as a team. These topics include: (1) instructional assistant qualifications; (2) duties--instructional, classroom clerical, auxillary; (3) factors to be considered when…

  13. Safety assessment for the proposed pilot-scale treatability tests for the 200-UP-1 and 200-ZP-1 groundwater operable units. Revision 1

    International Nuclear Information System (INIS)

    1994-12-01

    This safety assessment provides an analysis of the proposed pilot-scale treatability test activities to be and conducted within the 200 Area groundwater operable units on the Hanford Site. The 200-UP-1 and 200-ZP-1 operable units are located in the 200 West Area of the Hanford Site. These tests will evaluate an ion exchange (IX) water purification treatment system and granular activated carbon (GAC). A detailed engineering analysis of (GAC) adsorption for remediation of groundwater contamination. A detailed engineering analysis of the IX treatment system. The principal source of information for this assessment, states that the performance objective of the treatment systems is to remove 90% of the uranium and technetium-99 ( 99 Tc) from the extracted groundwater at the 200-UP-1 site. The performance objective for 200-ZP-1 is to remove 90% of the carbon tetrachloride (CCl 4 ), chloroform, and trichloroethylene (TCE) from the extracted groundwater

  14. Further development and data basis for safety and accident analyses of nuclear front end and back end facilities and actualization and revision of calculation methods for nuclear safety analyses. Final report; Weiterentwicklung von Methoden und Datengrundlagen zu Sicherheits- und Stoerfallanalysen fuer Anlagen der nuklearen Ver- und Entsorgung sowie Aktualisierung und Ueberpruefung von Rechenmethoden zu nuklearen Sicherheitsanalysen. Abschlussbericht

    Energy Technology Data Exchange (ETDEWEB)

    Kilger, Robert; Peters, Elisabeth; Sommer, Fabian; Moser, Eberhard-Franz; Kessen, Sven; Stuke, Maik

    2016-07-15

    This report briefly describes the activities carried out under the project 3613R03350 on the GRS ''Handbook on Accident Analysis for Nuclear Front and Back End Facilities'', and in detail the continuing work on the revision and updating of the GRS ''Handbook on Criticality'', which here focused on fissile systems with plutonium and {sup 233}U. The in previous projects started and ongoing literature study on innovative fuel concepts is continued. Also described are the review and qualification of computational methods by research and active benchmark participation, and the results of tracking the state of science and technology in the field of computational methods for criticality safety analysis. Special in-depth analyzes of selected criticality-relevant occurrences in the past are also documented.

  15. Revision of ASCE 4

    International Nuclear Information System (INIS)

    Nelson, T.A.; Murray, R.C.; Short, S.A.

    1995-01-01

    The original version of ASCE Standard 4, ''Seismic Analysis of Safety-Related Nuclear Structures'' was published in September 1986. It is ASCE policy to update its standards on a five year interval and the Working Group on Seismic Analysis of Safety Related Nuclear Structures was reconvened to formulate the revisions. The goal in updating the standard is to make sure that it is still relevant and that it incorporates the state of the practice in seismic engineering or, in some cases, where it has been demonstrated that state-of-the-art improvements need to be made to standard practice; new improvements are included. The contents of the new standard cover the same areas as the original version, with some additions. The contents are as follows: Input - response spectra and time histories; modeling of structures; analysis of structures; soil-structure interaction; input for subsystem analysis; special structures - buried pipes and conduits, earth-retaining walls, above-ground vertical tanks, raceways, and base-isolated structures; and an appendix providing seismic probabilistic risk assessment and margin assessment

  16. TRUPACT-II Operating and Maintenance Instructions

    Energy Technology Data Exchange (ETDEWEB)

    Westinghouse Electric Corporation, Waste Isolation Division

    1999-12-31

    The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II) Shipping Package and directly related components. This document complies with the minimum requirements as specified in the TRUPACT-II Safety Analysis Report for Packaging (SARP) and Nuclear Regulatory Commission (NRC) Certificate of Compliance (C of C) 9218. In the event there is a conflict between this document and the TRUPACT-II SARP, the TRUPACT-II SARP shall govern. TRUPACT-II C of C number 9218 states, ''... each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application.'' It further states, ''... each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the application.'' Chapter 9 of the TRUPACT-II SARP charges the Westinghouse Electric Corporation Waste Isolation Division (WID) with assuring that the TRUPACT-II is used in accordance with the requirements of the C of C. To meet this requirement and verify consistency of operations when loading and unloading the TRUPACT-II on the trailer, placing a payload in the packaging, unloading the payload from the packaging, or performing maintenance, the U.S. Department of Energy Carlsbad Area Office (U.S. DOE/CAO) finds it necessary to implement the changes that follow. This TRUPACT-II maintenance document represents a change to previous philosophy regarding site specific procedures for the use of the TRUPACT-II. This document details the instructions to be followed to consistently operate and maintain the TRUPACT-II. The intent of these instructions is to ensure that all users of the TRUPACT-II follow the same or equivalent instructions. Users may achieve this intent by any of the following methods: (1

  17. ASSET guidelines. Revised 1991 Edition

    International Nuclear Information System (INIS)

    1991-12-01

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

  18. Loosening After Acetabular Revision

    DEFF Research Database (Denmark)

    Beckmann, Nicholas A.; Weiss, Stefan; Klotz, Matthias C.M.

    2014-01-01

    The best method of revision acetabular arthroplasty remains unclear. Consequently, we reviewed the literature on the treatment of revision acetabular arthroplasty using revision rings (1541 cases; mean follow-up (FU) 5.7 years) and Trabecular Metal, or TM, implants (1959 cases; mean FU 3.7 years...

  19. Impact of revising the National Nosocomial Infection Surveillance System definition for catheter-related bloodstream infection in ICU: reproducibility of the National Healthcare Safety Network case definition in an Australian cohort of infection control professionals.

    Science.gov (United States)

    Worth, Leon J; Brett, Judy; Bull, Ann L; McBryde, Emma S; Russo, Philip L; Richards, Michael J

    2009-10-01

    Effective and comparable surveillance for central venous catheter-related bloodstream infections (CLABSIs) in the intensive care unit requires a reproducible case definition that can be readily applied by infection control professionals. Using a questionnaire containing clinical cases, reproducibility of the National Nosocomial Infection Surveillance System (NNIS) surveillance definition for CLABSI was assessed in an Australian cohort of infection control professionals participating in the Victorian Hospital Acquired Infection Surveillance System (VICNISS). The same questionnaire was then used to evaluate the reproducibility of the National Healthcare Safety Network (NHSN) surveillance definition for CLABSI. Target hospitals were defined as large metropolitan (1A) or other large hospitals (non-1A), according to the Victorian Department of Human Services. Questionnaire responses of Centers for Disease Control and Prevention NHSN surveillance experts were used as gold standard comparator. Eighteen of 21 eligible VICNISS centers participated in the survey. Overall concordance with the gold standard was 57.1%, and agreement was highest for 1A hospitals (60.6%). The proportion of congruently classified cases varied according to NNIS criteria: criterion 1 (recognized pathogen), 52.8%; criterion 2a (skin contaminant in 2 or more blood cultures), 83.3%; criterion 2b (skin contaminant in 1 blood culture and appropriate antimicrobial therapy instituted), 58.3%; non-CLABSI cases, 51.4%. When survey questions regarding identification of cases of CLABSI criterion 2b were removed (consistent with the current NHSN definition), overall percentage concordance increased to 62.5% (72.2% for 1A centers). Further educational interventions are required to improve the discrimination of primary and secondary causes of bloodstream infection in Victorian intensive care units. Although reproducibility of the CLABSI case definition is relatively poor, adoption of the revised NHSN definition

  20. Nuclear criticality safety guide

    International Nuclear Information System (INIS)

    Ro, Seong Ki; Shin, Hee Seong; Park, Seong Won; Shin, Young Joon.

    1997-06-01

    Nuclear criticality safety guide was described for handling, transportation and storage of nuclear fissile materials in this report. The major part of the report was excerpted frp, TID-7016(revision 2) and nuclear criticality safety written by Knief. (author). 16 tabs., 44 figs., 5 refs

  1. Discussion on some issues for HAF003 revision

    International Nuclear Information System (INIS)

    Huang Chaoyun, Wang Xiaotao; Duan Hongwei; Tian Feng

    2013-01-01

    This paper describes some key issues which should be considered during the revision of safety code Quality Assurance for Nuclear Power Plant (HAF003), based on the comparatively analysis and research on the quality assurance practice for nuclear power. It covers about 24 issues including management responsibilities, independent assessment, design control and procurement control etc. and is expected to provide some reference and proposal for HAF003 revision activities organized by National Nuclear Safety Agency (NNSA). (authors)

  2. 76 FR 44965 - Notice of Revision of Standard Forms 39 and 39-A

    Science.gov (United States)

    2011-07-27

    ... OFFICE OF PERSONNEL MANAGEMENT Notice of Revision of Standard Forms 39 and 39-A AGENCY: U.S... Management (OPM) has revised Standard Form (SF) 39, Request For Referral Of Eligibles, and SF 39-A, Request... part 332. The SF 39 outlines instructions to be used by hiring officials to request a list of eligible...

  3. Inquiry, A Project of the Wisconsin Bar Foundation. Vols. 1 and 2, Revised.

    Science.gov (United States)

    Scheurich, G. Michael, Ed.

    This new, revised edition of the Inquiry instructional materials is designed for use in teaching high school students about the U. S. laws and legal systems. The revised outlines, designed for instructors who have had legal training, are less technical and more informal, include new concepts and many current relevant topics, and de-emphasize…

  4. Strategy Instruction in Mathematics.

    Science.gov (United States)

    Goldman, Susan R.

    1989-01-01

    Experiments in strategy instruction for mathematics have been conducted using three models (direct instruction, self-instruction, and guided learning) applied to the tasks of computation and word problem solving. Results have implications for effective strategy instruction for learning disabled students. It is recommended that strategy instruction…

  5. Learning curves, taking instructions, and patient safety: using a theoretical domains framework in an interview study to investigate prescribing errors among trainee doctors

    Directory of Open Access Journals (Sweden)

    Duncan Eilidh M

    2012-09-01

    Full Text Available Abstract Background Prescribing errors are a major source of morbidity and mortality and represent a significant patient safety concern. Evidence suggests that trainee doctors are responsible for most prescribing errors. Understanding the factors that influence prescribing behavior may lead to effective interventions to reduce errors. Existing investigations of prescribing errors have been based on Human Error Theory but not on other relevant behavioral theories. The aim of this study was to apply a broad theory-based approach using the Theoretical Domains Framework (TDF to investigate prescribing in the hospital context among a sample of trainee doctors. Method Semistructured interviews, based on 12 theoretical domains, were conducted with 22 trainee doctors to explore views, opinions, and experiences of prescribing and prescribing errors. Content analysis was conducted, followed by applying relevance criteria and a novel stage of critical appraisal, to identify which theoretical domains could be targeted in interventions to improve prescribing. Results Seven theoretical domains met the criteria of relevance: “social professional role and identity,” “environmental context and resources,” “social influences,” “knowledge,” “skills,” “memory, attention, and decision making,” and “behavioral regulation.” From critical appraisal of the interview data, “beliefs about consequences” and “beliefs about capabilities” were also identified as potentially important domains. Interrelationships between domains were evident. Additionally, the data supported theoretical elaboration of the domain behavioral regulation. Conclusions In this investigation of hospital-based prescribing, participants’ attributions about causes of errors were used to identify domains that could be targeted in interventions to improve prescribing. In a departure from previous TDF practice, critical appraisal was used to identify additional domains

  6. Learning curves, taking instructions, and patient safety: using a theoretical domains framework in an interview study to investigate prescribing errors among trainee doctors.

    Science.gov (United States)

    Duncan, Eilidh M; Francis, Jill J; Johnston, Marie; Davey, Peter; Maxwell, Simon; McKay, Gerard A; McLay, James; Ross, Sarah; Ryan, Cristín; Webb, David J; Bond, Christine

    2012-09-11

    Prescribing errors are a major source of morbidity and mortality and represent a significant patient safety concern. Evidence suggests that trainee doctors are responsible for most prescribing errors. Understanding the factors that influence prescribing behavior may lead to effective interventions to reduce errors. Existing investigations of prescribing errors have been based on Human Error Theory but not on other relevant behavioral theories. The aim of this study was to apply a broad theory-based approach using the Theoretical Domains Framework (TDF) to investigate prescribing in the hospital context among a sample of trainee doctors. Semistructured interviews, based on 12 theoretical domains, were conducted with 22 trainee doctors to explore views, opinions, and experiences of prescribing and prescribing errors. Content analysis was conducted, followed by applying relevance criteria and a novel stage of critical appraisal, to identify which theoretical domains could be targeted in interventions to improve prescribing. Seven theoretical domains met the criteria of relevance: "social professional role and identity," "environmental context and resources," "social influences," "knowledge," "skills," "memory, attention, and decision making," and "behavioral regulation." From critical appraisal of the interview data, "beliefs about consequences" and "beliefs about capabilities" were also identified as potentially important domains. Interrelationships between domains were evident. Additionally, the data supported theoretical elaboration of the domain behavioral regulation. In this investigation of hospital-based prescribing, participants' attributions about causes of errors were used to identify domains that could be targeted in interventions to improve prescribing. In a departure from previous TDF practice, critical appraisal was used to identify additional domains that should also be targeted, despite participants' perceptions that they were not relevant to

  7. Multidisciplinary training program to create new breed of radiation monitor: the health and safety technician

    International Nuclear Information System (INIS)

    Vance, W.F.

    1979-01-01

    A multidiscipline training program established to create a new monitor, theHealth and Safety Technician, is described. The training program includes instruction in fire safety, explosives safety, industrial hygiene, industrial safety, health physics, and general safety practices

  8. 77 FR 9515 - List of Approved Spent Fuel Storage Casks: HI-STORM 100, Revision 8

    Science.gov (United States)

    2012-02-17

    ... Storage Casks: HI-STORM 100, Revision 8 AGENCY: Nuclear Regulatory Commission. ACTION: Direct final rule... regulations by revising the Holtec International HI-STORM 100 dry cask storage system listing within the... and safety will be adequately protected. This direct final rule revises the HI-STORM 100 listing in 10...

  9. 75 FR 55529 - Homeland Security Acquisition Regulation (HSAR); Revision Initiative

    Science.gov (United States)

    2010-09-13

    ... 3002 Definitions of Words and Terms Add an additional office within components--the Office of Selective... (b) of HSAR section 3003.1004 advises contracting officers that special posters and instructions may... DHS Hotline Poster described in the clause at FAR 52.203-14. Part 3004 Administrative Matters Revise...

  10. Bicycle Safety in Action.

    Science.gov (United States)

    National Commission on Safety Education, Washington, DC.

    This material was designed to assist schools in teaching bicycle safety. As the population grows and competition for road space increases, it is more imperative than ever that we concentrate attention on the need for caution among pupil cyclists. The pamphlet: (1) discusses the role of bicycle safety in classroom instruction and in student…

  11. Idaho Safety Manual.

    Science.gov (United States)

    Idaho State Dept. of Education, Boise. Div. of Vocational Education.

    This manual is intended to help teachers, administrators, and local school boards develop and institute effective safety education as a part of all vocational instruction in the public schools of Idaho. This guide is organized in 13 sections that cover the following topics: introduction to safety education, legislation, levels of responsibility,…

  12. Official News relating to CERN Safety Rules

    CERN Multimedia

    HSE Unit

    2015-01-01

    The CERN Safety Rules listed below have been published on the official CERN Safety Rules website (see here).   Safety Regulation SR-WS Works and services: this SR-WS (version 1) will cancel and replace the corresponding provisions of Safety Instruction IS50 “Safety Coordination on CERN Worksites”. General Safety Instruction GSI-WS-1 Safety coordination for works and services: this GSI-WS-1 (version 1) will cancel and replace the corresponding provisions of Safety Instruction IS39 “Notice of Start of Works (AOC)” and of Safety Instruction IS50 “Safety Coordination on CERN Worksites” ​Specific Safety Instruction SSI-WS-1-1 Safety coordinator for category 1 operations: this SSI-WS-1-4 (version 1) will cancel and replace the corresponding provisions of Safety Instruction IS50 “Safety Coordination on CERN Worksites”.​ ​ In order to limit the impact on the end-of-year technical st...

  13. 46. The goals of safety engineering department of the plant

    International Nuclear Information System (INIS)

    Ivanov, A.V.

    1993-01-01

    The goals of safety engineering department of the plant, including elaboration of instructions on safety engineering on all specialities, safety engineering training of all labours working on the plant and control for abidance by the instructions on safety engineering were discussed.

  14. Human-system interface design review guideline -- Review software and user's guide: Final report. Revision 1, Volume 3

    International Nuclear Information System (INIS)

    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

  15. SAFETY NOTES

    CERN Document Server

    TIS Secretariat

    2001-01-01

    Please note that the revisions of safety notes no 3 (NS 3 Rev. 2) and no 24 (NS 24 REV.) entitled respectively 'FIRE PREVENTION FOR ENCLOSED SPACES IN LARGE HALLS' and 'REMOVING UNBURIED ELV AND LVA ELECTRIC CONDUITS' are available on the web at the following urls: http://edmsoraweb.cern.ch:8001/cedar/doc.download?document_id=322811&version=1&filename=version_francaise.pdf http://edmsoraweb.cern.ch:8001/cedar/doc.download?document_id=322861&version=2&filename=version_francaise.pdf Paper copies can also be obtained from the TIS Divisional Secretariat, email tis.secretariat@cern.ch

  16. Bibliocable. Revised Edition.

    Science.gov (United States)

    Cable Television Information Center, Washington, DC.

    This selective, annotated bibliography is a revision of the original published in 1972 (ED 071 402). Some 104 books, articles, and reports included here deal with access, applications, franchising, regulation, technology, and other aspects of cable television. The listings are of two types in each category. First are revisions of the original…

  17. Safety at work-third edition

    International Nuclear Information System (INIS)

    Keidar, Y.; Keren, M.

    1992-01-01

    This book treats various aspects of safety at work with a view to instructing the worker in safeguarding himself against common risks and hazards. Special empasis is laid on the safety in nuclear installations. (author)

  18. Illinois School Bus Driver Instructional Program. Trainee Guide. Revised.

    Science.gov (United States)

    Illinois State Board of Education, Springfield.

    This trainee guide contains six units of materials for use by those studying to become school bus drivers in the State of Illinois. Covered in the units are the following topics: school bus driver role and responsibility, passenger control, first aid, driving fundamentals, accidents and emergencies, and detecting hazards. Each unit contains a…

  19. Investigating Instruction for Improving Revision of Argumentative Essays

    Science.gov (United States)

    Butler, Jodie A.; Britt, M. Anne

    2011-01-01

    Students are expected to come into the current college classroom already possessing certain skills including the ability to write at the appropriate academic level regardless of discipline and the ability to create well-structured arguments. Research indicates, however, that most students entering college are underprepared in both areas. One…

  20. Remedial Action and Waste Disposal Project Manager's Implementing Instructions

    International Nuclear Information System (INIS)

    Dronen, V.R.

    1998-01-01

    These Project Manager's Implementing Instructions provide the performance standards required of all Environmental Restoration Contractor personnel in their work during operation and administration of the Remedial Action and Waste Disposal Project. The instructions emphasize technical competency, workplace discipline, and personal accountability to ensure a high level of safety and performance during operations activities

  1. BIBLIOGRAPHY ON INDIVIDUALIZED INSTRUCTION.

    Science.gov (United States)

    Harvard Univ., Cambridge, MA. Graduate School of Education.

    THIS BIBLIOGRAPHY LISTS MATERIAL ON VARIOUS ASPECTS OF INDIVIDUALIZED INSTRUCTION. APPROXIMATELY 85 UNANNOTATED REFERENCES ARE PROVIDED TO DOCUMENTS DATING FROM 1958 TO 1966. JOURNALS, BOOKS, AND REPORT MATERIALS ARE LISTED. SUBJECT AREAS INCLUDED ARE PROGRAMED INSTRUCTION, TEACHING MACHINES, RESPONSE MODE, SELF-INSTRUCTION, AND COMPUTER-ASSISTED…

  2. The Instructional Capacitor

    Science.gov (United States)

    Walton, Elizabeth

    2012-01-01

    Many administrators are so overwhelmed by the basic responsibilities of their daily work that there seems to be little or no time left for providing quality leadership in instruction. Instead, schools employ department chairs, instructional specialists, and coordinators to provide instructional leadership. How can administrators find time in the…

  3. New set of Chemical Safety rules

    CERN Multimedia

    HSE Unit

    2011-01-01

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

  4. Instructed officers Radiation Protection

    International Nuclear Information System (INIS)

    2007-01-01

    This law contains instructions on the prevention of radiological and contains 4 articles Article I: describe the responsibilities of the institutions that operate within the scope of radiological protection in terms of the number of radiation protection officers and personal Supervisors who available in the practices radiation field. Article II: talking about the conditions of radiation protection officers that must be available in the main officers and working field in larg institutions and thecondition of specific requirements for large enterprises of work permits in the field of radiological work that issued by the Council. Article III: the functions and duties of officers in the prevention of radiological oversee the development of radiation protection programmes in the planning stages, construction and preparing the rules of local labour and what it lead of such tasks.Article IV: radiation protection officers powers: to modify and approve the programme of prevention and radiation safety at the company, stop any unsafe steps, amend the steps of the usage, operation of materials, devices and so on

  5. Publishing and Revising Content

    Science.gov (United States)

    Editors and Webmasters can publish content without going through a workflow. Publishing times and dates can be set, and multiple pages can be published in bulk. Making an edit to published content created a revision.

  6. Letter of Map Revision

    Data.gov (United States)

    Earth Data Analysis Center, University of New Mexico — The National Flood Hazard Layer (NFHL) data incorporates all Digital Flood Insurance Rate Map(DFIRM) databases published by FEMA, and any Letters Of Map Revision...

  7. HSE's safety assessment principles for criticality safety

    International Nuclear Information System (INIS)

    Simister, D N; Finnerty, M D; Warburton, S J; Thomas, E A; Macphail, M R

    2008-01-01

    The Health and Safety Executive (HSE) published its revised Safety Assessment Principles for Nuclear Facilities (SAPs) in December 2006. The SAPs are primarily intended for use by HSE's inspectors when judging the adequacy of safety cases for nuclear facilities. The revised SAPs relate to all aspects of safety in nuclear facilities including the technical discipline of criticality safety. The purpose of this paper is to set out for the benefit of a wider audience some of the thinking behind the final published words and to provide an insight into the development of UK regulatory guidance. The paper notes that it is HSE's intention that the Safety Assessment Principles should be viewed as a reflection of good practice in the context of interpreting primary legislation such as the requirements under site licence conditions for arrangements for producing an adequate safety case and for producing a suitable and sufficient risk assessment under the Ionising Radiations Regulations 1999 (SI1999/3232 www.opsi.gov.uk/si/si1999/uksi_19993232_en.pdf). (memorandum)

  8. Radiological control manual. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Kloepping, R.

    1996-05-01

    This Lawrence Berkeley National Laboratory Radiological Control Manual (LBNL RCM) has been prepared to provide guidance for site-specific additions, supplements and interpretation of the DOE Radiological Control Manual. The guidance provided in this manual is one methodology to implement the requirements given in Title 10 Code of Federal Regulations Part 835 (10 CFR 835) and the DOE Radiological Control Manual. Information given in this manual is also intended to provide demonstration of compliance to specific requirements in 10 CFR 835. The LBNL RCM (Publication 3113) and LBNL Health and Safety Manual Publication-3000 form the technical basis for the LBNL RPP and will be revised as necessary to ensure that current requirements from Rules and Orders are represented. The LBNL RCM will form the standard for excellence in the implementation of the LBNL RPP.

  9. Radiological control manual. Revision 1

    International Nuclear Information System (INIS)

    Kloepping, R.

    1996-05-01

    This Lawrence Berkeley National Laboratory Radiological Control Manual (LBNL RCM) has been prepared to provide guidance for site-specific additions, supplements and interpretation of the DOE Radiological Control Manual. The guidance provided in this manual is one methodology to implement the requirements given in Title 10 Code of Federal Regulations Part 835 (10 CFR 835) and the DOE Radiological Control Manual. Information given in this manual is also intended to provide demonstration of compliance to specific requirements in 10 CFR 835. The LBNL RCM (Publication 3113) and LBNL Health and Safety Manual Publication-3000 form the technical basis for the LBNL RPP and will be revised as necessary to ensure that current requirements from Rules and Orders are represented. The LBNL RCM will form the standard for excellence in the implementation of the LBNL RPP

  10. Agencies revise standards for radiation protection

    International Nuclear Information System (INIS)

    Anon.

    1984-01-01

    The article deals with a guideline, compiled by the IAEA, for radiation protection. The guidelines aim at the control of individual risk through specified limits, optimisation of protection and the justification of all practices involving exposure to radiation. The guideline is a revision of the 1967 publication of the IAEA, Basic safety standards for radiation protection. According to the document the main resposibility for radiation protection lies with the employer. The workers should be responsible for observing protection procedures and regulations for their own as well as others' safety

  11. Revised legislation affecting the transport of radioactive materials

    International Nuclear Information System (INIS)

    Rowlands, R.P.

    1976-01-01

    The revised edition of the model Regulations for the safe transport of radioactive materials (1973, Vienna, International Atomic Energy Agency Safety Series no.6) has acted as the basis for the conditions of carriage and regulatory requirements in Great Britain. The changes introduced in this revised edition are discussed, and the current Regulations and Codes of Practice covering U.K. and international transport by road, sea, rail and air reviewed. (U.K.)

  12. Radiation safety

    International Nuclear Information System (INIS)

    Van Riessen, A.

    2002-01-01

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

  13. Long multiplication by instruction sequences with backward jump instructions

    NARCIS (Netherlands)

    Bergstra, J.A.; Middelburg, C.A.

    2013-01-01

    For each function on bit strings, its restriction to bit strings of any given length can be computed by a finite instruction sequence that contains only instructions to set and get the content of Boolean registers, forward jump instructions, and a termination instruction. Backward jump instructions

  14. National Chemistry Teacher Safety Survey

    Science.gov (United States)

    Plohocki, Barbra A.

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

  15. Acetabular Cup Revision.

    Science.gov (United States)

    Kim, Young-Ho

    2017-09-01

    The use of acetabular cup revision arthroplasty is on the rise as demands for total hip arthroplasty, improved life expectancies, and the need for individual activity increase. For an acetabular cup revision to be successful, the cup should gain stable fixation within the remaining supportive bone of the acetabulum. Since the patient's remaining supportive acetabular bone stock plays an important role in the success of revision, accurate classification of the degree of acetabular bone defect is necessary. The Paprosky classification system is most commonly used when determining the location and degree of acetabular bone loss. Common treatment options include: acetabular liner exchange, high hip center, oblong cup, trabecular metal cup with augment, bipolar cup, bulk structural graft, cemented cup, uncemented cup including jumbo cup, acetabular reinforcement device (cage), trabecular metal cup cage. The optimal treatment option is dependent upon the degree of the discontinuity, the amount of available bone stock and the likelihood of achieving stable fixation upon supportive host bone. To achieve successful acetabular cup revision, accurate evaluation of bone defect preoperatively and intraoperatively, proper choice of method of acetabular revision according to the evaluation of acetabular bone deficiency, proper technique to get primary stability of implant such as precise grafting technique, and stable fixation of implant are mandatory.

  16. Reactor safety research and safety technology. Pt. 2

    International Nuclear Information System (INIS)

    Theenhaus, R.; Wolters, J.

    1987-01-01

    The state of HTR safety research work reached permits a comprehensive and reliable answer to be given to questions which have been raised by the reactor accident at Chernobyl, regarding HTR safety. Together with the probability safety analyses, the way to a safety concept suitable for an HTR is cleared; instructions are given for design optimisation with regard to safety technique and economy. The consequences of a graphite fire, the neutron physics design and the consequenes of the lack of a safety containment are briefly described. (DG) [de

  17. The Growth of Instructional Coaching Partner Conversations in a PreK-3rd Grade Teacher Professional Development Experience

    Science.gov (United States)

    Thomas, Earl E.; Bell, David L.; Spelman, Maureen; Briody, Jennifer

    2015-01-01

    Instructional coaching that supports teachers' with revising teaching practices is not understood. This study sought to understand the impact of the instructional coaching experience by recording coaching conversations/interactions with teachers. The purpose was to determine if the type of coaching conversations changed overtime during three…

  18. Programmed Instruction Revisited.

    Science.gov (United States)

    Skinner, B. F.

    1986-01-01

    Discusses the history and development of teaching machines, invented to restore the important features of personalized instruction as public school class size increased. Examines teaching and learning problems over the past 50 years, including motivation, attention, appreciation, discovery, and creativity in relation to programmed instruction.…

  19. Fashions in Instructional Development.

    Science.gov (United States)

    Knapper, Christopher K.

    This paper on instructional development notes the trend toward teaching improvement efforts, classifies instructional development centers in terms of their differing philosophies of operation, and identifies some general problems that have been encountered in institutional efforts to improve teaching and learning. Centers in North America, Europe,…

  20. Tractor Safety. Unit A-9.

    Science.gov (United States)

    Luft, Vernon D.; Backlund, Paul

    This document is a teacher's guide for a unit in tractor and machinery safety for college freshmen. It is intended to be used for 10 hours of instruction for freshmen who are intending to work on or around machinery. Safety hazards directly and indirectly related to many types of machinery are covered in addition to tractors. The objectives of the…

  1. Official News relating to CERN Safety Rules

    CERN Multimedia

    HSE Unit

    2015-01-01

    The CERN Safety Rules listed below have been published on the HSE website (see here) and entered into force on the 9 June 2015:   Safety Regulation SR-M “Mechanical equipment”: http://cern.ch/safety-rules/SR-M_ENv2.htm; this SR-M (version 2) cancels and replaces SR-M (version 1) and the corresponding provisions of General Safety Instruction GSI-M3 “Special Equipment” (version 1).   General Safety Instruction GSI-M-1 “Lifting equipment and accessories”: http://cern.ch/safety-rules/GSI-M-1_ENv2.htm; this GSI-M-1 (version 2) cancels and replaces GSI-M1 (version 1). Specific Safety Instruction SSI-M-1-1 “Slings and lifting chains”: http://cern.ch/safety-rules/SSI-M-1-1_EN.htm; Specific Safety Instruction SSI-M-1-2 “Cranes, bridge cranes, gantry cranes and power-driven hoists”: http://cern.ch/safety-rules/SSI-M-1-2_EN.htm; Specific Safety Instruction SSI-M-1-3 “Non-f...

  2. Effects of positive impression management on the NEO Personality Inventory--Revised in a clinical population.

    Science.gov (United States)

    Ballenger, J F; Caldwell-Andrews, A; Baer, R A

    2001-06-01

    Sixty adults in outpatient psychotherapy completed the NEO Personality Inventory--Revised (NEO PI-R, P. T. Costa & R. R. McCrae, 1992a). Half were instructed to fake good and half were given standard instructions. All completed the Interpersonal Adjective Scale--Revised, Big Five (J. S. Wiggins & P. D. Trapnell, 1997) under standard instructions, and their therapists completed the observer rating form of the NEO Five-Factor Inventory. A comparison group of 30 students completed the NEO PI-R under standard instructions. Standard and fake-good participants obtained significantly different NEO PI-R domain scores. Correlations between the NEO PI-R and criterion measures were significantly lower for faking than for standard patients. Validity scales for the NEO PI-R (J. A. Schinka, B. N. Kinder, & T. Kremer, 1997) were moderately accurate in discriminating faking from standard patients, but were only marginally accurate in discriminating faking patients from students.

  3. 14 CFR 34.6 - Aircraft safety.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false Aircraft safety. 34.6 Section 34.6... safety. (a) The provisions of this part will be revised if at any time the Administrator determines that an emission standard cannot be met within the specified time without creating a safety hazard. (b...

  4. Revision of Pachycentria (Melastomataceae)

    NARCIS (Netherlands)

    Clausing, Gudrun

    2000-01-01

    A revision of Pachycentria Blume, which includes the monotypic Pogonanthera Blume, is presented. Pachycentria comprises eight species and one subspecies. Two species, P. vogelkopensis and P. hanseniana, are newly described. The genus is distinguished from other genera in the Medinillinae by a small

  5. Revision of Oxandra (Annonaceae)

    NARCIS (Netherlands)

    Junikka, L.; Maas, P.J.M.; Maas-van de Kamer, H.; Westra, L.Y.Th.

    2016-01-01

    A taxonomic revision is given of the Neotropical genus Oxandra (Annonaceae). Within the genus 27 species are recognized, 4 of which are new to science. Most of the species are occurring in tropical South America, whereas a few (6) are found in Mexico and Central America and two in the West Indies

  6. Revision without ordinals

    NARCIS (Netherlands)

    Rivello, Edoardo

    2013-01-01

    We show that Herzberger’s and Gupta’s revision theories of truth can be recast in purely inductive terms, without any appeal neither to the transfinite ordinal numbers nor to the axiom of Choice. The result is presented in an abstract and general setting, emphasising both its validity for a wide

  7. Revising and editing for translators

    CERN Document Server

    Mossop, Brian

    2014-01-01

    Revising and Editing for Translators provides guidance and learning materials for translation students learning to edit texts written by others, and professional translators wishing to improve their self-revision ability or learning to revise the work of others. Editing is understood as making corrections and improvements to texts, with particular attention to tailoring them to the given readership. Revising is this same task applied to draft translations. The linguistic work of editors and revisers is related to the professional situations in which they work. Mossop offers in-depth coverage of a wide range of topics, including copyediting, style editing, structural editing, checking for consistency, revising procedures and principles, and translation quality assessment. This third edition provides extended coverage of computer aids for revisers, and of the different degrees of revision suited to different texts. The inclusion of suggested activities and exercises, numerous real-world examples, a proposed gra...

  8. Status of the IAEA safety standards programme

    International Nuclear Information System (INIS)

    2002-01-01

    This presentation describes the status of the IAEA safety standards program to May 2002. The safety standards program overcome whole main nuclear implementations as General safety, Nuclear safety, Radiation safety, Radioactive waste safety, and Transport safety. Throughout this report the first column provides the list of published IAEA Safety Standards. The second gives the working identification number (DS) of standards being developed or revised. The bold type indicates standard issued under the authority the Board of Governors, others are issued under authority of the Director General. The last column provides the list of Committees, the first Committee listed has the lead in the preparation and review of the particular standard

  9. Using Principles of Programmed Instruction

    Science.gov (United States)

    Huffman, Harry

    1971-01-01

    Although programmed instruction in accounting is available, it is limited in scope and in acceptance. Teachers, however, may apply principles of programming to the individualizing of instruction. (Author)

  10. Safety and efficiency of future systems

    International Nuclear Information System (INIS)

    2000-01-01

    The objective of the program was to investigate and evaluate new or revised concepts for nuclear energy that offer potential long term benefits in terms of cost, safety, waste management, use of fissile material, less risk of diversion and sustainability. The work program was concerned with studying innovative or revised reactor concepts and other applications, and innovative fuels and fuel cycles

  11. 77 FR 67628 - National Fire Codes: Request for Public Input for Revision of Codes and Standards

    Science.gov (United States)

    2012-11-13

    ... Standard on Fire and 7/8/2013 Life Safety in Animal Housing Facilities. NFPA 160--2011 Standard for the Use... five years in Revision Cycles that begin twice each year and take approximately two years to complete. Each Revision Cycle proceeds according to a published schedule that includes final dates for all major...

  12. 76 FR 32321 - Approval and Promulgation of Air Quality Implementation Plans; Pennsylvania; Revision to the...

    Science.gov (United States)

    2011-06-06

    ...) Program--Quality Assurance Protocol for the Safety Inspection Program in Non-I/M Counties AGENCY... approve revisions to the Pennsylvania State Implementation Plan (SIP). The revision consists of a change... prior SIP-approved I/M program to change the duration of the timing of quality assurance audits...

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

    Science.gov (United States)

    Dionne, Raymond A

    2016-09-01

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

  14. Basic Drafting. Revised.

    Science.gov (United States)

    Schertz, Karen

    This introductory module on drafting includes the technical content and tasks necessary for a student to be employed in an entry-level drafting occupation. The module contains 18 instructional units that cover the following topics: introduction to drafting; tools and equipment; supplies and materials; sketching; scales; drawing format; lettering;…

  15. Minnesota's Forest Trees. Revised.

    Science.gov (United States)

    Miles, William R.; Fuller, Bruce L.

    This bulletin describes 46 of the more common trees found in Minnesota's forests and windbreaks. The bulletin contains two tree keys, a summer key and a winter key, to help the reader identify these trees. Besides the two keys, the bulletin includes an introduction, instructions for key use, illustrations of leaf characteristics and twig…

  16. Questions and answers based on revised 10 CFR Part 20

    International Nuclear Information System (INIS)

    Borges, T.; Stafford, R.S.; Lu, P.Y.; Carter, D.

    1994-05-01

    NUREG/CR-6204 is a collection of questions and answers that were originally issued in seven sets and which pertain to revised 10 CFR Part 20. The questions came from both outside and within the NRC. The answers were compiled and provided by NRC staff within the offices of Nuclear Reactor Regulation, Nuclear Material Safety and Safeguards, Nuclear Regulatory Research, the Office of State Programs, and the five regional offices. Although all of the questions and answers have been reviewed by attorneys in the NRC Office of the General Counsel, they do not constitute official legal interpretations relevant to revised 10 CFR Part 20. The questions and answers do, however, reflect NRC staff decisions and technical options on aspects of the revised 10 CFR Part 20 regulatory requirements. This NUREG is being made available to encourage communication among the public, industry, and NRC staff concerning the major revisions of the NRC's standards for protection against radiation

  17. Using Interactive Video Instruction To Enhance Public Speaking Instruction.

    Science.gov (United States)

    Cronin, Michael W.; Kennan, William R.

    Noting that interactive video instruction (IVI) should not and cannot replace classroom instruction, this paper offers an introduction to interactive video instruction as an innovative technology that can be used to expand pedagogical opportunities in public speaking instruction. The paper: (1) defines the distinctive features of IVI; (2) assesses…

  18. Revision of Krsko NPP Quality Assurance Plan

    International Nuclear Information System (INIS)

    Biscan, R.; Fifnja, I.; Kavsek, D.

    2012-01-01

    International standards from nuclear power plant operation area are being frequently upgraded and revised in accordance with the continuous improvement philosophy. This philosophy applies also to the area of Quality Assurance, which has also undergone significant improvement since the early 1950s. Besides just nuclear industry, there are also other international quality standards that are being continuously developed and revised, bringing needs for upgrades also in the nuclear application. Since the beginning of Krsko NPP construction, the overall Quality Assurance program and its applicable procedures were in place to assure that all planned and systematic actions necessary to provide adequate confidence that an item or service will satisfy given requirements to quality, are in place. The overall requirements for quality as one of the major objectives for Krsko NPP operation are also set forth in the Updated Safety Analyses Report, the document that serves as a base for operating license. During more than 30 years of Krsko NPP operation, the quality requirements and related documents were revised and upgraded in several attempts. The latest revision 6 of QD-1, Quality Assurance Plan was issued during the year 2011. The bases for the revision were: Changes of the Slovenian regulatory requirements (ZVISJV, JV5, JV9?), Changes of Krsko NPP licensing documents (USAR section 13?), SNSA inspection requirements, Changes of international standards (IAEA, ISO?), Conclusions of first PSR, Implementation of ISO standards in Krsko NPP (ISO14001, ISO17025), Changes of plant procedures, etc. One of the most obvious changes was the enlargement of the QA Plan scope to cover interdisciplinary areas defined in the plant management program MD-1, such as Safety culture, Self-assessment, Human performance, Industrial Safety etc. The attachment of the QA Plan defining relationships between certain standards was also updated to provide matrix for better correlation of requirements of

  19. 309 Building fire protection analysis and justification for deactivation of sprinkler system. Revision 1

    International Nuclear Information System (INIS)

    Conner, R.P.

    1997-01-01

    Provide a 'graded approach' fire evaluation in preparation for turnover to Environmental Restoration Contractor for D and D. Scope includes revising 309 Building book value and evaluating fire hazards, radiological and toxicological releases, and life safety issues

  20. Computer Assisted Instruction

    Science.gov (United States)

    Higgins, Paul

    1976-01-01

    Methodology for developing a computer assisted instruction (CAI) lesson (scripting, programing, and testing) is reviewed. A project done by Informatics Education Ltd. (IEL) for the Department of National Defense (DND) is used as an example. (JT)

  1. Bibliographic Instruction : A Webliography

    Directory of Open Access Journals (Sweden)

    2004-09-01

    Full Text Available A Webliography about the Bibliographic Instruction, it collects a variety of internet resources divided to main categories; directories, articles, bibliographies, organization, mailing lists, and interest groups.

  2. Present status of Japanese Criticality Safety Handbook

    International Nuclear Information System (INIS)

    Okuno, Hiroshi

    1999-01-01

    A draft of the second edition of Nuclear Criticality Safety Handbook has been finalized, and it is under examination by reviewing committee for JAERI Report. Working Group designated for revising the Japanese Criticality Safety Handbook, which is chaired by Prof. Yamane, is now preparing for 'Guide on Burnup Credit for Storage and Transport of Spent Nuclear Fuel' and second edition of 'Data Collection' part of Handbook. Activities related to revising the Handbook might give a hint for a future experiment at STACY. (author)

  3. How explicit and implicit test instructions in an implicit learning task affect performance.

    Directory of Open Access Journals (Sweden)

    Arnaud Witt

    Full Text Available Typically developing children aged 5 to 8 years were exposed to artificial grammar learning. Following an implicit exposure phase, half of the participants received neutral instructions at test while the other half received instructions making a direct, explicit reference to the training phase. We first aimed to assess whether implicit learning operated in the two test conditions. We then evaluated the differential impact of age on learning performances as a function of test instructions. The results showed that performance did not vary as a function of age in the implicit instructions condition, while age effects emerged when explicit instructions were employed at test. However, performance was affected differently by age and the instructions given at test, depending on whether the implicit learning of short or long units was assessed. These results suggest that the claim that the implicit learning process is independent of age needs to be revised.

  4. Recent developments in the IAEA safety standards: design and operation of nuclear power plants

    International Nuclear Information System (INIS)

    Saito, Takehiko

    2004-01-01

    The IAEA has been publishing a wide variety of safety standards for nuclear and radiation related facilities and activities since 1978. In 1996, a more rigorously structured approach for the preparation and review of its safety standards was introduced. Currently, based on the approach, revision of most of the standards is in completion or near completion. The latest versions of the Safety Requirements for ''Design'' and ''Operation'' of nuclear power plants were respectively published in 2000. Currently, along with this revision of the Safety Requirements, many Safety Guides have been revised. In order to clarify the complicated revision procedure, an example of the entire revision process for a Safety Guide is provided. Through actual example of the revision process, enormous amount of work involved in the revision work is clearly indicated. The current status of all of the Safety Standards for Design and that for Operation of nuclear power plants are summarized. Summary of other IAEA safety standards currently revised and available related IAEA publications, together with information on the IAEA Web Site from where these documents can be downloaded, is also provided. The standards are reviewed to determine whether revision (or new issue) is necessary in five years following publication. The IAEA safety standards will continue to be updated through comprehensive and structured approach, collaboration of many experts of the world, and reflecting good practices of the world. The IAEA safety standards will serve to provide high level of safety assurance. (author)

  5. At-risk children's use of reflection and revision in hands-on experimental activities

    Science.gov (United States)

    Petrosino, Anthony J., Jr.

    The goal of this study was to investigate the effects of incorporating opportunities for reflection and revision in hands-on science instruction which emphasized experimentation using model rockets. The participants were low achieving sixth grade summer school students (n = 23) designated as at-risk for school failure by their district. The group was asked a series of interview questions based on work by Schauble et al. (1995) relating to experimentation. The interviews took place over three distinct time points corresponding to a "hands-on only" condition, a "hands-on with reflection and revision" condition and a "hands-on with repeated reflection and revision" condition. A Friedman's Two-Way Analysis of Variance by Ranks indicate students score low at first with traditional hands-on instruction but improve significantly with opportunities to reflect and revise their experiments. In addition, a sociocultural analysis was conducted during the summer school session to assess the model rocket activity as an apprenticeship, as guided participation and as participatory appropriation using a framework established by Rogoff (1994). Finally, a survey (the Classroom Environment Survey) was administered to the students measuring five constructs consistent with a constructivist classroom: participation, autonomy, relevance, commitment to learning and disruptions to learning. Analysis indicate students in the summer school model rocket intervention experienced a greater sense of constructivist principles during the activity than a similar comparison group utilizing reform minded instruction but not including opportunities for reflection and revision cycles. This research provides important evidence that, like scientists, students in school can learn effectively from extended practice in a varied context. Importantly, the data indicate that hands-on instruction is best utilized when opportunities for reflection and revision are made explicit. Implications are discussed related

  6. Safety Management at PUSPATI TRIGA Reactor (RTP)

    International Nuclear Information System (INIS)

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

    2011-01-01

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

  7. 77 FR 13997 - Revising Standards Referenced in the Acetylene Standard

    Science.gov (United States)

    2012-03-08

    ...: Occupational Safety and Health Administration (OSHA), Labor. ACTION: Proposed rule; withdrawal. SUMMARY: With this document, OSHA is withdrawing the proposed rule that accompanied its direct-final rule revising... and press inquiries: Contact Frank Meilinger, Director, OSHA Office of Communications, Room N-3647, U...

  8. 75 FR 5707 - Revising Standards Referenced in the Acetylene Standard

    Science.gov (United States)

    2010-02-04

    ...: Occupational Safety and Health Administration (OSHA), Labor. ACTION: Proposed rule; withdrawal. SUMMARY: With this document, OSHA is withdrawing the proposed rule that accompanied its direct-final rule revising... and press inquiries: Contact Jennifer Ashley, Director, OSHA Office of Communications, Room N-3647, U...

  9. Safety system status monitoring

    International Nuclear Information System (INIS)

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

    1984-03-01

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

  10. Safety system status monitoring

    Energy Technology Data Exchange (ETDEWEB)

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

    1984-03-01

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

  11. Safety assessment principles for nuclear plants

    International Nuclear Information System (INIS)

    1992-01-01

    The present Safety Assessment Principles result from the revision of those which were drawn up following a recommendation arising from the Sizewell-B enquiry. The principles presented here relate only to nuclear safety; there is a section on risks from normal operation and accident conditions and the standards against which those risks are assessed. A major part of the document deals with the principles that cover the design of nuclear plants. The revised Safety assessment principles are aimed primarily at the safety assessment of new nuclear plants but they will also be used in assessing existing plants. (UK)

  12. Playground Safety

    Science.gov (United States)

    ... Prevention Fall Prevention Playground Safety Poisoning Prevention Road Traffic Safety Sports Safety Get Email Updates To receive ... at the Consumer Product Safety Commission’s Playground Safety website . References U.S. Consumer Product Safety Commission. Injuries and ...

  13. Impending revision of the euratom treaty

    International Nuclear Information System (INIS)

    Fahl, G.

    1979-01-01

    The decision by the European Court of Justice in the matter of the EEC's participation in international negotiations on safety problems of the nuclear fuel cycle is of basic importance, beyond the case to which it referred, in the interpretation of the respective provisions of the Euratom Treaty in the nuclear fuel sector. The reasoning of the European Court of Justice, which constitutes a reinforcement and advancement of the responsibilities and rights of the EEC, has made France ask for a revision of the Treaty. (orig.) [de

  14. Technical specification optimization program - engineered safety features

    International Nuclear Information System (INIS)

    Andre, G.R.; Jansen, R.L.

    1986-01-01

    The Westinghouse Technical Specification Program (TOP) was designed to evaluate on a quantitative basis revisions to Nuclear Power Plant Technical Specifications. The revisions are directed at simplifying plant operation, and reducing unnecessary transients, shutdowns, and manpower requirements. In conjunction with the Westinghouse Owners Group, Westinghouse initiated a program to develop a methodology to justify Technical Specification revisions; particularly revisions related to testing and maintenance requirements on plant operation for instrumentation systems. The methodology was originally developed and applied to the reactor trip features of the reactor protection system (RPS). The current study further refined the methodology and applied it to the engineered safety features of the RPS

  15. Project SAFE. Update of the SFR-1 safety assessment. Phase 1. Appendix A5: Radionuclide transport

    International Nuclear Information System (INIS)

    Moreno, L.

    1998-01-01

    A critical revision of the previous safety assessments made by SKB on the Final Repository for Radioactive Operational Waste, SFR is presented. The review of the Deepened Safety Assessment is also discussed. Based on this critical revision improvements are suggested. Hydrology, formation of complexes, and long-term behaviour of the barriers are some of the aspects where the safety assessment could be improved

  16. Planning and Revising Written Arguments: The Effects of Two Text Structure-Based Interventions on Persuasiveness of 8th-Grade Students' Essays

    Science.gov (United States)

    Midgette, Ekaterina; Haria, Priti

    2016-01-01

    The purpose of the study was to investigate the effects of two comprehensive argumentative writing interventions--Text Structure Instruction (TSI) and Text Structure Revision Instruction (TSRI)--on the eighth-grade students' ability to compose convincing essays that include structural elements of argumentative discourse. Both treatment groups…

  17. Handbook of laboratory health and safety measures

    International Nuclear Information System (INIS)

    Pal, S.B.

    1985-01-01

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

  18. Inclusive differentiated instruction

    Directory of Open Access Journals (Sweden)

    Jerković Ljiljana S.

    2017-01-01

    Full Text Available Inclusive differentiated instruction is a new model of didactic instruction, theoretically described and established in this paper for the first time, after being experimentally verified through teaching of the mother tongue (instruction in reading and literature. Inclusive individually planned instruction is based on a phenomenological and constructivist didactic instructional paradigm. This type of teaching is essentially developmental and person-oriented. The key stages of inclusive differentiated instruction of literature are: 1 recognition of individual students' potential and educational needs regarding reading and work on literary texts; 2 planning and preparation of inclusive individually planned instruction in reading and literature; 3 actual class teaching of lessons thus prepared; and 4 evaluation of the student achievement following inclusive differentiated instruction in reading and literature. A highly important element of the planning and preparation of inclusive differentiated instruction is the creation of student profiles and inclusive individualized syllabi. Individualized syllabi specify the following: 1. a brief student profile; 2. the student position on the continuum of the learning outcomes of instruction in the Serbian language; 3. reverse-engineered macro-plan stages of instruction in the Serbian language (3.1. identifying expected outcomes and fundamental qualities of learners' work, 3.2. defining acceptable proofs of their realisation, 3.3. planning learning and teaching experiences, and 3.4. providing material and technical requisites for teaching; 4 the contents and procedure of individualized lessons targeting the student; 5 a plan of syllabus implementation monitoring and evaluation. The continuum of the learning outcomes of inclusive differentiated instruction in literature exists at three main levels, A, B and C. The three levels are: A reading techniques and learning about the main literary theory concepts; B

  19. Safety indicators: an efficient tool for a better safety

    International Nuclear Information System (INIS)

    Aufort, P.; Lars, R.

    1993-01-01

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

  20. The Bulimia Test--Revised: Validation with "DSM-IV" Criteria for Bulimia Nervosa.

    Science.gov (United States)

    Thelen, Mark H.; And Others

    1996-01-01

    The Bulimia Test--Revised (BULIT-R) was given to 23 female subjects who met the criteria for bulimia in the "Diagnostic and Statistical Manual of Mental Disorders" (DSM-IV) and 124 female controls. The BULIT-R appears to be a valid instruction for identifying individuals who meet DSM-IV criteria for bulimia. (SLD)

  1. Smart Meters in the Netherlands. Revised financial analysis and policy advice

    International Nuclear Information System (INIS)

    Van Gerwen, R.; Koenis, F.; Schrijner, M.; Widdershoven, G.

    2010-07-01

    Ministry of Economic Affairs, Agriculture and Innovation (ELI) has instructed KEMA to perform a revised cost-benefit analysis to gain insight into the consequences of the changed circumstances with respect to the business case for the introduction of smart meters in the Netherlands.

  2. Cutting through the Hype: The Essential Guide to School Reform. Revised, Expanded, and Updated Edition

    Science.gov (United States)

    David, Jane L.; Cuban, Larry

    2010-01-01

    "Cutting Through the Hype: The Essential Guide to School Reform" is a revised, expanded, and updated version of the classic work by Jane L. David and Larry Cuban. It offers balanced analyses of 23 currently popular school reform strategies, from teacher performance pay and putting mayors in charge to turnaround schools and data-driven instruction.…

  3. Revised inspection program for nuclear power plants

    International Nuclear Information System (INIS)

    1978-01-01

    The United States Nuclear Regulatory Commission (NRC) regulates nuclear power plants to assure adequate protection of the public and the environment from the dangers associated with nuclear materials. NRC fulfills this responsibility through comprehensive safety reviews of nuclear facilities, licensing of organizations that use nuclear materials, and continuing inspection. The NRC inspection program is currently conducted from the five regional offices in or near Philadelphia, Atlanta, Chicago, Dallas and San Francisco. Inspectors travel from the regional offices to nuclear power plants in various phases of construction, test and operation in order to conduct inspections. However, in June 1977 the Commission approved a revision to the inspection program that will include stationing inspectors at selected plants under construction and at all plants in operation. In addition, the revised program provides for appraising the performance of licensees on a national basis and involves more direct measurement and observation by NRC inspectors of work and tests in progress. The program also includes enhanced career management consisting of improved training and career development for inspectors and other professionals. The report was requested in the Conference Report on the NRC Authorization for Appropriations for Fiscal Year 1978. The report provides a discussion of the basis for both the current and revised inspection programs, describes these programs, and shows how the NRC inspection force will be trained and utilized. In addition, the report includes a discussion of the actions that will be taken to assure the objectivity of inspectors

  4. IAEA Issues Report on Mission to Review Japan's Nuclear Power Plant Safety Assessment Process

    International Nuclear Information System (INIS)

    2012-01-01

    Full text: A team of international nuclear safety experts has delivered its report on a mission it conducted from 21-31 January 2012 to review Japan's process for assessing nuclear safety at the nation's nuclear power plants. International Atomic Energy Agency (IAEA) officials delivered the IAEA Mission Report to Japanese officials yesterday and made it publicly available today. Following the 11 March 2011 accident at TEPCO's Fukushima Daiichi Nuclear Power Station, Japan's Nuclear and Industrial Safety Agency (NISA) announced the development of a revised safety assessment process for the nation's nuclear power reactors. At the request of the Government of Japan, the IAEA organized a team of five IAEA and three international nuclear safety experts and visited Japan to review NISA's approach to the Comprehensive Assessments for the Safety of Existing Power Reactor Facilities and how NISA examines the results submitted by nuclear operators. A Preliminary Summary Report was issued on 31 January. 'The mission report provides additional information regarding the team's recommendations and overall finding that NISA's instructions to power plants and its review process for the Comprehensive Safety Assessments are generally consistent with IAEA Safety Standards', said team leader James Lyons, Director of the IAEA's Nuclear Installation Safety Division. National safety assessments and their peer review by the IAEA are a key component of the IAEA Action Plan on Nuclear Safety, which was approved by the Agency's Member States following last year's nuclear accident at Fukushima Daiichi Nuclear Power Station. The IAEA safety review mission held meetings in Tokyo with officials from NISA, the Japanese Nuclear Energy Safety Organization (JNES), and the Kansai Electric Power Company (KEPCO), and the team visited the Ohi Nuclear Power Station to see an example of how Japan's Comprehensive Safety Assessment is being implemented by nuclear operators. In its report delivered today

  5. RB research reactor Safety Report

    International Nuclear Information System (INIS)

    Sotic, O.; Pesic, M.; Vranic, S.

    1979-04-01

    This RB reactor safety report is a revised and improved version of the Safety report written in 1962. It contains descriptions of: reactor building, reactor hall, control room, laboratories, reactor components, reactor control system, heavy water loop, neutron source, safety system, dosimetry system, alarm system, neutron converter, experimental channels. Safety aspects of the reactor operation include analyses of accident causes, errors during operation, measures for preventing uncontrolled activity changes, analysis of the maximum possible accident in case of different core configurations with natural uranium, slightly and highly enriched fuel; influence of possible seismic events

  6. Library Instruction for Freshman English: A Multi-Year Assessment of Student Learning

    Directory of Open Access Journals (Sweden)

    Susan Gardner Archambault

    2011-01-01

    Full Text Available Objective – The objective of this study was twofold: 1 to assess the effectiveness of curriculum changes made from the 2009 freshman English library instruction curriculum to the 2010 curriculum at Loyola Marymount University (LMU; and 2 to evaluate the effectiveness of library instruction delivered via a “blended” combination of face-to-face and online instruction versus online instruction alone.Methods – An experimental design compared random samples of student scores from 2009 and 2010 worksheets to determine the effects of a new curriculum on student learning. A second experiment examined the effect of delivery method on student learning by comparing scores from a group of students receiving only online instruction against a group receiving blended instruction.Results – The first component of the study, which compared scores between 2009 and 2010 to examine the effects of the curriculum revisions, had mixed results. Students scored a significantly higher mean in 2010 on completing and correctly listing book citation components than in 2009, but a significantly lower mean on constructing a research question. There was a significant difference in the distribution of scores for understanding differences between information found on the Internet versus through the Library that was better in 2010 than 2009, but worse for narrowing a broad research topic. For the study that examined computer aided instruction, the group of students receiving only computer-assisted instruction did significantly better overall than the group receiving blended instruction. When separate tests were run for each skill, two particular skills, generating keywords and completing book citation and location elements, resulted in a significantly higher mean.Conclusions – The comparison of scores between 2009 and 2010 were mixed, but the evaluation process helped us identify continued problems in the teaching materials to address in the next cycle of revisions

  7. Death Penalty Decisions: Instruction Comprehension, Attitudes, and Decision Mediators.

    Science.gov (United States)

    Patry, Marc W; Penrod, Steven D

    2013-01-01

    A primary goal of this research was to empirically evaluate a set of assumptions, advanced in the Supreme Court's ruling in Buchanan v. Angelone (1998), about jury comprehension of death penalty instructions. Further, this research examined the use of evidence in capital punishment decision making by exploring underlying mediating factors upon which death penalty decisions may be based. Manipulated variables included the type of instructions and several variations of evidence. Study 1 was a paper and pencil study of 245 undergraduate mock jurors. The experimental design was an incomplete 4×2×2×2×2 factorial model resulting in 56 possible conditions. Manipulations included four different types of instructions, presence of a list of case-specific mitigators to accompany the instructions, and three variations in the case facts: age of the defendant, bad prior record, and defendant history of emotional abuse. Study 2 was a fully-crossed 2×2×2×2×2 experiment with four deliberating mock juries per cell. Manipulations included jury instructions (original or revised), presence of a list of case-specific mitigators, defendant history of emotional abuse, bad prior record, and heinousness of the crime. The sample of 735 jury-eligible participants included 130 individuals who identified themselves as students. Participants watched one of 32 stimulus videotapes based on a replication of a capital sentencing hearing. The present findings support previous research showing low comprehension of capital penalty instructions. Further, we found that higher instruction comprehension was associated with higher likelihood of issuing life sentence decisions. The importance of instruction comprehension is emphasized in a social cognitive model of jury decision making at the sentencing phase of capital cases.

  8. Safety in the Chemical Laboratory: Safety in the Chemistry Laboratories: A Specific Program.

    Science.gov (United States)

    Corkern, Walter H.; Munchausen, Linda L.

    1983-01-01

    Describes a safety program adopted by Southeastern Louisiana University. Students are given detailed instructions on laboratory safety during the first laboratory period and a test which must be completely correct before they are allowed to return to the laboratory. Test questions, list of safety rules, and a laboratory accident report form are…

  9. Millwright Apprenticeship. Related Training Modules. 1.1-1.8 Safety.

    Science.gov (United States)

    Lane Community Coll., Eugene, OR.

    This packet, part of the instructional materials for the Oregon apprenticeship program for millwright training, contains eight modules covering safety. The modules provide information on the following topics: general safety, hand tool safety, power tool safety, fire safety, hygiene, safety and electricity, types of fire and fire prevention, and…

  10. Council directive of 1 June 1976 laying down the revised basic safety standards for the health protection of the general public and workers against the dangers of ionizing radiation

    International Nuclear Information System (INIS)

    1977-01-01

    As provided for in the Euratom Treaty, and in particular Article 30 thereof, basic standards for the protection of the health of workers and the general public against the dangers arising from ionizing radiations, must be established to enable each Member State in accordance with Article 33 of the Euratom Treaty to lay down provisions by legislation, regulation or administrative action to ensure compliance with each standards, to take the necessary measures with regard to teaching, education and vocational training and to make these provisions in harmony with the provisions applicable in this field in the other Member States. On 2 February 1959, the Council has adopted a directive establishing basic safety standards. These were modified partially by the directives of 5 March 1962 and 27 October 1966. The present edition reproduces the complete text of the directive amending the basic safety standards for the health protection of the population and work against the dangers of ionizing radiation adopted by the Council on 31 May 1976. These new standards take into consideration the increasing scientific knowledge in the fields of radiological protection and radiobiology and the practical experience of applying these directives in national laws

  11. Respiratory protection standard: comments on OSHA's proposed revision.

    Science.gov (United States)

    Decker, M D

    1995-06-01

    On November 15, 1994, the Occupational Safety and Health Administration (OSHA) published in the Federal Register (59:58884-58956) the draft of a proposed revision of the Respiratory Protection Standard. One of OSHA's oldest standards, the Respiratory Protection Standard defines the conduct of the employer (eg, hospital) with respect to respirator training, fit testing, medical examinations, use, storage, and so on. The proposed revision appears to have been drafted with no consideration for its effect on healthcare workers or the healthcare industry. SHEA has prepared the following comments to OSHA, which have been submitted to the docket and will be presented at public hearings later this month.

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

    International Nuclear Information System (INIS)

    1986-11-01

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

  13. Industrial hazard and safety handbook

    CERN Document Server

    King, Ralph W

    1979-01-01

    Industrial Hazard and Safety Handbook (Revised Impression) describes and exposes the main hazards found in industry, with emphasis on how these hazards arise, are ignored, are identified, are eliminated, or are controlled. These hazard conditions can be due to human stresses (for example, insomnia), unsatisfactory working environments, as well as secret industrial processes. The book reviews the cost of accidents, human factors, inspections, insurance, legal aspects, planning for major emergencies, organization, and safety measures. The text discusses regulations, codes of practice, site layou

  14. Safety study application guide

    International Nuclear Information System (INIS)

    1993-07-01

    Martin Marietta Energy Systems, Inc., (Energy Systems) is committed to performing and documenting safety analyses for facilities it manages for the Department of Energy (DOE). Included are analyses of existing facilities done under the aegis of the Safety Analysis Report Upgrade Program, and analyses of new and modified facilities. A graded approach is used wherein the level of analysis and documentation for each facility is commensurate with the magnitude of the hazard(s), the complexity of the facility and the stage of the facility life cycle. Safety analysis reports (SARs) for hazard Category 1 and 2 facilities are usually detailed and extensive because these categories are associated with public health and safety risk. SARs for Category 3 are normally much less extensive because the risk to public health and safety is slight. At Energy Systems, safety studies are the name given to SARs for Category 3 (formerly open-quotes lowclose quotes) facilities. Safety studies are the appropriate instrument when on-site risks are limited to irreversible consequences to a few people, and off-site consequences are limited to reversible consequences to a few people. This application guide provides detailed instructions for performing safety studies that meet the requirements of DOE Orders 5480.22, open-quotes Technical Safety Requirements,close quotes and 5480.23, open-quotes Nuclear Safety Analysis Reports.close quotes A seven-chapter format has been adopted for safety studies. This format allows for discussion of all the items required by DOE Order 5480.23 and for the discussions to be readily traceable to the listing in the order. The chapter titles are: (1) Introduction and Summary, (2) Site, (3) Facility Description, (4) Safety Basis, (5) Hazardous Material Management, (6) Management, Organization, and Institutional Safety Provisions, and (7) Accident Analysis

  15. Safety assessment and verification for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2001-01-01

    This publication supports the Safety Requirements on the Safety of Nuclear Power Plants: Design. This Safety Guide was prepared on the basis of a systematic review of all the relevant publications including the Safety Fundamentals, Safety of Nuclear Power Plants: Design, current and ongoing revisions of other Safety Guides, INSAG reports and other publications that have addressed the safety of nuclear power plants. This Safety Guide also provides guidance for Contracting Parties to the Convention on Nuclear Safety in meeting their obligations under Article 14 on Assessment and Verification of Safety. The Safety Requirements publication entitled Safety of Nuclear Power Plants: Design states that a comprehensive safety assessment and an independent verification of the safety assessment shall be carried out before the design is submitted to the regulatory body. This publication provides guidance on how this requirement should be met. This Safety Guide provides recommendations to designers for carrying out a safety assessment during the initial design process and design modifications, as well as to the operating organization in carrying out independent verification of the safety assessment of new nuclear power plants with a new or already existing design. The recommendations for performing a safety assessment are suitable also as guidance for the safety review of an existing plant. The objective of reviewing existing plants against current standards and practices is to determine whether there are any deviations which would have an impact on plant safety. The methods and the recommendations of this Safety Guide can also be used by regulatory bodies for the conduct of the regulatory review and assessment. Although most recommendations of this Safety Guide are general and applicable to all types of nuclear reactors, some specific recommendations and examples apply mostly to water cooled reactors. Terms such as 'safety assessment', 'safety analysis' and 'independent

  16. Apparel. Teacher's Instructional Guide.

    Science.gov (United States)

    Rambo, Patti

    This instructional guide for a one-half credit technological laboratory course for grades 10-12 focuses on apparel from the perspectives of personal decision making related to apparel, the apparel industry, and career preparation. Introductory materials are a course description; overview of course design; facilities, equipment, and resources; and…

  17. Instructional Guidelines. Welding.

    Science.gov (United States)

    Fordyce, H. L.; Doshier, Dale

    Using the standards of the American Welding Society and the American Society of Mechanical Engineers, this welding instructional guidelines manual presents a course of study in accordance with the current practices in industry. Intended for use in welding programs now practiced within the Federal Prison System, the phases of the program are…

  18. Windows into Instructional Practice

    Science.gov (United States)

    Steinbacher-Reed, Christina; Rotella, Sam A.

    2017-01-01

    Administrators are often removed from the daily instructional realities in classrooms, while teachers aren't given enough opportunities to lead in their schools, write Christina Steinbacher-Reed and Sam A. Rotella Jr. The result is a wall that prevents the two parties from collaborating in a way that improves school culture, teaching practices,…

  19. INSTRUCTIONAL MATERIALS CATALOG.

    Science.gov (United States)

    Ohio Vocational Agriculture Instructional Materials Service, Columbus.

    THE TITLE, IDENTIFICATION NUMBER, DATE OF PUBLICATION, PAGINATION, A BRIEF DESCRIPTION, AND PRICE ARE GIVEN FOR EACH OF THE INSTRUCTIONAL MATERIALS AND AUDIOVISUAL AIDS INCLUDED IN THIS CATALOG. TOPICS COVERED ARE FIELD CORPS, HORTICULTURE, ANIMAL SCIENCE, SOILS, AGRICULTURAL ENGINEERING, AND FARMING PROGRAMS. AN ORDER FORM IS INCLUDED. (JM)

  20. Computers in writing instruction

    NARCIS (Netherlands)

    Schwartz, Helen J.; van der Geest, Thea; Smit-Kreuzen, Marlies

    1992-01-01

    For computers to be useful in writing instruction, innovations should be valuable for students and feasible for teachers to implement. Research findings yield contradictory results in measuring the effects of different uses of computers in writing, in part because of the methodological complexity of

  1. Gaze Interactive Building Instructions

    DEFF Research Database (Denmark)

    Hansen, John Paulin; Ahmed, Zaheer; Mardanbeigi, Diako

    We combine eye tracking technology and mobile tablets to support hands-free interaction with digital building instructions. As a proof-of-concept we have developed a small interactive 3D environment where one can interact with digital blocks by gaze, keystroke and head gestures. Blocks may be moved...

  2. Job Instruction Training.

    Science.gov (United States)

    Pfau, Richard H.

    Job Instruction Training (JIT) is a step-by-step, relatively simple technique used to train employees on the job. It is especially suitable for teaching manual skills or procedures; the trainer is usually an employee's supervisor but can be a co-worker. The JIT technique consists of a series of steps that a supervisor or other instructor follows…

  3. Nuclear Energy. Instructional Materials.

    Science.gov (United States)

    Jordan, Kenneth; Thessing, Dan

    This document is one of five learning packets on alternative energy (see note) developed as part of a descriptive curriculum research project in Arkansas. The overall objectives of the learning packets are to improve the level of instruction in the alternative energies by vocational exploration teachers, and to facilitate the integration of new…

  4. Wind Power. Instructional Materials.

    Science.gov (United States)

    Jordan, Kenneth; Thessing, Dan

    This document is one of five learning packets on alternative energy developed as part of a descriptive curriculum research project in Arkansas (see note). The overall objectives of the learning packets are to improve the level of instruction in the alternative energies by vocational exploration teachers, and to facilitate the integration of new…

  5. Instructional Psychology 1976 - 1981,

    Science.gov (United States)

    1982-06-01

    business it is to carry out applied work in the design of instructional content and delivery. These organizations include specialized divisions of...34learning disabilities" label: An experimental analysis. Comtemporary Educational Psychology, 1977, 2, 292-297. Allington, R. L. Sensitivity to

  6. Reviews in instructional video

    NARCIS (Netherlands)

    van der Meij, Hans

    2017-01-01

    This study investigates the effectiveness of a video tutorial for software training whose construction was based on a combination of insights from multimedia learning and Demonstration-Based Training. In the videos, a model of task performance was enhanced with instructional features that were

  7. Computer-assisted instruction

    NARCIS (Netherlands)

    Voogt, J.; Fisser, P.; Wright, J.D.

    2015-01-01

    Since the early days of computer technology in education in the 1960s, it was claimed that computers can assist instructional practice and hence improve student learning. Since then computer technology has developed, and its potential for education has increased. In this article, we first discuss

  8. Scaffolding in Assisted Instruction

    Directory of Open Access Journals (Sweden)

    2007-01-01

    Full Text Available On-The-Job Training, developed as direct instruction, is one of the earliest forms of training. This method is still widely in use today because it requires only a person who knows how to do the task, and the tools the person uses to do the task. This paper is intended to be a study of the methods used in education in Knowledge Society, with more specific aspects in training the trainers; as a result of this approach, it promotes scaffolding in assisted instruction as a reflection of the digital age for the learning process. Training the trainers in old environment with default techniques and designing the learning process in assisted instruction, as an application of the Vygotskian concept of the zone of proximal development (ZPD to the area of computer literacy for the younger users, generate diversity in educational communities and requires standards for technology infrastructure, standards for the content, developed as a concepts map, and applications for personalized in-struction, based on ZPD theory.

  9. Characteristics of Instructional Videos

    Science.gov (United States)

    Beheshti, Mobina; Taspolat, Ata; Kaya, Omer Sami; Sapanca, Hamza Fatih

    2018-01-01

    Nowadays, video plays a significant role in education in terms of its integration into traditional classes, the principal delivery system of information in classes particularly in online courses as well as serving as a foundation of many blended classes. Hence, education is adopting a modern approach of instruction with the target of moving away…

  10. Facility transition instruction

    International Nuclear Information System (INIS)

    Morton, M.R.

    1997-01-01

    The Bechtel Hanford, Inc. facility transition instruction was initiated in response to the need for a common, streamlined process for facility transitions and to capture the knowledge and experience that has accumulated over the last few years. The instruction serves as an educational resource and defines the process for transitioning facilities to long-term surveillance and maintenance (S and M). Generally, these facilities do not have identified operations missions and must be transitioned from operational status to a safe and stable configuration for long-term S and M. The instruction can be applied to a wide range of facilities--from process canyon complexes like the Plutonium Uranium Extraction Facility or B Plant, to stand-alone, lower hazard facilities like the 242B/BL facility. The facility transition process is implemented (under the direction of the US Department of Energy, Richland Operations Office [RL] Assistant Manager-Environmental) by Bechtel Hanford, Inc. management, with input and interaction with the appropriate RL division and Hanford site contractors as noted in the instruction. The application of the steps identified herein and the early participation of all organizations involved are expected to provide a cost-effective, safe, and smooth transition from operational status to deactivation and S and M for a wide range of Hanford Site facilities

  11. Paratransit: An Instructional Module.

    Science.gov (United States)

    Scalici, Anthony

    A concept-based introduction to paratransit is provided in this instructional module for undergraduate and graduate transportation-related courses for disciplines such as engineering, business, marketing, and technology. The concept of paratransit generally refers to modes of transportation other than mass transit and solo-driven automobiles. The…

  12. Listening strategies instruction

    DEFF Research Database (Denmark)

    Nogueroles López, Marta

    2017-01-01

    , who presented similar level of Spanish, needs, educational and cultural background, but did not receive such a training. The listening strategies instruction consisted in integrating the development of listening strategies into a regular course of Spanish as a foreign language. Data referring...

  13. Inquiry-Oriented Instruction: A Conceptualization of the Instructional Principles

    Science.gov (United States)

    Kuster, George; Johnson, Estrella; Keene, Karen; Andrews-Larson, Christine

    2018-01-01

    Research has highlighted that inquiry-based learning (IBL) instruction leads to many positive student outcomes in undergraduate mathematics. Although this research points to the value of IBL instruction, the practices of IBL instructors are not well-understood. Here, we offer a characterization of a particular form of IBL instruction:…

  14. Safety of nuclear power plants: Operation. Safety requirements

    International Nuclear Information System (INIS)

    2004-01-01

    The safety of a nuclear power plant is ensured by means of its proper siting, design, construction and commissioning, followed by the proper management and operation of the plant. In a later phase, proper decommissioning is required. This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Operation, which was issued in 1988 as Safety Series No. 50-C-O (Rev. 1). The purpose of this revision was: to restructure Safety Series No. 50-C-O (Rev. 1) in the light of the basic objectives, concepts and principles in the Safety Fundamentals publication The Safety of Nuclear Installations. To be consistent with the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. And to reflect current practice and new concepts and technical developments. Guidance on fulfillment of these Safety Requirements may be found in the appropriate Safety Guides relating to plant operation. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the basic objectives, concepts and principles that are presented in the Safety Fundamentals publication The Safety of Nuclear Installations. This publication deals with matters specific to the safe operation of land based stationary thermal neutron nuclear power plants, and also covers their commissioning and subsequent decommissioning

  15. Safety of nuclear power plants: Operation. Safety requirements

    International Nuclear Information System (INIS)

    2003-01-01

    The safety of a nuclear power plant is ensured by means of its proper siting, design, construction and commissioning, followed by the proper management and operation of the plant. In a later phase, proper decommissioning is required. This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Operation, which was issued in 1988 as Safety Series No. 50-C-O (Rev. 1). The purpose of this revision was: to restructure Safety Series No. 50-C-O (Rev. 1) in the light of the basic objectives, concepts and principles in the Safety Fundamentals publication The Safety of Nuclear Installations. To be consistent with the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. And to reflect current practice and new concepts and technical developments. Guidance on fulfillment of these Safety Requirements may be found in the appropriate Safety Guides relating to plant operation. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the basic objectives, concepts and principles that are presented in the Safety Fundamentals publication The Safety of Nuclear Installations. This publication deals with matters specific to the safe operation of land based stationary thermal neutron nuclear power plants, and also covers their commissioning and subsequent decommissioning

  16. Safety of nuclear power plants: Operation. Safety requirements

    International Nuclear Information System (INIS)

    2000-01-01

    The safety of a nuclear power plant is ensured by means of its proper siting, design, construction and commissioning, followed by the proper management and operation of the plant. In a later phase, proper decommissioning is required. This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Operation, which was issued in 1988 as Safety Series No. 50-C-O (Rev. 1). The purpose of this revision was: to restructure Safety Series No. 50-C-O (Rev. 1) in the light of the basic objectives, concepts and principles in the Safety Fundamentals publication The Safety of Nuclear Installations; to be consistent with the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources; and to reflect current practice and new concepts and technical developments. Guidance on fulfillment of these Safety Requirements may be found in the appropriate Safety Guides relating to plant operation. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the basic objectives, concepts and principles that are presented in the Safety Fundamentals publication The Safety of Nuclear Installations. This publication deals with matters specific to the safe operation of land based stationary thermal neutron nuclear power plants, and also covers their commissioning and subsequent decommissioning

  17. The Librarian Leading the Machine: A Reassessment of Library Instruction Methods

    Science.gov (United States)

    Greer, Katie; Hess, Amanda Nichols; Kraemer, Elizabeth W.

    2016-01-01

    This article builds on the 2007 College and Research Libraries article, "The Librarian, the Machine, or a Little of Both." Since that time, Oakland University Libraries implemented changes to its instruction program that reflect larger trends in teaching and assessment throughout the profession; following these revisions, librarians…

  18. How School Principals Can Foster Effective Literacy Instruction: A Ten-Step Plan

    Science.gov (United States)

    Hinchman, Kathleen A.

    2009-01-01

    School principals can foster effective literacy instruction by orchestrating community collaboration in an ongoing cycle of literacy program development, implementation, evaluation, and revision outlined in this ten-step plan. The steps address forming a community advisory board, appointing a building literacy leader, forming a literacy team,…

  19. Evaluating Writing Instruction through an Investigation of Students' Experiences of Learning through Writing

    Science.gov (United States)

    Ellis, Robert A.; Taylor, Charlotte E.; Drury, Helen

    2005-01-01

    Learning through writing is a way of learning not only the appropriate written expression of disciplinary knowledge, but also the knowledge itself through reflection and revision. This study investigates the quality of a writing experience provided to university students in a first-year biology subject. The writing instruction methodology used is…

  20. Testing the Usability of a Portable DVD Player and Tailored Photo Instructions with Older Adult Veterans

    Science.gov (United States)

    Gould, Christine E.; Zapata, Aimee Marie L.; Shinsky, Deanna N.; Goldstein, Mary K.

    2018-01-01

    DVD-delivered behavioral skills training may help disseminate efficacious treatments to older adults independent of internet access. The present study examined the usability of a portable DVD player alongside iterative revisions of accompanying instructions to be used by older adults in a DVD-delivered behavioral skills treatment study. The sample…

  1. The Effect of Topical Structure Analysis Instruction on University Students' Writing Quality

    Science.gov (United States)

    Liangprayoon, Somlak; Chaya, Walaiporn; Thep-ackraphong, Tipa

    2013-01-01

    Coherence is considered one of the characteristics of effective writing. Topical structure analysis (TSA) has been taught to students as a revision strategy to raise their awareness of importance of textual coherence and helps them clearly understand its concept. This study aimed to investigate the effectiveness of TSA instruction in improving…

  2. Revised Rules for Concrete Bridges

    DEFF Research Database (Denmark)

    Thoft-Christensen, Palle; Jensen, F. M.; Middleton, C.

    This paper is based on research performed for the Highway Agency, London, UK under the project DPU/9/44 "Revision of Bridge Assessment Rules Based on Whole Life Performance: Concrete Bridges" It contains details of a methodology which can be used to generate Whole Life (WL) reliability profiles....... These WL reliability profiles may be used to establish revised rules for Concrete Bridges....

  3. Emotion Processes in Knowledge Revision

    Science.gov (United States)

    Trevors, Gregory J.; Kendeou, Panayiota; Butterfuss, Reese

    2017-01-01

    In recent years, a number of insights have been gained into the cognitive processes that explain how individuals overcome misconceptions and revise their previously acquired incorrect knowledge. The current study complements this line of research by investigating the moment-by-moment emotion processes that occur during knowledge revision using a…

  4. The Nuclear Safety Council's Instruction IS-30 on program requirements of fire protection at nuclear power plants; La instruccion IS-30 del consejo de Seguridad Nuclear sobre requisitos del programa de proteccion contraincendios en centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Peco, J.

    2015-07-01

    The Nuclear Safety Councils Instrumentation IS-30 is the standard that establishes the fire protection program requirements for the Spanish nuclear power plants with operating license in order to satisfy the two fire protection objectives, which are the adoption of the defense-in-depth principle for fire protection and, by fire area confinement, to ensure that one train of components needed to achieve and maintain the safe shutdown conditions is free of fire damage, and that radioactive liberation is minimized. (Author)

  5. Technical specification improvement through safety margin considerations

    International Nuclear Information System (INIS)

    Howard, R.C.; Jansen, R.L.

    1986-01-01

    Westinghouse has developed an approach for utilizing safety analysis margin considerations to improve plant operability through technical specification revision. This approach relies on the identification and use of parameter interrelations and sensitivities to identify acceptable operating envelopes. This paper summarizes technical specification activities to date and presents the use of safety margin considerations as another viable method to obtain technical specification improvement

  6. Generalization of socially transmitted and instructed avoidance

    Directory of Open Access Journals (Sweden)

    Gemma eCameron

    2015-06-01

    Full Text Available Excessive avoidance behavior, in which an instrumental action prevents an upcoming aversive event, is a defining feature of anxiety disorders. Left unchecked, both fear and avoidance of potentially threatening stimuli may generalize to perceptually related stimuli and situations. The behavioral consequences of generalization mean that aversive learning experiences with specific threats may lead people to infer that classes of related stimuli are threatening, potentially dangerous, and need to be avoided, despite differences in physical form. Little is known about avoidance generalization in humans and the learning pathways by which it may be transmitted. In the present study, we compared two pathways to avoidance, instructions and social observation, on subsequent generalization of avoidance behavior, fear expectancy and physiological arousal. Participants first learned that one cue was a danger cue (conditioned stimulus, CS+ and another was a safety cue (CS-. Groups then were either instructed that a simple avoidance response in the presence of the CS+ cancelled upcoming shock presentations (instructed-learning group or observed a short movie showing a demonstrator performing the avoidance response to prevent shock (observational-learning group. During generalization testing, danger and safety cues were presented along with generalization stimuli that parametrically varied in perceptual similarity to the CS+. Reinstatement of fear and avoidance was also tested. Findings demonstrate, for the first time, generalization of socially transmitted and instructed avoidance: both groups showed comparable generalization gradients in fear expectancy, avoidance behavior and arousal. Return of fear was evident, suggesting that generalized avoidance remains persistent following extinction testing. The utility of the present paradigm for research on avoidance generalization is discussed.

  7. Philippines revises power plans

    Energy Technology Data Exchange (ETDEWEB)

    Hayes, D.

    1988-02-01

    Following an unexpected surge in electricity demand the Philippines has revised its medium term power development programme. The sharp increase in electricity consumption follows three years of slack demand due to civil disturbances before the end of the Macros administration and the election of Corazon Aquino as President in 1986. Originally, the Aquino government's medium term power development plans called for about 500MW of generating capacity to be installed between 1986 and 1992. The three proposed plants were scheduled for commissioning in 1991 and 1992. However, a spurt in power demand growth during the past nine months has caused concern among industrialists that power shortages could occur by the end of the decade. So additional capacity will be installed to prevent an anticipated shortfall in electricity supplies by the early 1990s.

  8. Revised SRAC code system

    International Nuclear Information System (INIS)

    Tsuchihashi, Keichiro; Ishiguro, Yukio; Kaneko, Kunio; Ido, Masaru.

    1986-09-01

    Since the publication of JAERI-1285 in 1983 for the preliminary version of the SRAC code system, a number of additions and modifications to the functions have been made to establish an overall neutronics code system. Major points are (1) addition of JENDL-2 version of data library, (2) a direct treatment of doubly heterogeneous effect on resonance absorption, (3) a generalized Dancoff factor, (4) a cell calculation based on the fixed boundary source problem, (5) the corresponding edit required for experimental analysis and reactor design, (6) a perturbation theory calculation for reactivity change, (7) an auxiliary code for core burnup and fuel management, etc. This report is a revision of the users manual which consists of the general description, input data requirements and their explanation, detailed information on usage, mathematics, contents of libraries and sample I/O. (author)

  9. The Agency's Safety Standards and Measures

    International Nuclear Information System (INIS)

    1976-04-01

    The Agency's Health and Safety Measures were first, approved by the Board of Governors on 31 March 1960 in implementation of Articles III.A.6 and XII of the Statute of the Agency. On the basis of the experience gained from applying those measures to projects carried out by Members under agreements concluded with the Agency, the Agency's Health and Safety Measures were revised in 1975 and approved by the Board of Governors on 25 February 1976. The Agency's Safety Standards and Measures as revised are reproduced in this document for the information of all Members

  10. Instructional Leadership Practices in Singapore

    Science.gov (United States)

    Ng, Foo Seong David; Nguyen, Thanh Dong; Wong, Koon Siak Benjamin; Choy, Kim Weng William

    2015-01-01

    This paper presents a review of the literature on principal instructional leadership in Singapore. The authors investigated the dimensions of instructional leadership in the practices of Singapore principals and highlighted the strategies these leaders adopt to enact their instructional roles. Singapore principals were found to play an active role…

  11. Putting instruction sequences into effect

    NARCIS (Netherlands)

    Bergstra, J.A.

    2011-01-01

    An attempt is made to define the concept of execution of an instruction sequence. It is found to be a special case of directly putting into effect of an instruction sequence. Directly putting into effect of an instruction sequences comprises interpretation as well as execution. Directly putting into

  12. The Measurement of Instructional Accomplishments.

    Science.gov (United States)

    Fraley, Lawrence E.; Vargas, Ernest A.

    Instructional System Technology in recent years has been characterized by an increase in individualized instruction and the modularization of the curriculum. In traditional systems the learners are forced to take blocks of instruction the size of entire courses and these are much too large. The courses can now be broken down into conceptual…

  13. Intelligent Frameworks for Instructional Design.

    Science.gov (United States)

    Spector, J. Michael; And Others

    1992-01-01

    Presents a taxonomy describing various uses of artificial intelligence techniques in automated instructional development systems. Instructional systems development is discussed in relation to the design of computer-based instructional courseware; two systems being developed at the Air Force Armstrong Laboratory are reviewed; and further research…

  14. Very Long Instruction Word Processors

    Indian Academy of Sciences (India)

    Explicitly Parallel Instruction Computing (EPIC) is an instruction processing paradigm that has been in the spot- light due to its adoption by the next generation of Intel. Processors starting with the IA-64. The EPIC processing paradigm is an evolution of the Very Long Instruction. Word (VLIW) paradigm. This article gives an ...

  15. Motivational elements in user instructions

    NARCIS (Netherlands)

    Loorbach, N.R.

    2013-01-01

    Concerning the design of user instructions, two view can be distinguished. The traditional view considers instructions as purely instrumental documents. The more and more emerging affective view still assumes that above all, instructions should enable readers to perform tasks. But in order to

  16. Brief, cooperative peer-instruction sessions during lectures enhance student recall and comprehension*

    Science.gov (United States)

    Zhang, Niu; Henderson, Charles N.R.

    2016-01-01

    Objective: The objective of this study was to evaluate the academic impact of cooperative peer instruction during lecture pauses in an immunology/endocrinology course. Methods: Third-quarter students participated across iterations of the course. Each class offered 20 lectures of 50 minutes each. Classes were divided into a peer-instruction group incorporating cooperative peer instruction and a control group receiving traditional lectures. Peer-instruction group lectures were divided into 2–3 short presentations followed by a multiple-choice question (MCQ). Students recorded an initial answer and then had 1 minute to discuss answers with group peers. Following this, students could submit a revised answer. The control group received the same lecture material, but without MCQs or peer discussions. Final-exam scores were compared across study groups. A mixed-design analysis of covariance was used to analyze the data. Results: There was a statistically significant main effect for the peer-instruction activity (F(1, 93) = 6.573, p = .012, r = .257), with recall scores higher for MCQs asked after peer-instruction activities than for those asked before peer instruction. Final-exam scores at the end of term were greater in the peer-instruction group than the control group (F(1, 193) = 9.264, p = .003, r = .214; question type, F(1, 193) = 26.671, p = .000, r = .348). Conclusion: Lectures with peer-instruction pauses increase student recall and comprehension compared with traditional lectures. PMID:26967766

  17. Exposure to non-ionizing electromagnetic radiation and public health : review of safety levels; Exposicion a radiaciones no ionizantes ambientales y salud publica: Una revision de las bases biomedicas de los limites de seguridad

    Energy Technology Data Exchange (ETDEWEB)

    Ubeda, A.; Trillo, M. A.

    2005-07-01

    The potential health effects of the exposure to non-ionizing electromagnetic radiation are a source of increasing interest on the part of the public and the authorities. This article summarizes the theoretical-experimental basis supporting the safety levels proposed by international committees, and reviews the recent scientific literature on non-ionizing radiation's bioeffects that are relevant to the validation or modification of the present exposure limits. Because of its social interest, special consideration is given to power frequency fields (50-60Hz) and to the radio communication signals of mobile telephony. The paper also describes how interpretations of the scientific evidence, other than those of the international committees, have generated some controversy and have provided a basis for more restrictive limits, like those adopted in Europe by Switzerland and Italy. The article also identifies some gaps in the present scientific knowledge on the bioelectromagnetics discipline and proposes that additional research is needed to complete our present knowledge on the biological responses to non-ionizing radiation. (Author) 80 refs.

  18. Instructional immediacy in elearning.

    Science.gov (United States)

    Walkem, Kerrie

    2014-01-01

    Instructor immediacy has been positively associated with many desirable academic outcomes including increased student learning. This study extends existing understanding of instructional immediacy behaviours in elearning by describing postgraduate nursing students' reflections on their own experience. An exploratory, descriptive survey design was used to collect qualitative data. Participants were asked what behaviours or activities help to create rapport or a positive interpersonal connection (immediacy) between students and their online teacher(s). Thematic analysis of the data revealed three main themes: acknowledging and affirming student's personal and professional responsibilities; providing clear and timely information; and utilising rich media. These findings give lecturers insight into instructional strategies they may adopt to increase immediacy in elearning and hence improve student learning outcomes.

  19. A Critique of Instructional

    OpenAIRE

    McKernan, James

    2010-01-01

    The ‘objectives model’ of curriculum planning, predicated upon behavioural performances, has become the dominant form of curriculum planning in Europe and elsewhere in the world. This paper argues that the objectives model is satisfactory for training or instruction, but falls down when applied to a true sense of ‘education’. The paper outlines 13 limitations on the use of educational objectives. It is argued that those interested in using objectives are guided by evaluation as assessment rat...

  20. A study on scar revision

    Directory of Open Access Journals (Sweden)

    Ashutosh Talwar

    2016-04-01

    Full Text Available Introduction: Scars are psychologically distressing for the patients and have an impact on the quality of life and self esteem of the patients. Scar revision is an aesthetic skill which is mastered by plastic surgeons and encroached now by dermatosurgeons. Scars on the face are aesthetically unacceptable and various techniques have been improvised for making a scar aesthetically acceptable. Various types of techniques are used for scar revision like W plasty, Z plasty and VY plasty. Aims: To see the efficacy of various scar revision techniques including Z plasty, VY plasty and W plasty in 30 patients with disfiguring scars. Methods: We selected twenty patients of disfiguring scars for the study. The scars from various causes including trauma and burns were included in our study. Various techniques of scar revision include Z plasty, W plasty and VY plasty were performed according to the type and site of scar. Results: Male: female was 1.5: 1. The scar revision surgery yielded excellent results with minimal complications including haematoma formation, secondary infection and delayed healing seen in 5% patients each. Regarding the efficacy of scar revision, excellent improvement was seen in 60% patients, moderate improvement was seen in 30% patients and mild improvement was seen in 10% patients. Conclusions: Dermatologists can employ a number of surgical scar revision techniques. While some are better suited to treat specific types of scars, they can be used in combination with each other or with adjunctive therapies to achieve optimal results.

  1. Operational safety - the IAEA response

    International Nuclear Information System (INIS)

    Rosen, M.

    1984-01-01

    Nuclear safety is an international issue. The role of the International Atomic Energy Agency is growing because it offers a centre for contact and exchange between East and West, North and South. New initiatives are under way to intensify international co-operative safety efforts through exchange of information on abnormal events at nuclear power plants, and through greater sharing of safety research results. Emergency preparedness also lends itself to international co-operation. A report has been prepared on the need for establishing mutual emergency assistance. By analysing possible constraints to bilateral or multinational efforts in advance, a basis for agreement at the time of an emergency is being worked out. Safety standards have been developed in several areas. The NUSS Codes and Guides, now almost complete, make available to countries starting a nuclear power programme a coherent set of nuclear safety standards. A revised set of Basic Safety Standards for Radiation Protection has been issued in 1982. (author)

  2. Effective Multicultural Instruction

    Directory of Open Access Journals (Sweden)

    Franklin T. Thompson

    2014-02-01

    Full Text Available The reason why the Trayvon Martin murder trial and similar court cases create a philosophical rift in our nation is due in part to flaws in the delivery of multicultural education. Traditional multicultural instruction does not prepare citizens for the subtleties and complexities of race relations. This study investigates critical strategies and practices that address multicultural missing gaps. I also seek to fill a void in the literature created by a lack of student input regarding teaching strategies that encourage lifelong learning. Students (N = 337 enrolled at a Midwestern university were asked to rate the efficacy of selected instructional strategies. Utilizing a 9-point Likert-type scale, students gave themselves a personal growth rating of 7.15 (SD = 1.47. Variables important to predicting that growth (R2 = .56, p < .0005 were a six-factor variable known as a non-color-blind instructional approach (t = 10.509, p ≤ .0005, allowing students an opportunity to form their own opinions apart from the instructor (t = 4.797, p ≤ .0005, and a state law that mandated multicultural training (t = 3.234, p = .001. Results demonstrated that utilizing a 35% traditional and 65% critical pedagogy mixture when teaching multicultural education helped promote win/win scenarios for education candidates hoping to become difference makers.

  3. Репрезентация фрейма airplane safety Instruction в различных видах дискурса

    OpenAIRE

    Астахова, Е.

    2009-01-01

    В статье рассматривается фрейм AIRPLANE SAFETY INSTRUCTION как компонент концепта Instruction. Предполагается, что любой текст может содержать инструкцию о том, что и как необходимо делать в определённых ситуациях, в том числе и в чрезвычайных ситуациях. Целью данной работы является анализ образцов различных дискурсов и выявление способов репрезентации исследуемого фрейма....

  4. Va-Room: Motorcycle Safety.

    Science.gov (United States)

    Keller, Rosanne

    One of a series of instructional materials produced by the Literacy Council of Alaska, this booklet provides information about motorcycle safety. Using a simplified vocabulary and shorter sentences, it offers statistics concerning motorcycle accidents; information on how to choose the proper machine; basic information about the operation of the…

  5. Auto Safety

    Science.gov (United States)

    ... Safe Videos for Educators Search English Español Auto Safety KidsHealth / For Parents / Auto Safety What's in this ... by teaching some basic rules. Importance of Child Safety Seats Using a child safety seat (car seat) ...

  6. Draft revision of human factors guideline HF-010

    International Nuclear Information System (INIS)

    Lee, Hyun Chul; Lee, Yong Hee; Oh, In Seok; Lee, Jung Woon; Cha, Woo Chang; Lee, Dhong Ha

    2003-05-01

    The Application of Human Factors to the design of Man-Machine Interfaces System(MMIS) in the nuclear power plant is essential to the safety and productivity of the nuclear power plants, human factors standards and guidelines as well as human factors analysis methods and experiments are weightily used to the design application. A Korean engineering company has developed a human factors engineering guideline, so-call HF-010, and has used it for human factors design, however the revision of HF-010 is necessary owing to lack of the contents related to the advanced MMI(Man-Machine Interfaces). As the results of the reviews of HF-010, it is found out that the revision of Section 9. Computer Displays of HF-010 is urgent, thus the revision was drafted on the basis of integrated human factors design guidelines for VDT, human factors design guidelines for PMAS SPADES display, human factors design guidelines for PMAS alarm display, and human factors design guidelines for electronic displays developed by the surveillance and operation support project of KOICS. The draft revision of HF-010 Section 9 proposed in this report can be utilized for the human factors design of the advanced MMI, and the high practical usability of the draft can be kept up through the continuous revision according to the advancement of digital technology

  7. Decommissioning plan - decommissioning project for KRR 1 and 2 (revised)

    International Nuclear Information System (INIS)

    Jung, K. J.; Paik, S. T.; Chung, U. S.; Jung, K. H.; Park, S. K.; Lee, D. G.; Kim, H. R.; Kim, J. K.; Yang, S. H.; Lee, B. J.

    2000-10-01

    This report is the revised Decommissioning Plan for the license of TRIGA research reactor decommissioning project according to Atomic Energy Act No. 31 and No. 36. The decommissioning plan includes the TRIGA reactor facilities, project management, decommissioning method, decontamination and dismantling activity, treatment, packaging, transportation and disposal of radioactive wastes. the report also explained the radiation protection plan and radiation safety management during the decommissioning period, and expressed the quality assurance system during the period and the site restoration after decommissioning. The first decommissioning plan was made by Hyundai Engineering Co, who is the design service company, was submitted to the Ministry of Science and Technology, and then was reviewed by the Korea Institute of Nuclear Safety. The first decommissioning plan was revised including answers for the questions arising from review process

  8. Decommissioning plan - decommissioning project for KRR 1 and 2 (revised)

    Energy Technology Data Exchange (ETDEWEB)

    Jung, K. J.; Paik, S. T.; Chung, U. S.; Jung, K. H.; Park, S. K.; Lee, D. G.; Kim, H. R.; Kim, J. K.; Yang, S. H.; Lee, B. J

    2000-10-01

    This report is the revised Decommissioning Plan for the license of TRIGA research reactor decommissioning project according to Atomic Energy Act No. 31 and No. 36. The decommissioning plan includes the TRIGA reactor facilities, project management, decommissioning method, decontamination and dismantling activity, treatment, packaging, transportation and disposal of radioactive wastes. the report also explained the radiation protection plan and radiation safety management during the decommissioning period, and expressed the quality assurance system during the period and the site restoration after decommissioning. The first decommissioning plan was made by Hyundai Engineering Co, who is the design service company, was submitted to the Ministry of Science and Technology, and then was reviewed by the Korea Institute of Nuclear Safety. The first decommissioning plan was revised including answers for the questions arising from review process.

  9. Contact activation: a revision.

    Science.gov (United States)

    Schmaier, A H

    1997-07-01

    In conclusion, a revised view of the contact system has been presented. This system has little to do with the initiation of hemostasis. Like lupus anticoagulants, deficiencies of contact proteins give prolonged APTTs but may be risk factors for thrombosis. BK from kininogens is a potent modulator of vascular biology inducing vasodilation, tissue plasminogen activator release, and prostacyclin liberation. Kininogens, themselves, are selective inhibitors of alpha-thrombin-induced platelet activation preventing alpha-thrombin from cleaving the cloned thrombin receptor after arginine41. Kininogens' alpha-thrombin inhibitory activity exists in intact kininogens, BK, and all of BK's breakdown products. HK also is the pivotal protein for contact protein assembly on endothelium. It is the receptor for prekallikrein which when bound to HK becomes activated to kallikrein by an endothelial cell enzyme system independent of activated forms of plasma factor XII. Prekallikrein activation on endothelial cells results in kinetically favorable single chain urokinase and plasminogen activation. Thus the "physiologic, negatively charged surface" for contact system activation is really the assembly of these proteins on cell membranes and activation by membrane-associated enzymes.

  10. Significant Revisions to OSHA 29 CFR 1910.269.

    Science.gov (United States)

    Neitzel, Dennis K

    2015-06-01

    The updated OSHA 29 CFR 1910.269 requirements are significant for assisting employers in their efforts to protect their employees from electrical hazards. In addition, OSHA based these revisions on the latest consensus standards and improvements in electrical safety technology. Together, the updated regulation creates a unified and up-to-date set of requirements to help employers more effectively establish safe work practices to protect their workers.

  11. Cryogenic Safety Rules and Guidelines at CERN

    CERN Multimedia

    CERN. Geneva

    2016-01-01

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

  12. Circumcision revision in male children

    Directory of Open Access Journals (Sweden)

    Mohammed A. Al-Ghazo

    2006-08-01

    Full Text Available OBJECTIVE: To determine indications for circumcision revision and to identify the specialty of the person who performed unsatisfactory primary circumcision. MATERIALS AND METHODS: The authors reviewed medical records of 52 cases that underwent circumcision revision over a 6-year period (1998 to 2004. Sleeve surgical technique was used for revision in patients with redundant foreskin or concealed penis, penoplasty for partial or complete degloving of the penis and meatotomy for external meatal stenosis. The mean age of children was 32 months (range 6 months to 9 years. RESULTS: Most of unsatisfactory primary circumcisions (86.7% were performed by laymen. All patients who underwent circumcision revision had good to excellent cosmetic results. CONCLUSION: Primary circumcision performed by laymen carry a high complication rate and serious complications may occur. A period of training and direct supervision by physicians is required before allowing laymen to perform circumcision independently.

  13. EPR first responders revision test

    International Nuclear Information System (INIS)

    2011-01-01

    In this revision test evaluates the acquired knowledge in case of radiological emergency confront. Actions to be taken in relation to people, equipment and the environment. Doses, radioactive sources, pollution

  14. Corporate Author Entries. Revision 5

    International Nuclear Information System (INIS)

    Hendricks, P.L.

    1986-05-01

    This reference authority has been created and is maintained to provide standard forms for recording the names of organizations consistently in bibliographic citations. This revision includes approximately 42,000 entries established since 1973

  15. Development of Instructional Competencies for Assessing and Managing Suicide Risk for Baccalaureate Nursing Education: A Modified Delphi Study.

    Science.gov (United States)

    Kotowski, Abigail; Roye, Carol

    2017-03-01

    Suicide is a major health problem and a leading cause of death throughout the world. A primary goal for suicide prevention is reforming health professional education in order to increase the competence of health professionals in assessing and managing suicide risk. Nursing leadership is involved in this reform, yet nurses frequently lack the competence to care for patients in suicidal crisis. An identified gap in baccalaureate nursing education is instructional competencies for assessing and managing suicide risk. A modified Delphi study was used. The study began with a focus group which was conducted in order to develop the Round I Survey which included forty-four competencies. After scoring these competencies, thirty-four were scored for inclusion, two were dropped and eight were revised according to panel members' comments. The Round II Survey comprised the eight revised competencies which were scored for inclusion, resulting in forty-two competencies in the final set of instructional competencies. Forty-two instructional competencies were developed: fourteen pre-assessment instructional competencies, fifteen assessment instructional competencies, and thirteen management instructional competencies. Incorporating these instructional competencies into baccalaureate nursing education might increase the competence of nursing students, and thus new nurses, in caring for patients at risk for suicide. These instructional competencies provide a first step to address the challenging task of intervening with patients at risk for suicide.

  16. Safety case plan 2008

    International Nuclear Information System (INIS)

    2008-07-01

    Following the guidelines set forth by the Ministry of Trade and Industry (now Ministry of Employment and Economy) Posiva is preparing to submit the construction license application for a spent fuel repository by the end of the year 2012. The long-term safety section supporting the license application is based on a safety case, which, according to the internationally adopted definition, is a compilation of the evidence, analyses and arguments that quantify and substantiate the safety and the level of expert confidence in the safety of the planned repository. In 2005, Posiva presented a plan to prepare such a safety case. The present report provides a revised plan of the safety case contents mentioned above. The update of the safety case plan takes into account the recommendations made by the Radiation and Nuclear Safety Authority (STUK) about improving the focus and further developing the plan. Accordingly, particular attention is given to the quality management of the safety case work, the management of uncertainties and the scenario methodology. The quality management is based on the ISO 9001:2000 standard process thinking enhanced with special features arising from STUK's YVL Guides. The safety case production process is divided into four main sub-processes. The conceptualisation and methodology sub-process defines the framework for the assessment. The critical data handling and modelling sub-process links Posiva's main technical and scientific activities to the production of the safety case. The assessment sub-process analyses the consequences of the evolution of the disposal system in various scenarios, classified either as part of the expected evolution or as disruptive scenarios. The compliance and confidence sub-process is responsible for final evaluation of compliance of the assessment results with the regulatory criteria and the overall confidence in the safety case. As in the previous safety case plan, the safety case will be based on several reports, but

  17. Safety assessment standards for modern plants in the UK

    International Nuclear Information System (INIS)

    Harbison, S.A.; Hannaford, J.

    1993-01-01

    The NII has revised its safety assessment principles (SAPs). This paper discusses the revised SAPs and their links with international standards. It considers the licensing of foreign designs of plant - a matter under active consideration in the UK -and discusses how the SAPs and the licensing process cater for that possibility. (author)

  18. Best Estimate plus Uncertainty (BEPU) Analyses in the IAEA Safety Standards

    International Nuclear Information System (INIS)

    Dusic, Milorad; )

    2013-01-01

    The Safety Standards Series establishes an essential basis for safety and represents the broadest international consensus. Safety Standards Series publications are categorized into: Safety Fundamental (Present the overall objectives, concepts and principles of protection and safety, they are the policy documents of the safety standards), Safety Requirements (Establish requirements that must be met to ensure the protection and safety of people and the environment, both now and in the future), and Safety Guides (Provide guidance, in the form of more detailed actions, conditions or procedures that can be used to comply with the Requirements). The incorporation of more detailed requirements, in accordance with national practice, may still be necessary. There should be only one set of international safety standards. Each safety standard will be reviewed by the relevant committee or by the commission every five years. Best Estimate plus Uncertainty (BEPU) Analyses are approached in the following IAEA Safety Standards: - Safety Requirements SSR 2/1 - Safety of NPPs, Design (Revision of NS-R-1); - General Safety Requirement GSR Part 4: Safety Assessment for Facilities and Activities; - Safety Guide SSG-2 Deterministic Safety Analysis for Nuclear Power Plants. NUSSC suggested that new safety guides should be accompanied by documents like TECDOCs or Safety Reports describing in detail their recommendations where appropriate. Special review is currently underway to identify needs for revision in the light of the Fukushima accident. Revision will concern, first, the Safety Requirements, and then, the Selected Safety Guides

  19. USING GOOGLE+ FOR INSTRUCTION

    Directory of Open Access Journals (Sweden)

    Kevin YEE

    Full Text Available Introduced in July, 2011 in a beta test of invited users only, the new social media service Google+ (or G+ quickly spread by word of mouth, and Google leader Larry Page (2011 blogged that within sixteen days it had 10 million users. By August, it had 25 million users (Cashmore, 2011. Even with slower growth ahead (still with no marketing budget, the service looks likely to crest 100 million users perhaps as early as ten months, a feat that took Facebook three years. Other social networks, most notably Facebook and Twitter, have been used increasingly as instructional tools, since they are platforms with which students are already familiar (Maloney, 2007; McLoughlin & Lee, 2007. Selwyn (2009 found that students often eschew official channels for communication in favor of less formal community-based formats such as Facebook, implying a growing need for instructional communication tools that will be used willingly by students. The question is whether Google+ can be used like Twitter or Facebook to augment instruction, or even, perhaps, to improve upon those predecessors for academic purposes. Google+ is like Twitter in that anyone can follow a given user’s posts. There is no direct “friend” relationship required to read the posts written by others. However, it also approximates some features of Facebook. Rather than friends sorted into “lists” like in Facebook, Google+ allows users to place feeds into one or more “circles,” the better to monitor (or control the flow of information to and from different audiences. Circles are more intuitive, and more central to the experience, than the Facebook lists. They provide an explicit organizational structure, compared to the less-obvious listing functionality, which feels like an afterthought, found in Facebook.

  20. EST Vocabulary Instruction

    Directory of Open Access Journals (Sweden)

    Célia D.S. Bell

    2012-05-01

    Full Text Available This study aims at contributing to the investigation on the instruction of EST (English for Science and Technology vocabulary, in terms of receptive use of the language. It evaluates the effectiveness of two teaching approaches to the acquisition of vocabulary. The first approach consisted of teaching vocabulary through the use of dictionaries, where the words were merely translated into the learners’ L1 or defined in the target language thus promoting superficial level of word processing. The second approach employed activities promoting deep level of word processing. Data were analysed quantitatively. Results indicated that the two approaches seem to have some equipotentiality, as far as EST vocabulary is concerned.

  1. The Mere Exposure Instruction Effect.

    Science.gov (United States)

    Van Dessel, Pieter; Mertens, Gaëtan; Smith, Colin Tucker; De Houwer, Jan

    2017-09-01

    The mere exposure effect refers to the well-established finding that people evaluate a stimulus more positively after repeated exposure to that stimulus. We investigated whether a change in stimulus evaluation can occur also when participants are not repeatedly exposed to a stimulus, but are merely instructed that one stimulus will occur frequently and another stimulus will occur infrequently. We report seven experiments showing that (1) mere exposure instructions influence implicit stimulus evaluations as measured with an Implicit Association Test (IAT), personalized Implicit Association Test (pIAT), or Affect Misattribution Procedure (AMP), but not with an Evaluative Priming Task (EPT), (2) mere exposure instructions influence explicit evaluations, and (3) the instruction effect depends on participants' memory of which stimulus will be presented more frequently. We discuss how these findings inform us about the boundary conditions of mere exposure instruction effects, as well as the mental processes that underlie mere exposure and mere exposure instruction effects.

  2. 78 FR 47014 - Configuration Management Plans for Digital Computer Software Used in Safety Systems of Nuclear...

    Science.gov (United States)

    2013-08-02

    .... ML12354A524. 3. Revision 1 of RG 1.170, ``Test Documentation for Digital Computer Software used in Safety... is in ADAMS at Accession No. ML12354A531. 4. Revision 1 of RG 1.171, ``Software Unit Testing for... Software Used in Safety Systems of Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION...

  3. Computer-assisted instruction and diagnosis of radiographic findings.

    Science.gov (United States)

    Harper, D; Butler, C; Hodder, R; Allman, R; Woods, J; Riordan, D

    1984-04-01

    Recent advances in computer technology, including high bit-density storage, digital imaging, and the ability to interface microprocessors with videodisk, create enormous opportunities in the field of medical education. This program, utilizing a personal computer, videodisk, BASIC language, a linked textfile system, and a triangulation approach to the interpretation of radiographs developed by Dr. W. L. Thompson, can enable the user to engage in a user-friendly, dynamic teaching program in radiology, applicable to various levels of expertise. Advantages include a relatively more compact and inexpensive system with rapid access and ease of revision which requires little instruction to the user.

  4. West Valley Reprocessing Plant. Safety analysis report, supplement 21

    International Nuclear Information System (INIS)

    1976-01-01

    Supplement No. 21 contains responses to USNRC questions on quality assurance contained in USNRC letter to NFS dated January 22, 1976, revised pages for the safety analysis report, and Appendix IX ''Quality Assurance Manual--West Valley Construction Projects.''

  5. IAEA safety glossary. Terminology used in nuclear safety and radiation protection. 2007 ed

    International Nuclear Information System (INIS)

    2007-01-01

    In developing and establishing standards of safety for protecting people and the environment from harmful effects of ionizing radiation and for the safety of facilities and activities that give rise to radiation risks, clear communication on scientific and technical concepts is essential. The principles, requirements and recommendations that are established and explained in the IAEA's safety standards and elaborated upon in other publications must be clearly expressed. To this end, this Safety Glossary defines and explains technical terms used in IAEA safety standards and other safety related publications, and provides information on their usage. The primary purpose of the Safety Glossary is to harmonize terminology and usage in the IAEA safety standards for protecting people and the environment from harmful effects of ionizing radiation, and in their application. Once definitions of terms have been established, they are, in general, intended to be observed in safety standards and other safety related publications and in the work of the IAEA Department of Nuclear Safety and Security generally. The achievement of consistently high quality in its publications contributes to the authority and credibility of the IAEA, and thus to its influence and effectiveness. High quality in publications and documents is achieved not only by review to ensure that the relevant requirements are met, but also by managing their preparation so as to achieve high quality in their drafting. The Safety Glossary provides guidance primarily for the drafters and reviewers of safety standards, including IAEA technical officers and consultants and bodies for the endorsement of safety standards. The Safety Glossary is also a source of information for users of IAEA safety standards and other safety and security related IAEA publications and for other IAEA staff - notably writers, editors, translators, revisers and interpreters. Users of the Safety Glossary, in particular drafters of national

  6. IAEA safety glossary. Terminology used in nuclear safety and radiation protection. 2007 ed

    International Nuclear Information System (INIS)

    2007-06-01

    In developing and establishing standards of safety for protecting people and the environment from harmful effects of ionizing radiation and for the safety of facilities and activities that give rise to radiation risks, clear communication on scientific and technical concepts is essential. The principles, requirements and recommendations that are established and explained in the IAEA's safety standards and elaborated upon in other publications must be clearly expressed. To this end, this Safety Glossary defines and explains technical terms used in IAEA safety standards and other safety related publications, and provides information on their usage. The primary purpose of the Safety Glossary is to harmonize terminology and usage in the IAEA safety standards for protecting people and the environment from harmful effects of ionizing radiation, and in their application. Once definitions of terms have been established, they are, in general, intended to be observed in safety standards and other safety related publications and in the work of the IAEA Department of Nuclear Safety and Security generally. The achievement of consistently high quality in its publications contributes to the authority and credibility of the IAEA, and thus to its influence and effectiveness. High quality in publications and documents is achieved not only by review to ensure that the relevant requirements are met, but also by managing their preparation so as to achieve high quality in their drafting. The Safety Glossary provides guidance primarily for the drafters and reviewers of safety standards, including IAEA technical officers and consultants and bodies for the endorsement of safety standards. The Safety Glossary is also a source of information for users of IAEA safety standards and other safety and security related IAEA publications and for other IAEA staff - notably writers, editors, translators, revisers and interpreters. Users of the Safety Glossary, in particular drafters of national

  7. IAEA safety glossary. Terminology used in nuclear safety and radiation protection. 2007 ed

    International Nuclear Information System (INIS)

    2007-01-01

    In developing and establishing standards of safety for protecting people and the environment from harmful effects of ionizing radiation and for the safety of facilities and activities that give rise to radiation risks, clear communication on scientific and technical concepts is essential. The principles, requirements and recommendations that are established and explained in the IAA's safety standards and elaborated upon in other publications must be clearly expressed. To this end, this Safety Glossary defines and explains technical terms used in IAEA safety standards and other safety related publications, and provides information on their usage. The primary purpose of the Safety Glossary is to harmonize terminology and usage in the IAEA safety standards for protecting people and the environment from harmful effects of ionizing radiation, and in their application. Once definitions of terms have been established, they are, in general, intended to be observed in safety standards and other safety related publications and in the work of the IAEA Department of Nuclear Safety and Security generally. The achievement of consistently high quality in its publications contributes to the authority and credibility of the IAEA, and thus to its influence and effectiveness. High quality in publications and documents is achieved not only by review to ensure that the relevant requirements are met, but also by managing their preparation so as to achieve high quality in their drafting. The Safety Glossary provides guidance primarily for the drafters and reviewers of safety standards, including IAEA technical officers and consultants and bodies for the endorsement of safety standards. The Safety Glossary is also a source of information for users of IAEA safety standards and other safety and security related IAEA publications and for other IAEA staff - notably writers, editors, translators, revisers and interpreters. Users of the Safety Glossary, in particular drafters of national

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

    International Nuclear Information System (INIS)

    2005-01-01

    The International Atomic Energy Agency (IAEA) has put forward the vision of a global nuclear safety regime that provides for the protection of people and the environment from the effects of ionizing radiation from nuclear facilities, the minimization of the likelihood of accidents that could endanger life and property and effective mitigation of the effects of any such events should they occur. The strategic approach for achieving the vision of enhancing this regime involves four elements and aims at ensuring that the overall nuclear safety level in Member States continues to improve: - Improvement of national and international safety infrastructures: - Establishment and global acceptance of IAEA safety standards; - Integrated approach to the provision for the application of safety standards; and - Global network of knowledge and experience. The IAEA Operational Safety Review Team (OSART) programme provides advice and assistance to Member States to enhance the safety of nuclear power plants during commissioning and operation. The OSART programme, initiated in 1982, is available to all Member States with nuclear power plants under commissioning or in operation. The OSART methodology and its safety services may also be applied to other nuclear installations (e.g. fuel cycle facilities, research reactors). Conservative design, careful manufacture and sound construction are all prerequisites for safe operation of nuclear power plants. However, the safety of the plant depends ultimately on sound policies, procedures, processes and practices; on the capability and reliability of the commissioning and operating personnel; on comprehensive instructions; and on adequate resources. A positive attitude and conscientiousness on the part of the management and staff in discharging their responsibilities is important to safety. OSART missions consider these aspects in assessing a facility's operational practices in comparison with those used successfully in other countries and

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

    International Nuclear Information System (INIS)

    2008-01-01

    The International Atomic Energy Agency (IAEA) has put forward the vision of a global nuclear safety regime that provides for the protection of people and the environment from the effects of ionizing radiation from nuclear facilities, the minimization of the likelihood of accidents that could endanger life and property and effective mitigation of the effects of any such events should they occur. The strategic approach for achieving the vision of enhancing this regime involves four elements and aims at ensuring that the overall nuclear safety level in Member States continues to improve: - Improvement of national and international safety infrastructures: - Establishment and global acceptance of IAEA safety standards. - Integrated approach to the provision for the application of safety standards. And - Global network of knowledge and experience. The IAEA Operational Safety Review Team (OSART) programme provides advice and assistance to Member States to enhance the safety of nuclear power plants during commissioning and operation. The OSART programme, initiated in 1982, is available to all Member States with nuclear power plants under commissioning or in operation. The OSART methodology and its safety services may also be applied to other nuclear installations (e.g. fuel cycle facilities, research reactors). Conservative design, careful manufacture and sound construction are all prerequisites for safe operation of nuclear power plants. However, the safety of the plant depends ultimately on sound policies, procedures, processes and practices. On the capability and reliability of the commissioning and operating personnel. On comprehensive instructions. And on adequate resources. A positive attitude and conscientiousness on the part of the management and staff in discharging their responsibilities is important to safety. OSART missions consider these aspects in assessing a facility's operational practices in comparison with those used successfully in other countries and

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

    International Nuclear Information System (INIS)

    2007-01-01

    The International Atomic Energy Agency (IAEA) has put forward the vision of a global nuclear safety regime that provides for the protection of people and the environment from the effects of ionizing radiation from nuclear facilities, the minimization of the likelihood of accidents that could endanger life and property and effective mitigation of the effects of any such events should they occur. The strategic approach for achieving the vision of enhancing this regime involves four elements and aims at ensuring that the overall nuclear safety level in Member States continues to improve: - Improvement of national and international safety infrastructures: - Establishment and global acceptance of IAEA safety standards. - Integrated approach to the provision for the application of safety standards. And - Global network of knowledge and experience. The IAEA Operational Safety Review Team (OSART) programme provides advice and assistance to Member States to enhance the safety of nuclear power plants during commissioning and operation. The OSART programme, initiated in 1982, is available to all Member States with nuclear power plants under commissioning or in operation. The OSART methodology and its safety services may also be applied to other nuclear installations (e.g. fuel cycle facilities, research reactors). Conservative design, careful manufacture and sound construction are all prerequisites for safe operation of nuclear power plants. However, the safety of the plant depends ultimately on sound policies, procedures, processes and practices. On the capability and reliability of the commissioning and operating personnel. On comprehensive instructions. And on adequate resources. A positive attitude and conscientiousness on the part of the management and staff in discharging their responsibilities is important to safety. OSART missions consider these aspects in assessing a facility's operational practices in comparison with those used successfully in other countries and

  11. Radiation safety requirements for radionuclide laboratories

    International Nuclear Information System (INIS)

    1993-01-01

    In accordance with the section 26 of the Finnish Radiation Act (592/91) the safety requirements to be taken into account in planning laboratories and other premises, which affect safety in the use of radioactive materials, are confirmed by the Finnish Centre for Radiation and Nuclear Safety. The guide specifies the requirements for laboratories and storage rooms in which radioactive materials are used or stored as unsealed sources. There are also some general instructions concerning work procedures in a radionuclide laboratory

  12. Occupational exposures worldwide and revision of international standards for protection

    International Nuclear Information System (INIS)

    Czarwinski, R.; Crick, M. J.

    2011-01-01

    United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) has become the world authority on the levels and effects of ionising radiation. Since 1975, UNSCEAR has evaluated inter alia the level of occupational exposure worldwide. Based on revised questionnaires, more detailed information is now available. The results of the last evaluation (1995-2002) will be shown in the paper. Lessons learned from the responses by UN Member States will be given, as well as an outline of plans for data collection in future cycles. The requirements for protection against exposure to ionising radiation of workers, the public and patients are established in the International Basic Safety Standards for Protection against Ionising Radiation and for the Safety of Radiation Sources (BSS), published in 1996. As a result of a review of the BSS in 2006, the International Atomic Energy Agency (IAEA) started a process for the revision of these standards in 2007. International organisations including the joint sponsoring organisations of the BSS-IAEA, FAO, ILO, OECD/NEA, PAHO and WHO-as well as potential new joint sponsoring organisations of the revised BSS-the European Commission and UNEP-were involved from the beginning in the revision process. The paper also provides a summary of the status of the Draft Revised BSS and describes the new format. The paper focuses, in particular, on requirements for the protection of workers as well as record keeping requirements, which provide the legal basis for the collection of specific data; these data are of the type that can be used by UNSCEAR. (authors)

  13. The Instructional Network: Using Facebook to Enhance Undergraduate Mathematics Instruction

    Science.gov (United States)

    Gregory, Peter; Gregory, Karen; Eddy, Erik

    2014-01-01

    Facebook is a website with over one billion users worldwide that is synonymous with social-networking. However, in this study, Facebook is used as an "instructional network". Two sections of an undergraduate calculus course were used to study the effects of participating in a Facebook group devoted solely to instruction. One section was…

  14. Improving Reading Instruction through Research-Based Instructional Strategies

    Science.gov (United States)

    Nash, Vickie Lynn

    2010-01-01

    The diverse population of students in grades 1- 3 at a suburban elementary school has created a challenge for teachers when differentiating instruction in reading. The purpose of this doctoral project study was to explore the lived experiences of these teachers as they have acquired research-based instructional strategies in reading that support…

  15. Occupational Safety and Health Programs in Career Education.

    Science.gov (United States)

    DiCarlo, Robert D.; And Others

    This resource guide was developed in response to the Occupational Safety and Health Act of 1970 and is intended to assist teachers in implementing courses in occupational safety and health as part of a career education program. The material is a synthesis of films, programed instruction, slides and narration, case studies, safety pamphlets,…

  16. Radiation protection and safety of radiation sources international basic safety standards

    CERN Document Server

    International Atomic Energy Agency. Vienna

    2014-01-01

    The Board of Governors of the IAEA first approved Basic Safety Standards in June 1962; they were published by the IAEA as IAEA Safety Series No. 9. A revised edition was issued in 1967. A third revision was published by the IAEA as the 1982 Edition of IAEA Safety Series No. 9 ; this edition was jointly sponsored by the IAEA, ILO, OECD/NEA and the WHO. The next edition was International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources, published by the IAEA as IAEA Safety Series No. 115 in February 1996, and jointly sponsored by the FAO, IAEA, ILO, OECD/NEA, PAHO and the WHO.

  17. Safety of nuclear power plants: Design. Safety requirements

    International Nuclear Information System (INIS)

    2000-01-01

    The present publication supersedes the Code on the Safety of Nuclear Power Plants: Design (Safety Series No. 50-C-D (Rev. 1), issued in 1988). It takes account of developments relating to the safety of nuclear power plants since the Code on Design was last revised. These developments include the issuing of the Safety Fundamentals publication, The Safety of Nuclear Installations, and the present revision of various safety standards and other publications relating to safety. Requirements for nuclear safety are intended to ensure adequate protection of site personnel, the public and the environment from the effects of ionizing radiation arising from nuclear power plants. It is recognized that technology and scientific knowledge advance, and nuclear safety and what is considered adequate protection are not static entities. Safety requirements change with these developments and this publication reflects the present consensus. This Safety Requirements publication takes account of the developments in safety requirements by, for example, including the consideration of severe accidents in the design process. Other topics that have been given more detailed attention include management of safety, design management, plant ageing and wearing out effects, computer based safety systems, external and internal hazards, human factors, feedback of operational experience, and safety assessment and verification. This publication establishes safety requirements that define the elements necessary to ensure nuclear safety. These requirements are applicable to safety functions and the associated structures, systems and components, as well as to procedures important to safety in nuclear power plants. It is expected that this publication will be used primarily for land based stationary nuclear power plants with water cooled reactors designed for electricity generation or for other heat production applications (such as district heating or desalination). It is recognized that in the case of

  18. Safety of nuclear power plants: Design. Safety requirements

    International Nuclear Information System (INIS)

    2004-01-01

    The present publication supersedes the Code on the Safety of Nuclear Power Plants: Design (Safety Series No. 50-C-D (Rev. 1), issued in 1988). It takes account of developments relating to the safety of nuclear power plants since the Code on Design was last revised. These developments include the issuing of the Safety Fundamentals publication, The Safety of Nuclear Installations, and the present revision of various safety standards and other publications relating to safety. Requirements for nuclear safety are intended to ensure adequate protection of site personnel, the public and the environment from the effects of ionizing radiation arising from nuclear power plants. It is recognized that technology and scientific knowledge advance, and nuclear safety and what is considered adequate protection are not static entities. Safety requirements change with these developments and this publication reflects the present consensus. This Safety Requirements publication takes account of the developments in safety requirements by, for example, including the consideration of severe accidents in the design process. Other topics that have been given more detailed attention include management of safety, design management, plant ageing and wearing out effects, computer based safety systems, external and internal hazards, human factors, feedback of operational experience, and safety assessment and verification. This publication establishes safety requirements that define the elements necessary to ensure nuclear safety. These requirements are applicable to safety functions and the associated structures, systems and components, as well as to procedures important to safety in nuclear power plants. It is expected that this publication will be used primarily for land based stationary nuclear power plants with water cooled reactors designed for electricity generation or for other heat production applications (such as district heating or desalination). It is recognized that in the case of

  19. Nuclear safety

    International Nuclear Information System (INIS)

    1991-02-01

    This book reviews the accomplishments, operations, and problems faced by the defense Nuclear Facilities Safety Board. Specifically, it discusses the recommendations that the Safety Board made to improve safety and health conditions at the Department of Energy's defense nuclear facilities, problems the Safety Board has encountered in hiring technical staff, and management problems that could affect the Safety Board's independence and credibility

  20. Opinion of the IRSN on the instruction on the continuation of the GPR assessment of the safety re-examination VD3-900 - Examination of the conclusive report of the safety re-examination of the nr 1 reactor of the Fessenheim plant after the third decennial inspection

    International Nuclear Information System (INIS)

    2011-02-01

    This report first describes the context of the safety re-examination of the nr 1 reactor of the Fessenheim nuclear power station (CNPE) and assesses the generic aspects of this re-examination, assesses additional information transmitted by EDF and concerning these generic aspects (external and internal stresses, accidents and their radiological consequences, design of systems and civil engineering works), states recommendations on various topics and issues to be considered (internal explosions, probabilistic studies, severe accidents, confinement in post-accidental situation, behaviour of containment enclosures, and son on). It assesses the content of the conclusive report of the safety re-examination

  1. The transport safety programme

    International Nuclear Information System (INIS)

    Selling, H.A.

    1994-01-01

    The transport safety programme is one of the smaller technical sub-programmes in the Radiation Safety Section of the Division of Nuclear Safety, in terms of both regular budget and professional staff allocations. The overall aim of the programme is to promote the safe movement of radioactive material worldwide. The specific objectives are the development, review and maintenance of the Regulations for the Safe Transport of Radioactive Material, Safety Series No 6, and its supporting documents Safety Series Nos 7, 37 and 80 and the assistance to Member States and International Organizations in the proper implementation of the Regulations. One of the important issues that emerged during an ongoing Review/Revision process is the transport of Low-Specific Activity (LSA) material and Surface Contaminated Objects (SCO). Many of the radioactive waste materials fall in one of these categories. The subject has gained substance because it is expected that in the next decade radioactive waste could become available in so far unprecedented quantities and volumes due to decontamination and decommissioning of nuclear facilities. (author)

  2. Designing Instructional Materials: Some Guidelines.

    Science.gov (United States)

    Burbank, Lucille; Pett, Dennis

    Guidelines for the design of instructional materials are outlined in this paper. The principles of design are presented in five major categories: (1) general design (structural appeal and personal appeal); (2) instructional design (attention, memory, concept learning, and attitude change); (3) visual design (media considerations, pictures, graphs…

  3. Cognitive Approaches to Automated Instruction.

    Science.gov (United States)

    Regian, J. Wesley, Ed.; Shute, Valerie J., Ed.

    This book contains a snapshot of state-of-the-art research on the design of automated instructional systems. Selected cognitive psychologists were asked to describe their approach to instruction and cognitive diagnosis, the theoretical basis of the approach, its utility and applicability, and the knowledge engineering or task analysis methods…

  4. Physics Instruction for Radiologic Technologists

    Science.gov (United States)

    Chaney, Edward L.; And Others

    1974-01-01

    Discusses the Denver collaborative training program in radiologic technology with emphasis upon identification of core topics, preparation of quality instructional materials, and use of innovative teaching techniques, such as computer-assisted instruction and video tape presentations. Included is a 10-week course outline. (CC)

  5. Active Learning through Online Instruction

    Science.gov (United States)

    Gulbahar, Yasemin; Kalelioglu, Filiz

    2010-01-01

    This article explores the use of proper instructional techniques in online discussions that lead to meaningful learning. The research study looks at the effective use of two instructional techniques within online environments, based on qualitative measures. "Brainstorming" and "Six Thinking Hats" were selected and implemented…

  6. Adaptive instruction and pupil achievement

    NARCIS (Netherlands)

    Houtveen, A.A M; Booy, N; de Jong, Robert (Rob); van de Grift, W.J C M

    In this article the results are reported of a quasi-experiment on effects of adaptive instruction on reading results of children in the first year of reading instruction in Dutch primary schools. The research involved 456 pupils from 23 schools (12 experimental and 11 control group schools).

  7. Instructional Theory for Teaching Statistics.

    Science.gov (United States)

    Atwood, Jan R.; Dinham, Sarah M.

    Metatheoretical analysis of Ausubel's Theory of Meaningful Verbal Learning and Gagne's Theory of Instruction using the Dickoff and James paradigm produced two instructional systems for basic statistics. The systems were tested with a pretest-posttest control group design utilizing students enrolled in an introductory-level graduate statistics…

  8. Drug Safety

    Science.gov (United States)

    ... over-the-counter drug. The FDA evaluates the safety of a drug by looking at Side effects ... clinical trials The FDA also monitors a drug's safety after approval. For you, drug safety means buying ...

  9. Nuclear safety

    International Nuclear Information System (INIS)

    Tarride, Bruno

    2015-10-01

    The author proposes an overview of methods and concepts used in the nuclear industry, at the design level as well as at the exploitation level, to ensure an acceptable safety level, notably in the case of nuclear reactors. He first addresses the general objectives of nuclear safety and the notion of acceptable risk: definition and organisation of nuclear safety (relationships between safety authorities and operators), notion of acceptable risk, deterministic safety approach and main safety principles (safety functions and confinement barriers, concept of defence in depth). Then, the author addresses the safety approach at the design level: studies of operational situations, studies of internal and external aggressions, safety report, design principles for important-for-safety systems (failure criterion, redundancy, failure prevention, safety classification). The next part addresses safety during exploitation and general exploitation rules: definition of the operation domain and of its limits, periodic controls and tests, management in case of incidents, accidents or aggressions

  10. Unaligned instruction relocation

    Energy Technology Data Exchange (ETDEWEB)

    Bertolli, Carlo; O' Brien, John K.; Sallenave, Olivier H.; Sura, Zehra N.

    2017-10-17

    In one embodiment, a computer-implemented method includes receiving source code to be compiled into an executable file for an unaligned instruction set architecture (ISA). Aligned assembled code is generated, by a computer processor. The aligned assembled code complies with an aligned ISA and includes aligned processor code for a processor and aligned accelerator code for an accelerator. A first linking pass is performed on the aligned assembled code, including relocating a first relocation target in the aligned accelerator code that refers to a first object outside the aligned accelerator code. Unaligned assembled code is generated in accordance with the unaligned ISA and includes unaligned accelerator code for the accelerator and unaligned processor code for the processor. A second linking pass is performed on the unaligned assembled code, including relocating a second relocation target outside the unaligned accelerator code that refers to an object in the unaligned accelerator code.

  11. Unaligned instruction relocation

    Science.gov (United States)

    Bertolli, Carlo; O'Brien, John K.; Sallenave, Olivier H.; Sura, Zehra N.

    2018-01-23

    In one embodiment, a computer-implemented method includes receiving source code to be compiled into an executable file for an unaligned instruction set architecture (ISA). Aligned assembled code is generated, by a computer processor. The aligned assembled code complies with an aligned ISA and includes aligned processor code for a processor and aligned accelerator code for an accelerator. A first linking pass is performed on the aligned assembled code, including relocating a first relocation target in the aligned accelerator code that refers to a first object outside the aligned accelerator code. Unaligned assembled code is generated in accordance with the unaligned ISA and includes unaligned accelerator code for the accelerator and unaligned processor code for the processor. A second linking pass is performed on the unaligned assembled code, including relocating a second relocation target outside the unaligned accelerator code that refers to an object in the unaligned accelerator code.

  12. Recipe Modification Improves Food Safety Practices during Cooking of Poultry.

    Science.gov (United States)

    Maughan, Curtis; Godwin, Sandria; Chambers, Delores; Chambers, Edgar

    2016-08-01

    Many consumers do not practice proper food safety behaviors when preparing food in the home. Several approaches have been taken to improve food safety behaviors among consumers, but there still is a deficit in actual practice of these behaviors. The objective of this study was to assess whether the introduction of food safety instructions in recipes for chicken breasts and ground turkey patties would improve consumers' food safety behaviors during preparation. In total, 155 consumers in two locations (Manhattan, KS, and Nashville, TN) were asked to prepare a baked chicken breast and a ground turkey patty following recipes that either did or did not contain food safety instructions. They were observed to track hand washing and thermometer use. Participants who received recipes with food safety instructions (n = 73) demonstrated significantly improved food safety preparation behaviors compared with those who did not have food safety instructions in the recipe (n = 82). In addition, the majority of consumers stated that they thought the recipes with instructions were easy to use and that they would be likely to use similar recipes at home. This study demonstrates that recipes could be a good source of food safety information for consumers and that they have the potential to improve behaviors to reduce foodborne illness.

  13. Revised licensee event report system

    International Nuclear Information System (INIS)

    Mays, G.T.; Poore, W.P.

    1985-01-01

    Licensee Event Reports (LERs) provide the basis for evaluating and assessing operating experience information from nuclear power plants. The reporting requirements for submitting LERs to the Nuclear Regulatory Commission have been revised. Effective Jan. 1, 1984, all events were to be submitted in accordance with 10 CFR 50.73 of the Code of Federal Regulations. Report NUREG-1022, Licensee Event Report System-Description of System and Guidelines for Reporting, describes the guidelines on reportability of events. This article summarizes the reporting requirements as presented in NUREG-1022, high-lights differences in data reported between the revised and previous LER systems, and presents results from a preliminary assessment of LERs submitted under the revised LER reporting system

  14. Safety culture

    International Nuclear Information System (INIS)

    Keen, L.J.

    2003-01-01

    Safety culture has become a topic of increasing interest for industry and regulators as issues are raised on safety problems around the world. The keys to safety culture are organizational effectiveness, effective communications, organizational learning, and a culture that encourages the identification and resolution of safety issues. The necessity of a strong safety culture places an onus on all of us to continually question whether the safety measures already in place are sufficient, and are being applied. (author)

  15. Interactive Instruction in Bayesian Inference

    DEFF Research Database (Denmark)

    Khan, Azam; Breslav, Simon; Hornbæk, Kasper

    2018-01-01

    An instructional approach is presented to improve human performance in solving Bayesian inference problems. Starting from the original text of the classic Mammography Problem, the textual expression is modified and visualizations are added according to Mayer’s principles of instruction. These pri......An instructional approach is presented to improve human performance in solving Bayesian inference problems. Starting from the original text of the classic Mammography Problem, the textual expression is modified and visualizations are added according to Mayer’s principles of instruction....... These principles concern coherence, personalization, signaling, segmenting, multimedia, spatial contiguity, and pretraining. Principles of self-explanation and interactivity are also applied. Four experiments on the Mammography Problem showed that these principles help participants answer the questions...... that an instructional approach to improving human performance in Bayesian inference is a promising direction....

  16. 76 FR 67456 - Common Formats for Patient Safety Data Collection and Event Reporting

    Science.gov (United States)

    2011-11-01

    ... information regarding the quality and safety of health care delivery. The Patient Safety Act (at 42 U.S.C... Formats in order to facilitate standardized data collection and improve the safety and quality of health... conjunction with an interagency Federal Patient Safety Work Group (PSWG), revises and refines the Common...

  17. Quantum interaction. Revised selected papers

    Energy Technology Data Exchange (ETDEWEB)

    Song, Dawei; Zhang, Peng; Wang, Lei [Aberdeen Univ. (United Kingdom). School of Computing; Melucci, Massimo [Padua Univ., Padova (Italy). Dept. of Information Engineering; Frommholz, Ingo [Bedfordshire Univ. (United Kingdom); Arafat, Sachi (eds.) [Glasgow Univ. (United Kingdom). School of Computing Science

    2011-07-01

    This book constitutes the thoroughly refereed post-conference proceedings of the 5th International Symposium on Quantum Interaction, QI 2011, held in Aberdeen, UK, in June 2011. The 26 revised full papers and 6 revised poster papers, presented together with 1 tutorial and 1 invited talk were carefully reviewed and selected from numerous submissions during two rounds of reviewing and improvement. The papers show the cross-disciplinary nature of quantum interaction covering topics such as computation, cognition, mechanics, social interaction, semantic space and information representation and retrieval. (orig.)

  18. HEDR modeling approach: Revision 1

    International Nuclear Information System (INIS)

    Shipler, D.B.; Napier, B.A.

    1994-05-01

    This report is a revision of the previous Hanford Environmental Dose Reconstruction (HEDR) Project modeling approach report. This revised report describes the methods used in performing scoping studies and estimating final radiation doses to real and representative individuals who lived in the vicinity of the Hanford Site. The scoping studies and dose estimates pertain to various environmental pathways during various periods of time. The original report discussed the concepts under consideration in 1991. The methods for estimating dose have been refined as understanding of existing data, the scope of pathways, and the magnitudes of dose estimates were evaluated through scoping studies

  19. Quantum interaction. Revised selected papers

    International Nuclear Information System (INIS)

    Song, Dawei; Zhang, Peng; Wang, Lei; Arafat, Sachi

    2011-01-01

    This book constitutes the thoroughly refereed post-conference proceedings of the 5th International Symposium on Quantum Interaction, QI 2011, held in Aberdeen, UK, in June 2011. The 26 revised full papers and 6 revised poster papers, presented together with 1 tutorial and 1 invited talk were carefully reviewed and selected from numerous submissions during two rounds of reviewing and improvement. The papers show the cross-disciplinary nature of quantum interaction covering topics such as computation, cognition, mechanics, social interaction, semantic space and information representation and retrieval. (orig.)

  20. Medical writing, revising and editing

    DEFF Research Database (Denmark)

    Pilegaard, Morten

    2006-01-01

    The globalization of science makes medical writing, editing and revision a rapidly growing field of linguistic study and practice. Medical science texts are written according to uniform, general guidelines and medical genres have become highly conventionalized in terms of structure and linguistic...... form. Medical editing often takes the form of peer review and mainly addresses issues of contents and overall validity. Medical revision incorporates the checking of the macrostructure and the microstructure of the text, its language and style and its suitability for the target reader or client...

  1. Revising Nabokov Revising”

    Directory of Open Access Journals (Sweden)

    Marie Bouchet

    2010-10-01

    Full Text Available Nabokov revised his works as he translated them and, on another plane, canon revisionism has been having its backlash and provoked other refracting waves. The purpose of the conference was to advance Nabokov studies through the discussion of how our view of Nabokov’s standing and his works today should be revised, especially after the publication of The Original of Laura. However the conference was not confined to just this theme, since “revising” is a word rich with implications. To borrow s...

  2. Licensing safety critical software

    International Nuclear Information System (INIS)

    Archinoff, G.H.; Brown, R.A.

    1990-01-01

    Licensing difficulties with the shutdown system software at the Darlington Nuclear Generating Station contributed to delays in starting up the station. Even though the station has now been given approval by the Atomic Energy Control Board (AECB) to operate, the software issue has not disappeared - Ontario Hydro has been instructed by the AECB to redesign the software. This article attempts to explain why software based shutdown systems were chosen for Darlington, why there was so much difficulty licensing them, and what the implications are for other safety related software based applications

  3. 77 FR 74010 - Proposed Changes to FCC Form 499-A, FCC Form 499-Q, and Accompanying Instructions

    Science.gov (United States)

    2012-12-12

    ... changed to ``2012.'' 4. Web Pages. Hyperlinks were revised as appropriate throughout the Form 499-A... identification number (EIN) for the filer's holding company. 10. Definition of Affiliate. The definition of the... Instructions. This definition is the same as the definition contained in Appendix A of the Form 499-A...

  4. DEVELOPMENT AND EVALUATION OF INSTRUCTIONAL UNITS FOR TEACHING PROFIT-MAXIMIZING PRINCIPLES IN VOCATIONAL AGRICULTURE. FINAL REPORT.

    Science.gov (United States)

    BARKER, RICHARD L.

    THE WRITING, EVALUATION, AND REVISION OF THE INSTRUCTIONAL UNITS WERE COMPLETED ON SCHEDULE AND A SUMMARY OF THE STUDY WILL BE PUBLISHED IN THE LOCAL "RESEARCH SERIES IN AGRICULTURAL EDUCATION" TO BE SENT TO ALL STATES. THE DEVELOPMENT AND FINDINGS OF THE STUDY WILL BE INCLUDED IN "AGRICULTURAL EDUCATION MAGAZINE." SAMPLE COPIES OF THE UNIT WERE…

  5. ARS-Media for excel instruction manual

    Science.gov (United States)

    ARS-Media for Excel Instruction Manual is the instruction manual that explains how to use the Excel spreadsheet ARS-Media for Excel application. ARS-Media for Excel Instruction Manual is provided as a pdf file....

  6. Revised health and safety compliance model for the Ghanaian ...

    African Journals Online (AJOL)

    The construction industry in Ghana is faced with employees' negligence in obeying rules and ... In some cases few variables were combined with other factors to form new factors. .... gives a framework to reduce hazards at workplace and this should be ..... An empirical Study of e-recruitment technology adoption in Malaysia.

  7. Material Safety Data Sheet, MSDS D0211, Revision 5

    National Research Council Canada - National Science Library

    1998-01-01

    Partly Contents: Chemical Product Identification, Composition and Information on ingredients, First Aid Measures, Fire-Fighting Measures, Accidental Release Measures, Handling and Storage, Exposure Controls, Personal...

  8. Safety standards of IAEA for management systems

    International Nuclear Information System (INIS)

    Vincze, P.

    2005-01-01

    IAEA has developed a new series of safety standards which are assigned for constitution of the conditions and which give the instruction for setting up the management systems that integrate the aims of safety, health, life environment and quality. The new standard shall replace IAEA 50-C-Q - Requirements for security of the quality for safety in nuclear power plants and other nuclear facilities as well as 14 related safety instructions mentioned in the Safety series No. 50-C/SG-Q (1996). When developing of this complex, integrated set of requirements for management systems, the IAEA requirements 50-C-Q (1996) were taken into consideration as well as the publications developed within the International organisation for standardization (ISO) ISO 9001:2000 and ISO14001: 1996. The experience of European Union member states during the development, implementation and improvement of the management systems were also taken into consideration

  9. Handbook on criticality. Vol. 1. Criticality and nuclear safety; Handbuch zur Kritikalitaet. Bd. 1. Kritikalitaet und nukleare Sicherheit

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2015-04-15

    This handbook was prepared primarily with the aim to provide information to experts in industry, authorities or research facilities engaged in criticality-safety-related problems that will allow an adequate and rapid assessment of criticality safety issues already in the planning and preparation of nuclear facilities. However, it is not the intention of the authors of the handbook to offer ready solutions to complex problems of nuclear safety. Such questions have to remain subject to an in-depth analysis and assessment to be carried out by dedicated criticality safety experts. Compared with the previous edition dated December 1998, this handbook has been further revised and supplemented. The proven basic structure of the handbook remains unchanged. The handbook follows in some ways similar criticality handbooks or instructions published in the USA, UK, France, Japan and the former Soviet Union. The expedient use of the information given in this handbook requires a fundamental understanding of criticality and the terminology of nuclear safety. In Vol. 1, ''Criticality and Nuclear Safety'', therefore, first the most important terms and fundamentals are introduced and explained. Subsequently, experimental techniques and calculation methods for evaluating criticality problems are presented. The following chapters of Vol. 1 deal i. a. with the effect of neutron reflectors and absorbers, neutron interaction, measuring methods for criticality, and organisational safety measures and provide an overview of criticality-relevant operational experience and of criticality accidents and their potential hazardous impact. Vol. 2 parts 1 and 2 finally compile criticality parameters in graphical and tabular form. The individual graph sheets are provided with an initially explained set of identifiers, to allow the quick finding of the information of current interest. Part 1 includes criticality parameters for systems with {sup 235}U as fissile material, while part

  10. Infection as a Background to Safety: Source Material for Teaching.

    Science.gov (United States)

    Wyatt, H. V.

    1986-01-01

    Offers selections from papers which illustrate accidents, epidemics, and bad practices which could be used as background material for lessons on laboratory safety. Advocates the need for instruction on pathogenicity and infectivity. (ML)

  11. An evaluation of the uranium mine radiation safety course

    International Nuclear Information System (INIS)

    1984-07-01

    The report evaluates the Uranium Mine Radiation Safety Course focussing on the following areas: effectivenss of the course; course content; instructional quality; course administration. It notes strengths and weaknesses in these areas and offers preliminary recommendations for future action

  12. Bulletin 2005-12 : revised Alberta pipeline regulation issued

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-05-31

    A revised Pipeline Regulation has been issued and is currently available on the Alberta Energy and Utilities Board (EUB) website. Changes to the regulation reflect bothchanges in EUB regulatory policy and processes and technological improvements. Goals of the revision include improvements in overall pipeline performance, and the implementation of recommendations derived from the Public Safety and Sour Gas Committee concerning sour gas pipeline safety. The regulation was re-organized for greater clarity, and structured into 11 parts. Issues concerning the transition to the revised regulation were presented. The summary of notable administrative changes included clarifications of when a pipeline application is not required; when ABSA approval is required for steam lines; situations for which low-pressure natural gas lines must be licensed; and emergency response requirements. Technical clarifications include requirements for pipeline operations and maintenance manuals; composite materials; limitations on amounts of H{sub 2}S in polymeric pipe; pressure mismatches; approval for testing with gaseous media; venting of small volumes of raw gas; right-of-way surveillance; inspection of surface construction activities; annual corrosion evaluations; registering of pipelines and excavators in controlled areas with Alberta One-Call; ground disturbance training; restoration and signage maintenance on abandoned pipelines; sour service steel pipelines; unused pipelines and abandoned pipelines; and remediation of stub ends in operating pipelines.

  13. Preliminary hazards analysis of thermal scrap stabilization system. Revision 1

    International Nuclear Information System (INIS)

    Lewis, W.S.

    1994-01-01

    This preliminary analysis examined the HA-21I glovebox and its supporting systems for potential process hazards. Upon further analysis, the thermal stabilization system has been installed in gloveboxes HC-21A and HC-21C. The use of HC-21C and HC-21A simplified the initial safety analysis. In addition, these gloveboxes were cleaner and required less modification for operation than glovebox HA-21I. While this document refers to glovebox HA-21I for the hazards analysis performed, glovebox HC-21C is sufficiently similar that the following analysis is also valid for HC-21C. This hazards analysis document is being re-released as revision 1 to include the updated flowsheet document (Appendix C) and the updated design basis (Appendix D). The revised Process Flow Schematic has also been included (Appendix E). This Current revision incorporates the recommendations provided from the original hazards analysis as well. The System Design Description (SDD) has also been appended (Appendix H) to document the bases for Safety Classification of thermal stabilization equipment

  14. Nuclear Regulatory Commission Human Factors Program Plan. Revision 2

    International Nuclear Information System (INIS)

    1986-04-01

    This document is the Second Annual Revision to the NRC Human Factors Program Plan. The first edition was published in August 1983. Revision 1 was published in July of 1984. Purpose of the NRC Human Factors Program is to ensure that proper consideration is given to human factors in the design and operation of nuclear power plants. This document describes the plans of the Office of Nuclear Reactor Regulation to address high priority human factors concerns of importance to reactor safety in FY 1986 and FY 1987. Revision 2 of the plan incorporates recent Commission decisions and policies bearing on the human factors aspects of reactor safety regulation. With a few exceptions, the principal changes from prior editions reflect a shift from developing new requirements to staff evaluation of industry progress in resolving human factors issues. The plan addresses seven major program elements: (1) Training, (2) Licensing Examinations, (3) Procedures, (4) Man-Machine Interface, (5) Staffing and Qualifications, (6) Management and Organization, and (7) Human Performance

  15. Failure of aseptic revision total knee arthroplasties.

    Science.gov (United States)

    Leta, Tesfaye H; Lygre, Stein Håkon L; Skredderstuen, Arne; Hallan, Geir; Furnes, Ove

    2015-02-01

    In Norway, the proportion of revision knee arthroplasties increased from 6.9% in 1994 to 8.5% in 2011. However, there is limited information on the epidemiology and causes of subsequent failure of revision knee arthroplasty. We therefore studied survival rate and determined the modes of failure of aseptic revision total knee arthroplasties. This study was based on 1,016 aseptic revision total knee arthroplasties reported to the Norwegian Arthroplasty Register between 1994 and 2011. Revisions done for infections were not included. Kaplan-Meier and Cox regression analyses were used to assess the survival rate and the relative risk of re-revision with all causes of re-revision as endpoint. 145 knees failed after revision total knee arthroplasty. Deep infection was the most frequent cause of re-revision (28%), followed by instability (26%), loose tibial component (17%), and pain (10%). The cumulative survival rate for revision total knee arthroplasties was 85% at 5 years, 78% at 10 years, and 71% at 15 years. Revision total knee arthroplasties with exchange of the femoral or tibial component exclusively had a higher risk of re-revision (RR = 1.7) than those with exchange of the whole prosthesis. The risk of re-revision was higher for men (RR = 2.0) and for patients aged less than 60 years (RR = 1.6). In terms of implant survival, revision of the whole implant was better than revision of 1 component only. Young age and male sex were risk factors for re-revision. Deep infection was the most frequent cause of failure of revision of aseptic total knee arthroplasties.

  16. Nuclear Criticality Safety Data Book

    Energy Technology Data Exchange (ETDEWEB)

    Hollenbach, D. F. [Y-12 National Security Complex, Oak Ridge, TN (United States)

    2016-11-14

    The objective of this document is to support the revision of criticality safety process studies (CSPSs) for the Uranium Processing Facility (UPF) at the Y-12 National Security Complex (Y-12). This design analysis and calculation (DAC) document contains development and justification for generic inputs typically used in Nuclear Criticality Safety (NCS) DACs to model both normal and abnormal conditions of processes at UPF to support CSPSs. This will provide consistency between NCS DACs and efficiency in preparation and review of DACs, as frequently used data are provided in one reference source.

  17. Nuclear Criticality Safety Data Book

    International Nuclear Information System (INIS)

    Hollenbach, D. F.

    2016-01-01

    The objective of this document is to support the revision of criticality safety process studies (CSPSs) for the Uranium Processing Facility (UPF) at the Y-12 National Security Complex (Y-12). This design analysis and calculation (DAC) document contains development and justification for generic inputs typically used in Nuclear Criticality Safety (NCS) DACs to model both normal and abnormal conditions of processes at UPF to support CSPSs. This will provide consistency between NCS DACs and efficiency in preparation and review of DACs, as frequently used data are provided in one reference source.

  18. The nuclear liability conventions revised

    International Nuclear Information System (INIS)

    Reyners, P.

    2004-01-01

    The signature on 12 February 2004 of the Protocols amending respectively the 1960 Paris Convention and the 1963 Brussels Supplementary Convention was the second step of the process of modernisation of the international nuclear liability regime after the adoption in September 1997 of a Protocol revising the 1963 Vienna Convention and of a new Convention on Supplementary Compensation for Nuclear Damage. The common objective of the new instruments is to provide more funds to compensate a larger number of potential victims in respect of a broader range of damage. Another goal of the revision exercise was to maintain the compatibility between the Paris and Vienna based systems, a commitment enshrined in the 1988 Joint Protocol, as well as to ascertain that Paris/Brussels countries could also become a Party to the Convention on Supplementary Compensation. However, while generally consistent vis a vis the Joint Protocol, the provisions of the Paris and Vienna Conventions, as revised, differ on some significant aspects. Another remaining issue is whether the improved international nuclear liability regime will succeed in attracting in the future a larger number of countries, particularly outside Europe, and will so become truly universal. Therefore, the need for international co-operation to address these issues, to facilitate the adoption of new implementing legislation and to ensure that this special regime keeps abreast of economic and technological developments, is in no way diminished after the revision of the Conventions.(author)

  19. Concise revision of the Sarcospermataceae

    NARCIS (Netherlands)

    Lam, H.J.; Royen, van P.

    1952-01-01

    After the senior writer, together with W. W. Varossieau, had published a revision of this monogeneric family (Blumea III, 1938—’39 and IV, 1941), some more material has been examined by us and, moreover, some new species have been described. Thanks to the courtesy of Prof. F. Gagnepain of Paris, and

  20. Guidelines for Curriculum Development. Revised.

    Science.gov (United States)

    Kistler, K.; And Others

    The curriculum development process explained in this booklet was first implemented at College of the Redwoods in May 1986 and then revised in June 1989. First, information on the college's Curriculum Committee is provided, indicating that the committee was formed to plan credit/non-credit courses; evaluate and approve additions, modifications, or…

  1. Revised Accounting for Business Combinations

    Science.gov (United States)

    Wilson, Arlette C.; Key, Kimberly

    2008-01-01

    The Financial Accounting Standards Board (FASB) has recently issued Statement of Financial Accounting Standards No. 141 (Revised 2007) Business Combinations. The object of this Statement is to improve the relevance, representational faithfulness, and comparability of reported information about a business combination and its effects. This Statement…

  2. How Adults Learn. Revised Edition.

    Science.gov (United States)

    Kidd, J. R.

    The book's emphasis is on learning during the years of adulthood and examines present-day practice of adult education for practitioners. This revised edition brings up to date advances in such areas of learning as controversial theory; the effects of environment; sensory processes; intellectual capacities; motivation and attitude; transactional…

  3. A revision of the Paronychiinae

    NARCIS (Netherlands)

    Chaudhri, Mohammad Nazeer

    1968-01-01

    This study was undertaken, in April 1964, at the suggestion of Prof. Dr. J. Lanjouw. The need for such a revision, was, however, stressed by the authors of the subtribe, viz. PAX et K. HOFFMANN, who, while delimiting these genera, remarked that the Systematics of both the (main) genera of this

  4. Diet History Questionnaire: Database Revision History

    Science.gov (United States)

    The following details all additions and revisions made to the DHQ nutrient and food database. This revision history is provided as a reference for investigators who may have performed analyses with a previous release of the database.

  5. [Revised practice guideline 'Anaemia in midwifery practice'

    NARCIS (Netherlands)

    Beentjes, M.; Jans, S.M.P.J.

    2012-01-01

    The practice guideline of the Royal Dutch Organization of Midwives 'Anaemia in primary care midwifery practice' published in 2000, has recently been revised. The revised guideline takes physiological haemodilution during pregnancy into consideration and provides gestation specific reference values

  6. Revised Human Health Risk Assessment on Chlorpyrifos

    Science.gov (United States)

    We have revised our human health risk assessment and drinking water exposure assessment for chlorpyrifos that supported our October 2015 proposal to revoke all food residue tolerances for chlorpyrifos. Learn about the revised analysis.

  7. 75 FR 60485 - NRC Enforcement Policy Revision

    Science.gov (United States)

    2010-09-30

    ... NUCLEAR REGULATORY COMMISSION [NRC-2008-0497] NRC Enforcement Policy Revision AGENCY: Nuclear Regulatory Commission. ACTION: Policy statement. SUMMARY: The Nuclear Regulatory Commission (NRC or Commission) is publishing a major revision to its Enforcement Policy (Enforcement Policy or Policy) to...

  8. Reactor safety

    International Nuclear Information System (INIS)

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

    1985-01-01

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

  9. Updated safety analysis of ITER

    International Nuclear Information System (INIS)

    Taylor, Neill; Baker, Dennis; Ciattaglia, Sergio; Cortes, Pierre; Elbez-Uzan, Joelle; Iseli, Markus; Reyes, Susana; Rodriguez-Rodrigo, Lina; Rosanvallon, Sandrine; Topilski, Leonid

    2011-01-01

    An updated version of the ITER Preliminary Safety Report has been produced and submitted to the licensing authorities. It is revised and expanded in response to requests from the authorities after their review of an earlier version in 2008, to reflect enhancements in ITER safety provisions through design changes, to incorporate new and improved safety analyses and to take into account other ITER design evolution. The updated analyses show that changes to the Tokamak cooling water system design have enhanced confinement and reduced potential radiological releases as well as removing decay heat with very high reliability. New and updated accident scenario analyses, together with fire and explosion risk analyses, have shown that design provisions are sufficient to minimize the likelihood of accidents and reduce potential consequences to a very low level. Taken together, the improvements provided a stronger demonstration of the very good safety performance of the ITER design.

  10. Updated safety analysis of ITER

    Energy Technology Data Exchange (ETDEWEB)

    Taylor, Neill, E-mail: neill.taylor@iter.org [ITER Organization, CS 90 046, 13067 St Paul Lez Durance Cedex (France); Baker, Dennis; Ciattaglia, Sergio; Cortes, Pierre; Elbez-Uzan, Joelle; Iseli, Markus; Reyes, Susana; Rodriguez-Rodrigo, Lina; Rosanvallon, Sandrine; Topilski, Leonid [ITER Organization, CS 90 046, 13067 St Paul Lez Durance Cedex (France)

    2011-10-15

    An updated version of the ITER Preliminary Safety Report has been produced and submitted to the licensing authorities. It is revised and expanded in response to requests from the authorities after their review of an earlier version in 2008, to reflect enhancements in ITER safety provisions through design changes, to incorporate new and improved safety analyses and to take into account other ITER design evolution. The updated analyses show that changes to the Tokamak cooling water system design have enhanced confinement and reduced potential radiological releases as well as removing decay heat with very high reliability. New and updated accident scenario analyses, together with fire and explosion risk analyses, have shown that design provisions are sufficient to minimize the likelihood of accidents and reduce potential consequences to a very low level. Taken together, the improvements provided a stronger demonstration of the very good safety performance of the ITER design.

  11. Nuclear Criticality Safety Department Qualification Program

    International Nuclear Information System (INIS)

    Carroll, K.J.; Taylor, R.G.; Worley, C.A.

    1996-01-01

    The Nuclear Criticality Safety Department (NCSD) is committed to developing and maintaining a staff of highly qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. This document defines the Qualification Program to address the NCSD technical and managerial qualification as required by the Y-1 2 Training Implementation Matrix (TIM). This Qualification Program is in compliance with DOE Order 5480.20A and applicable Lockheed Martin Energy Systems, Inc. (LMES) and Y-1 2 Plant procedures. It is implemented through a combination of WES plant-wide training courses and professional nuclear criticality safety training provided within the department. This document supersedes Y/DD-694, Revision 2, 2/27/96, Qualification Program, Nuclear Criticality Safety Department There are no backfit requirements associated with revisions to this document

  12. Nuclear criticality safety handbook. Version 2

    International Nuclear Information System (INIS)

    1999-03-01

    The Nuclear Criticality Safety Handbook, Version 2 essentially includes the description of the Supplement Report to the Nuclear Criticality Safety Handbook, released in 1995, into the first version of Nuclear Criticality Safety Handbook, published in 1988. The following two points are new: (1) exemplifying safety margins related to modelled dissolution and extraction processes, (2) describing evaluation methods and alarm system for criticality accidents. Revision is made based on previous studies for the chapter that treats modelling the fuel system: e.g., the fuel grain size that the system can be regarded as homogeneous, non-uniformity effect of fuel solution, and burnup credit. This revision solves the inconsistencies found in the first version between the evaluation of errors found in JACS code system and criticality condition data that were calculated based on the evaluation. (author)

  13. Nuclear criticality safety department training implementation

    International Nuclear Information System (INIS)

    Carroll, K.J.; Taylor, R.G.; Worley, C.A.

    1996-01-01

    The Nuclear Criticality Safety Department (NCSD) is committed to developing and maintaining a staff of qualified personnel to meet the current and anticipated needs in Nuclear Criticality Safety (NCS) at the Oak Ridge Y-12 Plant. The NCSD Qualification Program is described in Y/DD-694, Qualification Program, Nuclear Criticality Safety Department This document provides a listing of the roles and responsibilities of NCSD personnel with respect to training and details of the Training Management System (TMS) programs, Mentoring Checklists and Checksheets, as well as other documentation utilized to implement the program. This document supersedes Y/DD-696, Revision 2, dated 3/27/96, Training Implementation, Nuclear Criticality Safety Department. There are no backfit requirements associated with revisions to this document

  14. Revision de los principales modelos de diseño instruccional

    Directory of Open Access Journals (Sweden)

    Francisco Javier Jardines Garza

    2011-07-01

    Full Text Available The intention of this document is to describe and to analyze the taxonomy of Instructional Development models (ID elaborated by Kent L. Gustafson and Robert Maribe Branch (2002. A taxonomy of ID models is useful because it allows to identify and to analyze in a more expeditious way each model and help us to consider which can be more useful in the application in different situation. Three categories in the classification settled down of ID: a Instruction in the classroom, b products for implementation by other users, and c instructional systems more extensive and complexes directed to problems or goals of an organization. In order to categorize the models, nine characteristics of the ID models are considered: characteristic product in terms of prepared instruction; resources entrusted to the developed attempt, if it is an individual effort or teamwork, the ability and experience that ID delay of the individual or the team, if the instructional materials are selected of the existing resources or represent a design and original product; the amount of realized preliminary analysis, the anticipated technological complexity of development atmospheres and gives, the amount of realized tests and revision, the amount of diffusion and pursuit that happens after the development. This taxonomy is not unique nor is the best one of the classifications ID models but it possible to be concluded that he is useful for the professionals, instructional and educating investigators, and designers in the development of its educative activities.

  15. SARP-II: Safeguards Accounting and Reports Program, Revised

    International Nuclear Information System (INIS)

    Kempf, C.R.

    1994-01-01

    A computer code, SARP (Safeguards Accounting and Reports Program) which will generate and maintain at-facility safeguards accounting records, and generate IAEA safeguards reports based on accounting data input by the user, was completed in 1990 by the Safeguards, Safety, and Nonproliferation Division (formerly the Technical Support Organization) at Brookhaven National Laboratory as a task under the US Program of Technical Support to IAEA safeguards. The code was based on a State System of Accounting for and Control of Nuclear Material (SSAC) for off-load refueled power reactor facilities, with model facility and safeguards accounting regime as described in IAEA Safeguards Publication STR-165. Since 1990, improvements in computing capabilities and comments and suggestions from users engendered revision of the original code. The result is an updated, revised version called SARP-II which is discussed in this report

  16. 242-A evaporator safety analysis report

    International Nuclear Information System (INIS)

    Campbell, T.A.

    1998-01-01

    In compliance with DOE Orders, an update of the 242-A SAR has been prepared, as documented in the referenced ECN. Several categories of changes were identified for inclusion in this revision of the SAR. These categories will be utilized to simplify the discussion of the changes for this USQ document. However, it is important to note that no new tests or experiments were included in this revision of the SAR. Editorial changes and/or informational updates to Chapters 9 and 11 were included as part of this revision. However, no changes to Operational Safety Requirements (OSRs) contained in Chapter 11 were required. General categories of changes included in this revision are listed

  17. Humeral windows in revision total elbow arthroplasty.

    Science.gov (United States)

    Peach, Chris A; Salama, Amir; Stanley, David

    2016-04-01

    The use of cortical windows for revision elbow arthroplasty has not previously been widely reported. Their use aids safe revision of a well fixed humeral prosthesis and can be used in the setting of dislocation, periprosthetic fracture or aseptic loosening of the ulnar component. We describe our technique and results of cortical windows in the distal humerus for revision elbow arthroplasty surgery.

  18. A taxonomic revision of the genus Podocarpus

    NARCIS (Netherlands)

    Laubenfels, de D.J.

    1985-01-01

    In connection with the forthcoming revision of the Coniferae for the Flora Malesiana, the author thought it necessary to revise the genus Podocarpus. Although this genus has a substantial representation in Malesia (30 species), the revision is too involved to be appropriate with the Flora Malesiana

  19. 24 CFR 968.225 - Budget revisions.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 4 2010-04-01 2010-04-01 false Budget revisions. 968.225 Section... Fewer Than 250 Units) § 968.225 Budget revisions. (a) A PHA shall not incur any modernization cost in excess of the total HUD-approved CIAP budget. A PHA shall submit a budget revision, in a form prescribed...

  20. 7 CFR 3015.115 - Budget revisions.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 15 2010-01-01 2010-01-01 false Budget revisions. 3015.115 Section 3015.115..., DEPARTMENT OF AGRICULTURE UNIFORM FEDERAL ASSISTANCE REGULATIONS Programmatic Changes and Budget Revisions § 3015.115 Budget revisions. (a) Nonconstruction projects. (1) Except as provided in paragraph (a)(2) of...

  1. 48 CFR 15.307 - Proposal revisions.

    Science.gov (United States)

    2010-10-01

    ... AND CONTRACT TYPES CONTRACTING BY NEGOTIATION Source Selection 15.307 Proposal revisions. (a) If an... allow proposal revisions to clarify and document understandings reached during negotiations. At the... submit a final proposal revision. The contracting officer is required to establish a common cut-off date...

  2. Motivational Measure of the Instruction Compared: Instruction Based on the ARCS Motivation Theory vs Traditional Instruction in Blended Courses

    Science.gov (United States)

    Colakoglu, Ozgur M.; Akdemir, Omur

    2012-01-01

    The ARCS Motivation Theory was proposed to guide instructional designers and teachers who develop their own instruction to integrate motivational design strategies into the instruction. There is a lack of literature supporting the idea that instruction for blended courses if designed based on the ARCS Motivation Theory provides different…

  3. Sensitivity Studies on Revised PSA Model of KHNP Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lee, Hyun-Gyo; Hwang, Seok-Won; Shin, Tae-Young

    2016-01-01

    Korea also performed safety revaluation for all nuclear power plants led by Korean regulatory and elicited 49 improvement factor for plants. One of those factors is Severe Accident Management Guidelines (SAMG) development, KHNP decided to develop Low Power and Shutdown(LPSD) Probabilistic Safety Assessment (PSA) models and upgrade full power PSA models of all operating plants for enhancement of guideline quality. In this paper we discuss about the effectiveness of post Fukushima equipment and improvements of each plant based on the results of revised full power PSA and newly developed LPSD PSA. Through sensitivity analysis based on revised PSA models we confirmed that the facilities installed or planned to installation as follow-up measures of Fukushima accident helped to enhance the safety of nuclear power plants. These results will provide various technical insights to scheduled studies which evaluate effectiveness of Fukushima post action items and develop accident management guideline. Also it will contribute to improve nuclear power plants safety

  4. Sensitivity Studies on Revised PSA Model of KHNP Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hyun-Gyo; Hwang, Seok-Won; Shin, Tae-Young [KHNP, Daejeon (Korea, Republic of)

    2016-10-15

    Korea also performed safety revaluation for all nuclear power plants led by Korean regulatory and elicited 49 improvement factor for plants. One of those factors is Severe Accident Management Guidelines (SAMG) development, KHNP decided to develop Low Power and Shutdown(LPSD) Probabilistic Safety Assessment (PSA) models and upgrade full power PSA models of all operating plants for enhancement of guideline quality. In this paper we discuss about the effectiveness of post Fukushima equipment and improvements of each plant based on the results of revised full power PSA and newly developed LPSD PSA. Through sensitivity analysis based on revised PSA models we confirmed that the facilities installed or planned to installation as follow-up measures of Fukushima accident helped to enhance the safety of nuclear power plants. These results will provide various technical insights to scheduled studies which evaluate effectiveness of Fukushima post action items and develop accident management guideline. Also it will contribute to improve nuclear power plants safety.

  5. Evaluation on safety issues of SMART

    International Nuclear Information System (INIS)

    Kim, W. S.; Seol, K. W.; Yoon, Y. K.; Lee, J. H.

    2001-01-01

    Safety issues on the SMART were evaluated in the light of the compliance with the Ministerial Ordinance of Technical Requirements applying to Nuclear Installations, which was recently revised. Evaluation concludes that regulatory requirements associated with following items have to be developed as the licensing criteria for the SMART: (1) proving the safety of design or materials different form existing reactors; (2) coping with beyond design basis accidents; (3) rulemaking on the safety of reactor safeguard vessel ; (4) ensuring integrity of steam generator tubes; and (5) classifying equipment based on their safety significance. Appropriate actions including implementation of new requirements under development should be taken for safety issues such as diversity of reactivity control and in-service inspection of steam generator tubes that are not complied with the current Technical Requirements. Safety level of the SMART design will be evaluated further by the more detailed assessment according to the Technical Requirements, and additional safety issues will be identified and resolved, if it necessary

  6. Alkem instruction: Legal relief of a Federal State against instructions under the Atomic Energy Act issued by the Federal Government

    International Nuclear Information System (INIS)

    Steinberg, R.

    1987-01-01

    The German Federal Minister for the Environment, Protection of Nature, and Reactor Safety instructed the Hesse State Minister for Economics and Technology to grant the applications filed by Alkem GmbH for a first partial permit of the construction and operation of a fuel element factory, and to grant it on the basis of a draft working document discussed between the two ministries. The new feature is the refusal of the Hesse State Minister to follow these instructions. This has given rise to a conflict between the State and Federal Governments. The article deals with one aspect of the multifaceted legal controversy, i.e., the question of the possibilities of legal relief open to a Federal State against an instruction under the Atomic Energy Act issued by the Federal Government. First, the rank of this instruction within the scope of administration on behalf of the Federal Government will be discussed. Next, the central problem of the preconditions under which an instruction may violate rights of a Federal State will be investigated. Finally, the possibilities of litigation will be briefly referred to. (orig./HP) [de

  7. Site-Specific Waste Management Instruction - 100-DR-1 Group 2 Sites

    International Nuclear Information System (INIS)

    Jackson, R.W.

    1998-01-01

    This site-specific waste management instruction (SSWMI) provides guidance for the management of wastes that may be generated during the excavation and remediation of the 100-DR-1 Group 2 sites. The management of waste generated as a result of these activities will be as directed in this SSWMI. This SSWMI will be revised to incorporate guidance for management of wastes encountered that are not addressed in this SSWMI

  8. The Relationship among Elementary Teachers’ Mathematics Anxiety, Mathematics Instructional Practices, and Student Mathematics Achievement

    OpenAIRE

    Hadley, Kristin M.; Dorward, Jim

    2011-01-01

    Many elementary teachers have been found to have high levels of mathematics anxiety but the impact on student achievement was unknown. Elementary teachers (N = 692) completed the modified Mathematics Anxiety Rating Scale-Revised (Hopko, 2003) along with a questionnaire probing anxiety about teaching mathematics and current mathematics instructional practices. Student mathematics achievement data were collected for the classrooms taught by the teachers. A positive relationship was found betwee...

  9. Development of the methodology for application of revised source term to operating nuclear power plants in Korea

    International Nuclear Information System (INIS)

    Kang, M.S.; Kang, P.; Kang, C.S.; Moon, J.H.

    2004-01-01

    Considering the current trend in applying the revised source term proposed by NUREG-1465 to the nuclear power plants in the U.S., it is expected that the revised source term will be applied to the Korean operating nuclear power plants in the near future, even though the exact time can not be estimated. To meet the future technical demands, it is necessary to prepare the technical system including the related regulatory requirements in advance. In this research, therefore, it is intended to develop the methodology to apply the revised source term to operating nuclear power plants in Korea. Several principles were established to develop the application methodologies. First, it is not necessary to modify the existing regulations about source term (i.e., any back-fitting to operating nuclear plants is not necessary). Second, if the pertinent margin of safety is guaranteed, the revised source term suggested by NUREG-1465 may be useful to full application. Finally, a part of revised source term could be selected to application based on the technical feasibility. As the results of this research, several methodologies to apply the revised source term to the Korean operating nuclear power plants have been developed, which include: 1) the selective (or limited) application to use only some of all the characteristics of the revised source term, such as release timing of fission products and chemical form of radio-iodine and 2) the full application to use all the characteristics of the revised source term. The developed methodologies are actually applied to Ulchin 9 and 4 units and their application feasibilities are reviewed. The results of this research are used as either a manual in establishing the plan and the procedure for applying the revised source term to the domestic nuclear plant from the utility's viewpoint; or a technical basis of revising the related regulations from the regulatory body's viewpoint. The application of revised source term to operating nuclear

  10. 75 FR 36288 - Amended Safety Zone and Regulated Navigation Area, Chicago Sanitary and Ship Canal, Romeoville, IL

    Science.gov (United States)

    2010-06-25

    ...The Coast Guard is revising its safety zone and Regulated Navigation Area (RNA) on the Chicago Sanitary and Ship Canal (CSSC) near Romeoville, IL. This revised temporary interim rule reduces the areas covered by the safety zone and RNA, and places additional restrictions on vessels that may transit the RNA.

  11. Zoology by Self-Instruction

    Science.gov (United States)

    Roach, Keith; Hammond, Roger

    1976-01-01

    A historical account is given of how a conventional university first-year undergraduate course in zoology has been replaced by a self-instructional one. Advantages and problems are weighed, and successful student achievement and interest are described. (LBH)

  12. A Fallibilistic Model for Instruction

    Science.gov (United States)

    Dawson, A. J.

    1971-01-01

    Discusses models in inquiry and of instruction based on critical Fallibilistic philosophy, developed by Karl R. Popper, which holds that all knowledge grows by conjecture and refutation. Classroom applications of strategies which result from the model are presented. (JP)

  13. Instructional Style Meets Classroom Design.

    Science.gov (United States)

    Novelli, Joan

    1991-01-01

    Nine elementary teachers explain how they design their classrooms to match and support their instructional styles. The teachers focus on whole language programs, student portfolios, science activity set-ups, technology transformation, learning center strategies, and space utilization. (SM)

  14. Intelligent Tools and Instructional Simulations

    National Research Council Canada - National Science Library

    Murray, William R; Sams, Michelle; Belleville, Michael

    2001-01-01

    This intelligent tools and instructional simulations project was an investigation into the utility of a knowledge-based performance support system to support learning and on-task performance for using...

  15. Measurement control workshop instructional materials

    Energy Technology Data Exchange (ETDEWEB)

    Gibbs, Philip [Brookhaven National Lab. (BNL), Upton, NY (United States); Crawford, Cary [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); McGinnis, Brent [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Insolves LLC, Piketon, OH (United States)

    2014-04-01

    A workshop to teach the essential elements of an effective nuclear materials control and accountability (MC&A) programs are outlined, along with the modes of Instruction, and the roles and responsibilities of participants in the workshop.

  16. Measurement Control Workshop Instructional Materials

    International Nuclear Information System (INIS)

    Gibbs, Philip; Crawford, Cary; McGinnis, Brent

    2014-01-01

    A workshop to teach the essential elements of an effective nuclear materials control and accountability (MC&A) programs are outlined, along with the modes of Instruction, and the roles and responsibilities of participants in the workshop.

  17. Adaptive Explicitly Parallel Instruction Computing

    National Research Council Canada - National Science Library

    Talla, Surendranath

    2000-01-01

    .... With in this context, we ask ourselves the following questions. 1. Can application performance be improved if the compiler had the freedom to pick the instruction set on a per application basis? 2...

  18. NEEDLE REVISION WITH MITOMYCIN-C IN ENCAPSULATED BLEBS

    Directory of Open Access Journals (Sweden)

    R Zarei

    2008-08-01

    Full Text Available "nThe most common cause of failure during the first trimester after trabeculectomy is encapsulated bleb and needling bleb revision is a less invasive method in the management of refractory cases. The purpose of this study is to determine the efficacy and safety of mitomycin-C (MMC augmented bleb revision of failed filtration surgery. This study is a before-after (paired observation. 33 patients with failed trabeculectomy because of bleb encapsulation, whose intraocular pressure (IOP was not reduced under 21 mmHg despite of medications and digital massage , underwent needling bleb revision and subconjunctival injection of 0.1 ml MMC (0.4 mg/ml.The mean follow-up time was 9.24 ± 5.27 months (1-20 months. Statistical analysis of the data included the paired two-tailed Student's t test for preoperative and postoperative IOP and number of medications. 36 needling procedures (mean, 1.09 ± 0.21 revisions per eye were performed on 33 eyes. Patients were between 10-80 years old (mean, 45.67 ± 22.41 years and mean follow-up was 9.24 ± 5.27 months. IOP decreased from 29.06 ± 5.03 mmHg to 18.21 ± 6.76 mmHg at last follow-up (P= 0.000. Antiglaucoma medications decreased from 2.18 ± 0.58 to 1.36 ± 0.29 at last follow-up (P= 0.000.Overall, 6 (18.2% of 33 cases achieved a complete success and 20 (60.6% of cases achieved a qualified success. The complications of this procedure were subconjunctival hemorrhage (17 cases, hyphema (5 cases and conjunctival button hole (2 cases. Needling bleb revision with mitomycin-C appears to be an effective and relatively safe way to revive failed filtration surgery.

  19. Automotive Electronics. Teacher Edition (Revised).

    Science.gov (United States)

    Mackert, Howard C.; Heiserman, Russell L.

    This learning module addresses computers and their applications in contemporary automobiles. The text provides students with information on automotive microcomputers and hands-on activities that will help them see how semiconductors and digital logic devices fit into the modern repair facility. The module contains nine instructional units that…

  20. Revise of the law concerning prevention from radiation hazards due to radioisotopes, etc

    International Nuclear Information System (INIS)

    Sakamoto, Yoshiaki; Sendo, Muneaki

    2004-01-01

    The Law Concerning Prevention from Radiation Hazards due to Radioisotopes, etc. was revised in 2004. The regulation about disposal of RI waste was fixed at this revise of the law. Regulation of an application about the disposal of the RI waste was added to former radioactive waste control business. And regulation of confirmation of waste disposal by a regulation body was added. By this law revision, a necessary system for the RI waste disposal is ready. Furthermore, the Basic Safety Standard (BSS) and the following rationalization of related to regulation were introduced into the Law Concerning Prevention from Radiation Hazards due to Radioisotopes, etc. by this law revision. The regulation for a handling of radionuclides will be changed a lot due to the introduction of the BSS. (author)

  1. Rating Instructional Conversations: A Guide

    OpenAIRE

    Rueda, Robert; Goldenberg, Claude; Gallimore, Ronald

    1992-01-01

    The current focus on more effective ways to foster literacy in school-age children, especially language minority students, has led to the development of alternative instructional approaches. One such approach is the instructional conversation (IC), based on early work in the Hawaiian Kamehameha Elementary Education Project (KEEP), on neo-Vygotskian theory, and on recent classroom-based research on reading comprehension. The present report outlines preliminary efforts to operationaliz...

  2. PLE-based instruction concept

    Science.gov (United States)

    Javorcik, Tomas

    2017-11-01

    The paper is aimed at the description of a PLE (Personal Learning Environment)-based teaching model suitable for implementation in the instruction of upper primary school students. The paper describes the individual stages of the model and its use of ICT (Information and Communication Technologies) tools. The Personal Learning Environment is a form of instruction which allows for the meaningful use of information and communication technologies (including mobile technologies) in their entirety.

  3. Tritium control and accountability instructions

    International Nuclear Information System (INIS)

    Wall, W.R.; Cruz, S.L.

    1985-08-01

    This instruction describes the tritium accountability procedures practiced by the Tritium Research Laboratory, at Sandia National Laboratories, Livermore. The accountability procedures are based upon the Sandia National Laboratories, Livermore, Nuclear Materials Operations Manual, SAND83-8036. The Nuclear Materials Operations Manual describes accountability techniques which are in compliance with the Department of Energy 5630 series Orders, Code of Federal Regulations, and Sandia National Laboratories Instructions

  4. Tritium control and accountability instructions

    International Nuclear Information System (INIS)

    Wall, W.R.

    1981-03-01

    This instruction describes the tritium accountability procedures practiced by the Tritium Research Laboratory, Building 968 at Sandia National Laboratories, Livermore. The accountability procedures are based upon the Sandia National Laboratories, Livermore, Nuclear Materials Operations Manual, SAND78-8018. The Nuclear Materials Operations Manual describes accountability techniques which are in compliance with the Department of Energy Manual, Code of Federal Regulations, and Sandia National Laboratories Instructions

  5. IAEA safety fundamentals: the safety of nuclear installations and the defence in depth concept

    International Nuclear Information System (INIS)

    Aro, I.

    2005-01-01

    This presentation is a replica of the similar presentation provided by the IAEA Basic Professional Training Course on Nuclear Safety. The presentation utilizes the IAEA Safety Series document No. 110, Safety Fundamentals: the Safety of Nuclear Installations. The objective of the presentation is to provide the basic rationale for actions in provision of nuclear safety. The presentation also provides basis to understand national nuclear safety requirements. There are three Safety Fundamentals documents in the IAEA Safety Series: one for nuclear safety, one for radiation safety and one for waste safety. The IAEA is currently revising its Safety Fundamentals by combining them into one general Safety Fundamentals document. The IAEA Safety Fundamentals are not binding requirements to the Member States. But, a very similar text has been provided in the Convention on Nuclear Safety which is legally binding for the Member State after ratification by the Parliament. This presentation concentrates on nuclear safety. The Safety Fundamentals documents are the 'policy documents' of the IAEA Safety Standards Series. They state the basic objectives, concepts and principles involved in ensuring protection and safety in the development and application of atomic energy for peaceful purposes. They will state - without providing technical details and without going into the application of principles - the rationale for actions necessary in meeting Safety Requirements. Chapter 7 of this presentation describes the basic features of defence in depth concept which is referred to in the Safety Fundamentals document. The defence in depth concept is a key issue in reaching high level of safety specifically at the design stage but as the reader can see the extended concept also refers to the operational stage. The appendix has been taken directly from the IAEA Basic Professional Training Course on Nuclear Safety and applied to the Finnish conditions. The text originates from the references

  6. Formative research: pretesting, revising, and more pretesting.

    Science.gov (United States)

    Zimmerman, M; Steckel, L

    1985-01-01

    Thorough and extensive pretesting is the formative research technique that the Program for the Introduction and Adaptation of Contraceptive Technology (PIACT) and its sister organization, the Program for Appropriate Technology in Health (PATH), rely on to develop well-understood and culturally appropriate print materials. Formative research is defined as evaluation activities that occur during a project to determine if the objectives are being met and, if not, to modify the project's direction to ensure that they are. Before materials are finalized or printed, an interviewer should pretest them with representatives of the target population to determine if the intended message is being conveyed and if it is clear and acceptable to them. Pretesting should be done while the materials are still in an unfinished state so audience-generated alterations can be made easily. Revised materials also should be tested until they communicate the inforamtion as intended. Due to the fact that PIACT/PATH work with countries where large percentages of the population are illiterate, its motivational and instructional materials rely on pictures to convey the message. Often, pictures are augmented by a line or 2 of simple text in the local language. This text also requires careful pretesting. Examples from the field demonstrate the importance of pretesting to assure that print materials are appropriate to the group for whom they are being developed. The examples deal with sympbols, positive messages, the use of common objects, extraneous detail, messages about time, and text. Through pretesting, PIACT/PATH has learned that there can be a large discrepancy between what materials developers intend to convey and what the audience understands. Pretesting is an essential formative technique that builds upon information gathered during the materials development process, ensuring the message designer that the materials will effectively address the needs of the target audience.

  7. Safe Handling of Radioisotopes. First Edition with Revised Appendix I

    International Nuclear Information System (INIS)

    1966-01-01

    Under its Statute the International Atomic Energy Agency is empowered to provide for the application of standards of safety for protection against radiation to its own operations and to operations making use of assistance provided by it or with which it is otherwise directly associated. To this end authorities receiving such assistance are required to observe relevant health and safety measures prescribed by the Agency. As a first step, it was considered an urgent task to provide users of radioisotopes with a manual of practice for the safe handling of these substances. The first edition of such a manual was published in 1958 and represented the first of the 'Safety Series', a series of manuals and codes on health and safety published by the Agency. It was prepared after careful consideration of existing national and international codes of radiation safety by a group of international experts and in consultation with other international bodies. This edition presents the first revision. It incorporates in the Appendices the latest recommendations of the International Commission on Radiological Protection and extracts from the report of the Committee II of the I.C.R.P. on permissible dose for internal radiation. The Health Physics and Medical Addenda to this Manual, published as No. 2 and No. 3 in the Safety Series in 1960, give more complete advice to the user on specialized topics.

  8. Instructional Technology and Objectification

    Directory of Open Access Journals (Sweden)

    Bekir S. Gur

    2008-05-01

    Full Text Available Objectification refers to the way in which everything (including human beings is treated as an object, raw material, or resource to be manipulated and used. In this article, objectification refers to the way that education is often reduced to the packaging and delivery of information. A critique of objectification in instructional technology is presented. In the context of Heidegger’s critique of technology, the authors claim that objectification in education is metaphysical in the sense that the intelligibility (being of education is equated with ready-to-use packages, and thus is reduced to delivery and transmission of objects. The embodiment dimension of teaching and learning can help us in resisting this reduction. The authors argue that objectification increases bureaucratic control over the teaching process and deskills teachers; and by which teachers are proletarianized. The authors conclude that instructional designers should create structures in which a care relation and dialogue between students and teachers can take place. Résumé: L’objectification réfère à la façon dont tout (incluant les être humains est traité comme un objet, une matière première ou une ressource qui peut être manipulée et utilisée. Dans cet article, l’objectification réfère à la façon dont l’éducation est souvent réduite à la mise en boîte et à la livraison de l’information. Une critique de l’objectification en technologie éducative est présentée. Dans le contexte de la critique de la technologie par Heidegger, les auteurs prétendent que l’objectification en éducation est métaphysique dans le sens que l’intelligibilité (être de l’éducation équivaut à la mise en boîte prêt-à –utiliser, et se résume donc à la livraison et à la transmission d’objets. L’incarnation de l’enseignement et de l’apprentissage peuvent nous aider à résister à cette réduction. Les auteurs arguent que l

  9. The safety interlocking system at the NAC

    International Nuclear Information System (INIS)

    Visser, K.; Mostert, H.

    1984-01-01

    The central safety interlocking system (CSIS) controls the higher level of interlocking between the various cyclotron subsystems. It ensures the safe operation of the entire cyclotron facility as regards personnel safety and proper instrument operation. The system consists of a micro-processor with a ROM-based safety interlocking program, relay output modules providing ''safety OK'' instructions to all interlocked apparatus, alarm input modules connected to transducers providing binary alarm status signals and an interface to the central control computer. All solid state electronic components of the system are situated in a low level radiation area and are interfaced to cyclotron equipment by means of 24 V relays

  10. Technical specifications: Callaway Plant, Unit No. 1 (Docket No. STN 50-483). Appendix A to License No. NPF-30. Revision 1

    International Nuclear Information System (INIS)

    1984-10-01

    Revised specifications are presented concerning limiting safety system settings for control systems, power distribution, instrumentation, coolant system, emergency core cooling system, containment systems, plant systems, electrical systems, refueling operations, radioactive effluents, and radiation environmental monitoring

  11. Outlines of revised regulation standards for experimental research reactors

    International Nuclear Information System (INIS)

    Hohara, Shinya

    2015-01-01

    In response to the accident of TEPCO Fukushima Daiichi Nuclear Power Station, the government took actions through the revision of regulatory standards as well as the complete separation of regulation administrative department from promotion administrative department. The Nuclear and Industrial Safety Agency of the Ministry of Economy, Trade and Industry, which has been in charge of the regulations of commercial reactors, and the Office of Nuclear Regulations of the Ministry of Education, Culture, Sports, Science and Technology, which has been in charge of the regulations of reactors for experiment and research, were separated from both ministries, and integrated into the Nuclear Regulation Authority, which was newly established as the affiliated agency of the Ministry of the Environment. As for the revision of regulations and standards, the Nuclear Safety Commission was dismantled, and regulation enacting authority was given to the new Nuclear Regulation Authority, and the regulations that stipulated new regulatory standards were enacted. This paper outlines the contents of regulations related mainly to the reactors for experiment and research, and explains the following: (1) retroactive application of the new regulatory standards to existing reactor facilities, (2) examinations at the Nuclear Regulatory Agency, (3) procedures to confirm the compliance to the new standards, (4) seismic design classification, and (5) importance classification of safety function. (A.O.)

  12. Occupational safety meets radiation protection

    International Nuclear Information System (INIS)

    Severitt, S.; Oehm, J.; Sobetzko, T.; Kloth, M.

    2012-01-01

    The cooperation circle ''Synergies in operational Security'' is a joint working group of the Association of German Safety Engineers (VDSI) and the German-Swiss Professional Association for Radiation Protection (FS). The tasks of the KKSyS are arising from the written agreement of the two associations. This includes work on technical issues. In this regard, the KKSyS currently is dealing with the description of the interface Occupational Safety / Radiation Protection. ''Ignorance is no defense'' - the KKSyS creates a brochure with the working title ''Occupational Safety meets radiation protection - practical guides for assessing the hazards of ionizing radiation.'' The target groups are entrepreneurs and by them instructed persons to carry out the hazard assessment. Our aim is to create practical guides, simple to understand. The practical guides should assist those, who have to decide, whether an existing hazard potential through ionizing radiation requires special radiation protection measures or whether the usual measures of occupational safety are sufficient. (orig.)

  13. Intelligent Instructional Systems in Military Training.

    Science.gov (United States)

    Fletcher, J.D.; Zdybel, Frank

    Intelligent instructional systems can be distinguished from more conventional approaches by the automation of instructional interaction and choice of strategy. This approach promises to reduce the costs of instructional materials preparation and to increase the adaptability and individualization of the instruction delivered. Tutorial simulation…

  14. The main requirements of the International Basic Safety Standards

    International Nuclear Information System (INIS)

    Webb, G.A.M.

    1998-01-01

    The main requirements of the new international basic safety standards are discussed, including such topics as health effects of ionizing radiations, the revision of basic safety standards, the requirements for radiation protection practices, the requirements for intervention,and the field of regulatory infrastructures. (A.K.)

  15. Effects of ventilated safety helmets in a hot environment

    Science.gov (United States)

    G.A. Davis; E.D. Edmisten; R.E. Thomas; R.B. Rummer; D.D. Pascoe

    2001-01-01

    Forest workers are likely to remove head protection in hot and humid conditions because of thermal discomfort. However, a recent Occupational Safety and Health Administration (OSHA) regulation revision requires all workers in logging operations to wear safety helmets, thus creating a compliance problem. To determine which factors contribute to forest workers’ thermal...

  16. Training Course for Compliance Safety and Health Officers. Final Report.

    Science.gov (United States)

    McKnight, A. James; And Others

    The report describes revision of the Compliance Safety and Health Officers (CSHO) course for the Department of Labor, Occupational Safety and Health Administration (OSHA). The CSHO's job was analyzed in depth, in accord with OSHA standards, policies, and procedures. A listing of over 1,700 violations of OSHA standards was prepared, and specialists…

  17. 78 FR 11092 - Safety and Health Regulations for Construction

    Science.gov (United States)

    2013-02-15

    ... LABOR DEPARTMENT Occupational Safety and Health Administration 29 CFR Part 1926 Safety and Health Regulations for Construction CFR Correction In Title 29 of the Code of Federal Regulations, Part 1926, revised as of July 1, 2012, on page 225, in Sec. 1926.152, paragraph (c)(16) is added to read as follows: Sec...

  18. 46 CFR 28.270 - Instruction, drills, and safety orientation.

    Science.gov (United States)

    2010-10-01

    ... Lines or With More Than 16 Individuals On Board, or for Fish Tender Vessels Engaged in the Aleutian... outfit and a self-contained breathing apparatus, if the vessel is so equipped; (8) Making a voice radio...

  19. Guidelines for the review research reactor safety. Reference document for IAEA Integrated Safety Assessment of Research Reactors (INSARR)

    International Nuclear Information System (INIS)

    1997-01-01

    In 1992, the IAEA published new safety standards for research reactors as part of the set of publications considered by its Research Reactor Safety Programme (RRSP). This set also includes publications giving guidance for all safety aspects related to the lifetime of a research reactor. In addition, the IAEA has also revised the Safety Standards for radiation protection. Consequently, it was considered advisable to revise the Integrated Safety Assessment of Research Reactors (INSARR) procedures to incorporate the new requirements and guidance as well as to extend the scope of the safety reviews to currently operating research reactors. The present report is the result of this revision. The purpose of this report is to give guidance on the preparation, execution, reporting and follow-up of safety review mission to research reactors as conducted by the IAEA under its INSARR missions safety service. However, it will also be of assistance to operators and regulators in conducting: (a) ad hoc safety assessments of research reactors to address individual issues such as ageing or safety culture; and (b) other types of safety reviews such as internal and peer reviews and regulatory inspections

  20. 76 FR 32333 - Approval and Promulgation of Air Quality Implementation Plans; Pennsylvania; Revision to the...

    Science.gov (United States)

    2011-06-06

    ...) Program--Quality Assurance Protocol for the Safety Inspection Program in Non-I/M Counties AGENCY... Implementation Plan (SIP) revision submitted by the Commonwealth of Pennsylvania for the purpose of changing the...). Specifically, the Commonwealth is amending a provision of its prior SIP-approved I/M program to amend the...

  1. 77 FR 41190 - Revised Document Posted: NIOSH List of Antineoplastic and Other Hazardous Drugs in Healthcare...

    Science.gov (United States)

    2012-07-12

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention [Docket Number NIOSH-190] Revised Document Posted: NIOSH List of Antineoplastic and Other Hazardous Drugs in Healthcare Settings 2012, Correction AGENCY: National Institute for Occupational Safety and Health (NIOSH) of the...

  2. Method for environmental risk analysis (MIRA) revision 2007

    International Nuclear Information System (INIS)

    2007-04-01

    OLF's instruction manual for carrying out environmental risk analyses provides a united approach and a common framework for environmental risk assessments. This is based on the best information available. The manual implies standardizations of a series of parameters, input data and partial analyses that are included in the environmental risk analysis. Environmental risk analyses carried out according to the MIRA method will thus be comparable between fields and between companies. In this revision an update of the text in accordance with today's practice for environmental risk analyses and prevailing regulations is emphasized. Moreover, method adjustments for especially protected beach habitats have been introduced, as well as a general method for estimating environmental risk concerning fish. Emphasis has also been put on improving environmental risk analysis' possibilities to contribute to a better management of environmental risk in the companies (ml)

  3. Trust Revision for Conflicting Sources

    Science.gov (United States)

    2017-02-01

    strategy is to first revise a priori trust assignments as a function of the degree of conflict, before the evidence is fused. This paper focuses on the...practical trust transitivity seems to be idiosyncratic for humans and animals, with no true analogue among non- living forms (and in the physical world ...visiting a foreign country Alice is looking for a restaurant where the locals go, because she would like to avoid places overrun by tourists. She meets a

  4. Clean Air Act. Revision 5

    Energy Technology Data Exchange (ETDEWEB)

    1994-02-15

    This Reference Book contains a current copy of the Clean Air Act, as amended, and those regulations that implement the statute and appear to be most relevant to DOE activities. The document is provided to DOE and contractor staff for informational purposes only and should not be interpreted as legal guidance. This Reference Book has been completely revised and is current through February 15, 1994.

  5. Revised dietary guidelines for Koreans.

    Science.gov (United States)

    Jang, Young Ai; Lee, Haeng Shin; Kim, Bok Hee; Lee, Yoonna; Lee, Hae Jeung; Moon, Jae Jin; Kim, Cho-il

    2008-01-01

    With rapidly changing dietary environment, dietary guidelines for Koreans were revised and relevant action guides were developed. First, the Dietary Guidelines Advisory Committee was established with experts and government officials from the fields of nutrition, preventive medicine, health promotion, agriculture, education and environment. The Committee set dietary goals for Koreans aiming for a better nutrition state of all after a thorough review and analysis of recent information related to nutritional status and/or problems of Korean population, changes in food production/supply, disease pattern, health policy and agricultural policy. Then, the revised dietary guidelines were proposed to accomplish these goals in addition to 6 different sets of dietary action guides to accommodate specific nutrition and health problems of respective age groups. Subsequently, these guidelines and guides were subjected to the focus group review, consumer perception surveys, and a public hearing for general and professional comments. Lastly, the language was clarified in terms of public understanding and phraseology. The revised Dietary guidelines for Koreans are as follows: eat a variety of grains, vegetables, fruits, fish, meat, poultry and dairy products; choose salt-preserved foods less, and use less salt when you prepare foods; increase physical activity for a healthy weight, and balance what you eat with your activity; enjoy every meal, and do not skip breakfast; if you drink alcoholic beverages, do so in moderation; prepare foods properly, and order sensible amounts; enjoy our rice-based diet.

  6. Computer assisted instruction on "learning nutrition flags for deaf 5th grade and 6th grad students": effectiveness of instruction.

    Science.gov (United States)

    Srisorachatr, Suwat; Huadong, Yotsinee; Hudthagosol, Chatrapa; Danthanavanich, Suksiri

    2013-12-01

    Deaf students are of a number of under privilege group for whom there are limited resources for their use, related to health including nutrition. The purpose of this research was to create computer-assisted instruction for "nutrition flags" for 5 and 6th grade students. The content of nutrition included the concept of a healthy balance diets and portion sizes of each food group. The content and pictures for computer-assisted instruction came from existing curriculum, and focused on nutritional content. The contents in this instruction were divided into three units according to students' learning capacity. The story boards were developed by staff including nutritionists, Thai sign language interpreters, and deaf students. Then, the contents and nutrition vocabulary were translated into Thai sign language. After recording the sign language on video, this material was merged with the contents and converted into a computer program. The computer assisted instruction was tested with students from Nakon Pathom School for the Deaf The first trial was conducted with three students, the second with five students, and the third with 15 students during the academic year 2009. The computer- assisted instruction was revised until it met the standard criteria of 80/80. Effectiveness testing was carried out with 36 students for five consecutive days. On the first day, the pre-test was completed, and on days 2-4, the students performed self-study and completed the exercises for units 1-3, with 50 minutes spent on each unit. The post-test was completed on the last day. The study was conducted during the 2010 academic year Data analysis was performed using the t-test. The results showed an effectiveness of 81.85/82.22, which was higher than the standard criteria of 80/80. The post-test average score was higher than the pre-test average score with a statistical significance level at p < 0.0001. Suggestions for instruction for the deaf are that the length of the instruction in each

  7. Vaccine Safety

    Science.gov (United States)

    ... During Pregnancy Frequently Asked Questions about Vaccine Recalls Historical Vaccine Safety Concerns FAQs about GBS and Menactra ... CISA Resources for Healthcare Professionals Evaluation Current Studies Historical Background 2001-12 Publications Technical Reports Vaccine Safety ...

  8. SAFETY FIRST

    Institute of Scientific and Technical Information of China (English)

    2007-01-01

    Ensuring safety while peacefully utilizing nuclear energy is a top priority for China A fter a recent earthquake in Japan caused radioactive leaks at a nuclear power plant in Tokyo, the safety of nuclear energy has again aroused public attention.

  9. ITER safety

    International Nuclear Information System (INIS)

    Raeder, J.; Piet, S.; Buende, R.

    1991-01-01

    As part of the series of publications by the IAEA that summarize the results of the Conceptual Design Activities for the ITER project, this document describes the ITER safety analyses. It contains an assessment of normal operation effluents, accident scenarios, plasma chamber safety, tritium system safety, magnet system safety, external loss of coolant and coolant flow problems, and a waste management assessment, while it describes the implementation of the safety approach for ITER. The document ends with a list of major conclusions, a set of topical remarks on technical safety issues, and recommendations for the Engineering Design Activities, safety considerations for siting ITER, and recommendations with regard to the safety issues for the R and D for ITER. Refs, figs and tabs

  10. Water Safety

    Science.gov (United States)

    ... Staying Safe Videos for Educators Search English Español Water Safety KidsHealth / For Parents / Water Safety What's in ... remains your best measure of protection. Making Kids Water Wise It's important to teach your kids proper ...

  11. Revised radiation emergency procedures at Pakistan research reactor PINSTECH

    International Nuclear Information System (INIS)

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

    1984-12-01

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

  12. ITER Safety and Licensing

    International Nuclear Information System (INIS)

    Girard, J-.P; Taylor, N.; Garin, P.; Uzan-Elbez, J.; GULDEN, W.; Rodriguez-Rodrigo, L.

    2006-01-01

    The site for the construction of ITER has been chosen in June 2005. The facility will be implemented in Europe, south of France close to Marseille. The generic safety scheme is now under revision to adapt the design to the host country regulation. Even though ITER will be an international organization, it will have to comply with the French requirements in the fields of public and occupational health and safety, nuclear safety, radiation protection, licensing, nuclear substances and environmental protection. The organization of the central team together with its partners organized in domestic agencies for the in-kind procurement of components is a key issue for the success of the experimentation. ITER is the first facility that will achieve sustained nuclear fusion. It is both important for the experimental one-of-a-kind device, ITER itself, and for the future of fusion power plants to well understand the key safety issues of this potential new source of energy production. The main safety concern is confinement of the tritium, activated dust in the vacuum vessel and activated corrosion products in the coolant of the plasma-facing components. This is achieved in the design through multiple confinement barriers to implement the defence in depth approach. It will be demonstrated in documents submitted to the French regulator that these barriers maintain their function in all postulated incident and accident conditions. The licensing process started by examination of the safety options. This step has been performed by Europe during the candidature phase in 2002. In parallel to the final design, and taking into account the local regulations, the Preliminary Safety Report (RPrS) will be drafted with support of the European partner and others in the framework of ITER Task Agreements. Together with the license application, the RPrS will be forwarded to the regulatory bodies, which will launch public hearings and a safety review. Both processes must succeed in order to

  13. Safety of Nuclear Power Plants: Commissioning and Operation. Specific Safety Requirements (Arabic Edition)

    International Nuclear Information System (INIS)

    2017-01-01

    This publication is a revision of IAEA Safety Standards Series No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe commissioning, operation, and transition from operation to decommissioning of nuclear power plants. Over recent years there have been developments in areas such as long term operation of nuclear power plants, plant ageing, periodic safety review, probabilistic safety analysis review and risk informed decision making processes. It became necessary to revise the IAEA’s Safety Requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles. A review of Safety Requirements publications, initiated in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan, revealed no significant areas of weakness but resulted in a small set of amendments to strengthen the requirements and facilitate their implementation. These are contained in the present publication.

  14. Safety of Nuclear Power Plants: Commissioning and Operation. Specific Safety Requirements

    International Nuclear Information System (INIS)

    2017-01-01

    This publication is a revision of IAEA Safety Standards Series No. NS-R-2, Safety of Nuclear Power Plants: Operation, and has been extended to cover the commissioning stage. It describes the requirements to be met to ensure the safe commissioning, operation, and transition from operation to decommissioning of nuclear power plants. Over recent years there have been developments in areas such as long term operation of nuclear power plants, plant ageing, periodic safety review, probabilistic safety analysis review and risk informed decision making processes. It became necessary to revise the IAEA’s Safety Requirements in these areas and to correct and/or improve the publication on the basis of feedback from its application by both the IAEA and its Member States. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles. A review of Safety Requirements publications, initiated in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan, revealed no significant areas of weakness but resulted in a small set of amendments to strengthen the requirements and facilitate their implementation. These are contained in the present publication.

  15. Safety assessment and verification for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2004-01-01

    This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. The present publication is a revision of the IAEA Safety Guide on Management of Nuclear Power Plants for Safe Operation issued in 1984. It supplements Section 2 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation. Nuclear power technology is different from the customary technology of power generation from fossil fuel and by hydroelectric means. One major difference between the management of nuclear power plants and that of conventional generating plants is the emphasis that should be placed on nuclear safety, quality assurance, the management of radioactive waste and radiological protection, and the accompanying national regulatory requirements. This Safety Guide highlights the important elements of effective management in relation to these aspects of safety. The attention to be paid to safety requires that the management recognize that personnel involved in the nuclear power programme should understand, respond effectively to, and continuously search for ways to enhance safety in the light of any additional requirements socially and legally demanded of nuclear energy. This will help to ensure that safety policies that result in the safe operation of nuclear power plants are implemented and that margins of safety are always maintained. The structure of the organization, management standards and administrative controls should be such that there is a high degree of assurance that safety policies and decisions are implemented, safety is continuously enhanced and a strong safety culture is promoted and supported. The objective of this publication is to guide Member States in setting up an operating organization which facilitates the safe operation of nuclear power plants to a high level internationally. The second objective is to provide guidance on the most important organizational elements in order to contribute to a strong safety

  16. Safety assessment and verification for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2005-01-01

    This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. The present publication is a revision of the IAEA Safety Guide on Management of Nuclear Power Plants for Safe Operation issued in 1984. It supplements Section 2 of the Safety Requirements publication on Safety of Nuclear Power Plants: Operation. Nuclear power technology is different from the customary technology of power generation from fossil fuel and by hydroelectric means. One major difference between the management of nuclear power plants and that of conventional generating plants is the emphasis that should be placed on nuclear safety, quality assurance, the management of radioactive waste and radiological protection, and the accompanying national regulatory requirements. This Safety Guide highlights the important elements of effective management in relation to these aspects of safety. The attention to be paid to safety requires that the management recognize that personnel involved in the nuclear power programme should understand, respond effectively to, and continuously search for ways to enhance safety in the light of any additional requirements socially and legally demanded of nuclear energy. This will help to ensure that safety policies that result in the safe operation of nuclear power plants are implemented and that margins of safety are always maintained. The structure of the organization, management standards and administrative controls should be such that there is a high degree of assurance that safety policies and decisions are implemented, safety is continuously enhanced and a strong safety culture is promoted and supported. The objective of this publication is to guide Member States in setting up an operating organization which facilitates the safe operation of nuclear power plants to a high level internationally. The second objective is to provide guidance on the most important organizational elements in order to contribute to a strong safety

  17. Food safety

    Science.gov (United States)

    ... safety URL of this page: //medlineplus.gov/ency/article/002434.htm Food safety To use the sharing features on this page, please enable JavaScript. Food safety refers to the conditions and practices that preserve the quality of food. These practices prevent contamination and foodborne ...

  18. DWPF waste form compliance plan (Draft Revision)

    International Nuclear Information System (INIS)

    Plodinec, M.J.; Marra, S.L.

    1991-01-01

    The Department of Energy currently has over 100 million liters of high-level radioactive waste in storage at the Savannah River Site (SRS). In the late 1970's, the Department of Energy recognized that there were significant safety and cost advantages associated with immobilizing the high-level waste in a stable solid form. Several alternative waste forms were evaluated in terms of product quality and reliability of fabrication. This evaluation led to a decision to build the Defense Waste Processing Facility (DWPF) at SRS to convert the easily dispersed liquid waste to borosilicate glass. In accordance with the NEPA (National Environmental Policy Act) process, an Environmental Impact Statement was prepared for the facility, as well as an Environmental Assessment of the alternative waste forms, and issuance of a Record of Decision (in December, 1982) on the waste form. The Department of Energy, recognizing that start-up of the DWPF would considerably precede licensing of a repository, instituted a Waste Acceptance Process to ensure that these canistered waste forms would be acceptable for eventual disposal at a federal repository. This report is a revision of the DWPF compliance plan

  19. Good safety culture maintenance at Leningrad nuclear power plant

    International Nuclear Information System (INIS)

    Ardanov, A.

    1996-01-01

    The evidence in favour of the Leningrad NPP commitment to safety tasks, as the case is in the international practice, is The Safety Policy Statement document where safety is declared to be more significant than the power generation related issues, with the entire responsibility for the safety provision taken over by the operating utility. To avoid the situation when the stated safety tasks and policy remain only a declaration, the organizational structure of the operating utility was expanded to include The Safety Control Department and The Quality Control Department whose tasks encompass the control of the achieved safety level, development of recommendations, measures and actions aimed at the safety culture improvement, assessment and revision of the criteria and requirements to the personnel and management. Each individual at LNPP whose activity affects the plant safety has been familiarized with The Safety Policy Statement document

  20. Good safety culture maintenance at Leningrad nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Ardanov, A [Safety Control Dept., Leningrad Nuclear Power Plant, Leningrad (Russian Federation)

    1997-12-31

    The evidence in favour of the Leningrad NPP commitment to safety tasks, as the case is in the international practice, is The Safety Policy Statement document where safety is declared to be more significant than the power generation related issues, with the entire responsibility for the safety provision taken over by the operating utility. To avoid the situation when the stated safety tasks and policy remain only a declaration, the organizational structure of the operating utility was expanded to include The Safety Control Department and The Quality Control Department whose tasks encompass the control of the achieved safety level, development of recommendations, measures and actions aimed at the safety culture improvement, assessment and revision of the criteria and requirements to the personnel and management. Each individual at LNPP whose activity affects the plant safety has been familiarized with The Safety Policy Statement document.