Occupational Safety and Health Curriculum Manual.

Science.gov (United States)

Gourley, Frank A., Jr., Comp.

With the enactment of the Occupational Safety and Health Act of 1970, the need for manpower development in the field of industrial safety and hygiene has resulted in the development of a broad based program in Occupational Safety and Health. The manual provides information to administrators and instructors on a program of study in this field for…

Radiological Emergency Response Health and Safety Manual

Energy Technology Data Exchange (ETDEWEB)

D. R. Bowman

2001-05-01

This manual was created to provide health and safety (H&S) guidance for emergency response operations. The manual is organized in sections that define each aspect of H and S Management for emergency responses. The sections are as follows: Responsibilities; Health Physics; Industrial Hygiene; Safety; Environmental Compliance; Medical; and Record Maintenance. Each section gives guidance on the types of training expected for managers and responders, safety processes and procedures to be followed when performing work, and what is expected of managers and participants. Also included are generic forms that will be used to facilitate or document activities during an emergency response. These ensure consistency in creating useful real-time and archival records and help to prevent the loss or omission of information.

Highway Safety Program Manual: Volume 8: Alcohol in Relation to Highway Safety.

Science.gov (United States)

National Highway Traffic Safety Administration (DOT), Washington, DC.

Volume 8 of the 19-volume Highway Safety Program Manual (which provides guidance to State and local governments on preferred highway safety practices) concentrates on alcohol in relation to highway safety. The purpose and objectives of the alcohol program are outlined. Federal authority in the area of highway safety and general policies regarding…

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

Transuranic waste characterization sampling and analysis methods manual. Revision 1

International Nuclear Information System (INIS)

Suermann, J.F.

1996-04-01

This Methods Manual provides a unified source of information on the sampling and analytical techniques that enable Department of Energy (DOE) facilities to comply with the requirements established in the current revision of the Transuranic Waste Characterization Quality Assurance Program Plan (QAPP) for the Waste Isolation Pilot Plant (WIPP) Transuranic (TRU) Waste Characterization Program (the Program) and the WIPP Waste Analysis Plan. This Methods Manual includes all of the testing, sampling, and analytical methodologies accepted by DOE for use in implementing the Program requirements specified in the QAPP and the WIPP Waste Analysis Plan. The procedures in this Methods Manual are comprehensive and detailed and are designed to provide the necessary guidance for the preparation of site-specific procedures. With some analytical methods, such as Gas Chromatography/Mass Spectrometry, the Methods Manual procedures may be used directly. With other methods, such as nondestructive characterization, the Methods Manual provides guidance rather than a step-by-step procedure. Sites must meet all of the specified quality control requirements of the applicable procedure. Each DOE site must document the details of the procedures it will use and demonstrate the efficacy of such procedures to the Manager, National TRU Program Waste Characterization, during Waste Characterization and Certification audits

Activity Management System user reference manual. Revision 1

International Nuclear Information System (INIS)

Gates, T.A.; Burdick, M.B.

1994-01-01

The Activity Management System (AMS) was developed in response to the need for a simple-to-use, low-cost, user interface system for collecting and logging Hanford Waste Vitrification Plant Project (HWVP) activities. This system needed to run on user workstations and provide common user access to a database stored on a local network file server. Most important, users wanted a system that provided a management tool that supported their individual process for completing activities. Existing system treated the performer as a tool of the system. All AMS data is maintained in encrypted format. Users can feel confident that any activities they have entered into the database are private and that, as the originator, they retain sole control over who can see them. Once entered into the AMS database, the activities cannot be accessed by anyone other than the originator, the designated agent, or by authorized viewers who have been explicitly granted the right to look at specific activities by the originator. This user guide is intended to assist new AMS users in learning how to use the application and, after the initial learning process, will serve as an ongoing reference for experienced users in performing infrequently used functions. Online help screens provide reference to some of the key information in this manual. Additional help screens, encompassing all the applicable material in this manual, will be incorporated into future AMS revisions. A third, and most important, source of help is the AMS administrator(s). This guide describes the initial production version of AMS, which has been designated Revision 1.0

Sodium safety manual

International Nuclear Information System (INIS)

Hayes, D.J.; Gardiner, R.L.

1980-09-01

The sodium safety manual is based upon more than a decade of experience with liquid sodium at Berkeley Nuclear Laboratories (BNL). It draws particularly from the expertise and experience developed in the course of research work into sodium fires and sodium water reactions. It draws also on information obtained from the UKAEA and other sodium users. Many of the broad principles will apply to other Establishments but much of the detail is specific to BNL and as a consequence its application at other sites may well be limited. Accidents with sodium are at best unpleasant and at worst lethal in an extremely painful way. The object of this manual is to help prevent sodium accidents. It is not intended to give detailed advice on specific precautions for particular situations, but rather to set out the overall strategy which will ensure that sodium activities will be pursued safely. More detail is generally conveyed to staff by the use of local instructions known as Sodium Working Procedures (SWP's) which are not reproduced in this manual although a list of current SWP's is included. Much attention is properly given to the safe design and operation of larger facilities; nevertheless evidence suggests that sodium accidents most frequently occur in small-scale work particularly in operations associated with sodium cleaning and special care is needed in all such cases. (U.K.)

Development of a health and safety manual for emergency response operations

International Nuclear Information System (INIS)

Riland, C.A.; Junio, S.S.

2000-01-01

The Federal Radiological Monitoring and Assessment Center (FRMAC) Health and Safety Manual, which has been under development by a multi-agency group, is nearing completion and publication. The manual applies to offsite monitoring during a radiological accident or incident. Though written for multi-agency offsite monitoring activities (FRMAC), the manual is generic in nature and should be readily adaptable for other emergency response operations. Health and safety issues for emergency response situations often differ from those of normal operations. Examples of these differences and methodologies to address these issues are discussed. Challenges in manual development, including lack of regulatory and guidance documentation, are also discussed. One overriding principle in the Health and Safety Manual development is the overall reduction of risk, not just dose. The manual is broken into several chapters, which include Overview of Responsibities, Health Physics, Industrial Hygiene and Safey, Medical, and Environmental Compliance and Records. Included is a series of appendices, which presents additional information on forms and plans for default scenarios

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

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.

IAEA publishes first health and safety manual

Energy Technology Data Exchange (ETDEWEB)

NONE

1959-01-15

A 'Manual on the Safe Handling of Radioisotopes' was published in English on 15 Dec ember 1958 by the International Atomic Energy Agency. This is a comprehensive handbook of internationally compiled recommendations for users of radioisotopes. It covers organizational, medical and technical aspects of radiation safety practices. It is also the Agency's first technical publication. French, Russian and Spanish editions will appear shortly. The Manual should prove useful to all users of radioisotopes in industry, medicine, research, etc., but is directed mainly to small scale users who may not have access to other sources of information. The recommendations apply only to radioactivity surpassing the limit of 0,002 microcurie concentration per gram of material; or a total activity of more than 0,1 microcuries in the working areas; this limit is based on the most dangerous radioisotopes. The experts state that the limiting level might be higher for less dangerous isotopes, but recommend that all be treated as potentially dangerous. This would have educational value and avoid accidents caused by misidentification. The Manual also stressed that good radiation safety practices depend on effective organization and warns that even very competent workers sometimes ignore or forget important health and safety requirements.

IAEA publishes first health and safety manual

International Nuclear Information System (INIS)

1959-01-01

A 'Manual on the Safe Handling of Radioisotopes' was published in English on 15 Dec ember 1958 by the International Atomic Energy Agency. This is a comprehensive handbook of internationally compiled recommendations for users of radioisotopes. It covers organizational, medical and technical aspects of radiation safety practices. It is also the Agency's first technical publication. French, Russian and Spanish editions will appear shortly. The Manual should prove useful to all users of radioisotopes in industry, medicine, research, etc., but is directed mainly to small scale users who may not have access to other sources of information. The recommendations apply only to radioactivity surpassing the limit of 0,002 microcurie concentration per gram of material; or a total activity of more than 0,1 microcuries in the working areas; this limit is based on the most dangerous radioisotopes. The experts state that the limiting level might be higher for less dangerous isotopes, but recommend that all be treated as potentially dangerous. This would have educational value and avoid accidents caused by misidentification. The Manual also stressed that good radiation safety practices depend on effective organization and warns that even very competent workers sometimes ignore or forget important health and safety requirements

Spent Nuclear Fuel Project Cold Vacuum Drying Facility Operations Manual

International Nuclear Information System (INIS)

IRWIN, J.J.

1999-01-01

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-553, Spent Nuclear Fuel Project Final Safety Analysis Report Annex B--Cold Vacuum Drying Facility. The HNF-SD-SNF-DRD-002, 1999, (Cold Vacuum Drying Facility Design Requirements), Rev. 4. and the CVDF Final Design Report. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence and references to the CVDF System Design Descriptions (SDDs). This manual has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

Safety Training: "Manual Handling" course in September

CERN Multimedia

Safety Training, HSE Unit

2016-01-01

The next "Manual Handling" course will be given, in French, on 26 September 2016. This course is designed for anyone required to carry out manual handling of loads in the course of their work.   The main objective of this course is to adopt and apply the basic principles of physical safety and economy of effort. There are places available. If you are interested in following this course, please fill an EDH training request via our catalogue. 

Spent nuclear fuel project cold vacuum drying facility operations manual

International Nuclear Information System (INIS)

IRWIN, J.J.

1999-01-01

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

Spent Nuclear Fuel (SNF) Cold Vacuum Drying (CVD) Facility Operations Manual

Energy Technology Data Exchange (ETDEWEB)

IRWIN, J.J.

1999-07-02

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-553, Spent Nuclear Fuel Project Final Safety Analysis Report Annex B--Cold Vacuum Drying Facility. The HNF-SD-SNF-DRD-002, 1999, Cold Vacuum Drying Facility Design Requirements, Rev. 4, and the CVDF Final Design Report. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence and references to the CVDF System Design Descriptions (SDDs). This manual has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

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

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.

Spent Nuclear Fuel (SNF) Cold Vacuum Drying (CVD) Facility Operations Manual; FINAL

International Nuclear Information System (INIS)

IRWIN, J.J.

1999-01-01

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-553, Spent Nuclear Fuel Project Final Safety Analysis Report Annex B-Cold Vacuum Drying Facility. The HNF-SD-SNF-DRD-002, 1999, Cold Vacuum Drying Facility Design Requirements, Rev. 4, and the CVDF Final Design Report. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence and references to the CVDF System Design Descriptions (SDDs). This manual has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

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

Safety manual for civil engineering and building works of nuclear power plants

International Nuclear Information System (INIS)

1988-01-01

This manual lays down the various important considerations that go into safe design of civil structures for nuclear power plants. This manual identifies the design approach, quality assurance requirements and acceptance criteria that need to be observed to assure safety. Considerations on civil design having bearing on safety, during decommissioning are also indicated. (original). 37 refs., tabs

Nuclear criticality safety. Chapter 0530 of AEC manual

International Nuclear Information System (INIS)

2006-01-01

The programme objectives of this chapter of the U.S. Atomic Energy Commission manual on nuclear criticality safety are to protect the health and safety of the public and of the government and contractor personnel working in plants that handle fissionable material and to protect public and private property from the consequences of a criticality accident occurring in AEC-owned plants and other AEC-contracted activities involving fissionable materials

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 ...

Health and Safety Procedures Manual for hazardous waste sites

Energy Technology Data Exchange (ETDEWEB)

Thate, J.E.

1992-09-01

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

Principles and Practices of Occupational Safety and Health: Student Manual: Booklet One.

Science.gov (United States)

Occupational Safety and Health Administration, Washington, DC.

The manual is the first of six student manuals for use in a course on occupational health and safety for supervisory personnel. The manual contains lessons 1-3 of the 15 consecutively-numbered lessons, each of which contains study questions (and answers) interwoven with the text and review questions at the end of each section. Lesson 1 (three…

Principles and Practices of Occupational Safety and Health: Student Manual: Booklet Five.

Science.gov (United States)

Occupational Safety and Health Administration, Washington, DC.

The manual is the fifth of six student manuals for use in a course on occupational health and safety for supervisory personnel. The manual contains lessons 14 and 15 of the 15 consecutively-numbered lessons, each of which contains study questions (and answers) interwoven with the text and review questions at the end of each section. Lesson 14…

Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual

Energy Technology Data Exchange (ETDEWEB)

IRWIN, J.J.

2000-02-03

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of the Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the spent nuclear fuel project (SNFP) Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual

International Nuclear Information System (INIS)

IRWIN, J.J.

2000-01-01

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of the Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the spent nuclear fuel project (SNFP) Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

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

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.

Principles and Practices of Occupational Safety and Health: Administrator's Manual.

Science.gov (United States)

Occupational Safety and Health Administration, Washington, DC.

The manual guides an instructor in conducting a training course for first-line supervisors to familiarize them with six aspects relating to the Occupational Safety and Health Act of 1970: (1) requirements of the Act, (2) compliance with its standards, (3) identification of health and safety hazards, (4) correction of adverse conditions, (5) record…

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.''

Manual for environmental radiological surveillance

International Nuclear Information System (INIS)

Sumiya, Shuichi; Matsuura, Kenichi; Nakano, Masanao; Takeyasu, Masanori; Morisawa, Masato; Onuma, Toshimitsu; Fujita, Hiroki; Mizutani, Tomoko; Watanabe, Hajime; Sugai, Masamitsu

2010-03-01

Environmental radiation monitoring around the Tokai Reprocessing Plant has been conducted by the Nuclear Fuel Cycle Engineering Laboratories, based on 'Safety Regulations for the Reprocessing Plant of JAEA, Chapter IV - Environmental monitoring' and Environmental Radiation Monitoring Program decided by the Ibaraki prefectural government. The radiation monitoring installations and equipments were also prepared for emergency. This manual describes; (1) the installations of radiological measurement, (2) the installations of meteorological observation, and (3) environmental data processing system for executing the terrestrial environmental monitoring by Environmental Protection Section, Radiation Protection Department. The environmental monitoring has been operated through the manual published in 1993 (PNC TN8520 93-001). Then the whole articles were revised because the partially of installations and equipments having been updated in recent years. (author)

Manual on quality assurance for computer software related to the safety of nuclear power plants

International Nuclear Information System (INIS)

1988-01-01

The objective of the Manual is to provide guidance in the assurance of quality of specification, design, maintenance and use of computer software related to items and activities important to safety (hereinafter referred to as safety related) in nuclear power plants. This guidance is consistent with, and supplements, the requirements and recommendations of Quality Assurance for Safety in Nuclear Power Plants: A Code of Practice, 50-C-QA, and related Safety Guides on quality assurance for nuclear power plants. Annex A identifies the IAEA documents referenced in the Manual. The Manual is intended to be of use to all those who, in any way, are involved with software for safety related applications for nuclear power plants, including auditors who may be called upon to audit management systems and product software. Figs

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.

Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR): Data manual. Part 3: Hardware component failure data; Volume 5, Revision 4

International Nuclear Information System (INIS)

Reece, W.J.; Gilbert, B.G.; Richards, R.E.

1994-09-01

This data manual contains a hard copy of the information in the Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) Version 3.5 database, which is sponsored by the US Nuclear Regulatory Commission. NUCLARR was designed as a tool for risk analysis. Many of the nuclear reactors in the US and several outside the US are represented in the NUCLARR database. NUCLARR includes both human error probability estimates for workers at the plants and hardware failure data for nuclear reactor equipment. Aggregations of these data yield valuable reliability estimates for probabilistic risk assessments and human reliability analyses. The data manual is organized to permit manual searches of the information if the computerized version is not available. Originally, the manual was published in three parts. In this revision the introductory material located in the original Part 1 has been incorporated into the text of Parts 2 and 3. The user can now find introductory material either in the original Part 1, or in Parts 2 and 3 as revised. Part 2 contains the human error probability data, and Part 3, the hardware component reliability data

Occupational safety manual. 4. rev. ed.

International Nuclear Information System (INIS)

Skiba, R.

1979-01-01

With the rapid technical development and increasing life expectancy, protection against occupational hazards has become a central economic and social problem. Consultants and others responsible for occupational safety should not only be interested in their work but also have sufficient basic knowledge. The complex subject is presented in a simplified and easily comprehensible manner, with particular regard to the practical side. The book is at the same time a textbook for basic training and a reference manual for the working practice. (orig./HP) [de

Helicopter Operations and Personnel Safety (Helirescue Manual). Fourth Edition.

Science.gov (United States)

Dalle-Molle, John

The illustrated manual includes information on various aspects of helicopter rescue missions, including mission management roles for key personnel, safety rules around helicopters, requests for helicopter support, sample military air support forms, selection of landing zones, helicopter evacuations, rescuer delivery, passenger unloading, crash…

Federal Radiological Monitoring and Assessment Center Health and Safety Manual

Energy Technology Data Exchange (ETDEWEB)

FRMAC Health and Safety Working Group

2012-03-20

This manual is a tool to provide information to all responders and emergency planners and is suggested as a starting point for all organizations that provide personnel/assets for radiological emergency response. It defines the safety requirements for the protection of all emergency responders. The intent is to comply with appropriate regulations or provide an equal level of protection when the situation makes it necessary to deviate. In the event a situation arises which is not addressed in the manual, an appropriate management-level expert will define alternate requirements based on the specifics of the emergency situation. This manual is not intended to pertain to the general public.

Manual on maintenance of systems and components important to safety

International Nuclear Information System (INIS)

1986-01-01

The Manual should serve as guidance at the plant management level for the maintenance of systems and components important to safety. It includes a detailed description of management systems, administrative controls and procedures. The Annexes contain examples of documents and practices adopted by Operating Organizations of some Member States. It is not the intention of this Manual to address the technical problem of how to maintain a particular component but rather to cover the programmatic aspects of maintenance. It also contains some aspects of surveillance and verification activities. The Manual makes only general statements about radiation protection provisions in connection with maintenance; detailed guidance can be found in other IAEA documents

Highway Safety Manual applied in Missouri - freeway/software : research summary.

Science.gov (United States)

2016-03-01

AASHTOs Highway Safety Manual (HSM) : includes models for freeway segments, speedchange : lanes (transitional area between mainline : and ramps), ramps, and interchange terminals. : These predictive models for freeway : interchanges need to be cal...

A feasibility study for Arizona's roadway safety management process using the Highway Safety Manual and SafetyAnalyst : final report.

Science.gov (United States)

2016-07-01

To enable implementation of the American Association of State Highway Transportation (AASHTO) Highway Safety Manual using : SaftetyAnalyst (an AASHTOWare software product), the Arizona Department of Transportation (ADOT) studied the data assessment :...

Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR): Data manual. Part 2: Human error probability (HEP) data; Volume 5, Revision 4

Energy Technology Data Exchange (ETDEWEB)

Reece, W.J.; Gilbert, B.G.; Richards, R.E. [EG and G Idaho, Inc., Idaho Falls, ID (United States)

1994-09-01

This data manual contains a hard copy of the information in the Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) Version 3.5 database, which is sponsored by the US Nuclear Regulatory Commission. NUCLARR was designed as a tool for risk analysis. Many of the nuclear reactors in the US and several outside the US are represented in the NUCLARR database. NUCLARR includes both human error probability estimates for workers at the plants and hardware failure data for nuclear reactor equipment. Aggregations of these data yield valuable reliability estimates for probabilistic risk assessments and human reliability analyses. The data manual is organized to permit manual searches of the information if the computerized version is not available. Originally, the manual was published in three parts. In this revision the introductory material located in the original Part 1 has been incorporated into the text of Parts 2 and 3. The user can now find introductory material either in the original Part 1, or in Parts 2 and 3 as revised. Part 2 contains the human error probability data, and Part 3, the hardware component reliability data.

Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR): Data manual. Part 2: Human error probability (HEP) data; Volume 5, Revision 4

International Nuclear Information System (INIS)

Reece, W.J.; Gilbert, B.G.; Richards, R.E.

1994-09-01

This data manual contains a hard copy of the information in the Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) Version 3.5 database, which is sponsored by the US Nuclear Regulatory Commission. NUCLARR was designed as a tool for risk analysis. Many of the nuclear reactors in the US and several outside the US are represented in the NUCLARR database. NUCLARR includes both human error probability estimates for workers at the plants and hardware failure data for nuclear reactor equipment. Aggregations of these data yield valuable reliability estimates for probabilistic risk assessments and human reliability analyses. The data manual is organized to permit manual searches of the information if the computerized version is not available. Originally, the manual was published in three parts. In this revision the introductory material located in the original Part 1 has been incorporated into the text of Parts 2 and 3. The user can now find introductory material either in the original Part 1, or in Parts 2 and 3 as revised. Part 2 contains the human error probability data, and Part 3, the hardware component reliability data

Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR): Data manual, Part 2: Human Error Probability (HEP) Data. Volume 5, Revision 4

International Nuclear Information System (INIS)

Reece, W.J.; Gilbert, B.G.; Richards, R.E.

1994-09-01

This data manual contains a hard copy of the information in the Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) Version 3.5 database, which is sponsored by the US Nuclear Regulatory Commission. NUCLARR was designed as a tool for risk analysis. Many of the nuclear reactors in the US and several outside the US are represented in the NUCLARR database. NUCLARR includes both human error probability estimates for workers at the plants and hardware failure data for nuclear reactor equipment. Aggregations of these data yield valuable reliability estimates for probabilistic risk assessments and human reliability analyses. The data manual is organized to permit manual searches of the information if the computerized version is not available. Originally, the manual was published in three parts. In this revision the introductory material located in the original Part 1 has been incorporated into the text of Parts 2 and 3. The user can now find introductory material either in the original Part 1, or in Parts 2 and 3 as revised. Part 2 contains the human error probability data, and Part 3, the hardware component reliability data

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.''

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...

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...

Environment, safety and health progress assessment manual

International Nuclear Information System (INIS)

1992-12-01

On June 27, 1989, the Secretary of Energy announced a 10-Point Initiative to strengthen environment, safety, and health (ES ampersand H) programs, and waste management activities at DOE production, research, and testing facilities. One of the points involved conducting dent Tiger Team Assessments of DOE operating facilities. The Office of Special independent Projects (OSP), EH-5, in the Office of the Assistant Secretary for Environment, Safety and Health, EH-1, was assigned the responsibility to conduct the Tiger Team Assessments. Through June 1992, a total of 35 Tiger Team Assessments were completed. The Secretary directed that Corrective Action Plans be developed and implemented to address the concerns identified by the Tiger Teams. In March 1991, the Secretary approved a plan for assessments that are ''more focused, concentrating on ES ampersand H management, ES ampersand H corrective actions, self-assessment programs, and root-cause related issues.'' In July 1991, the Secretary approved the initiation of ES ampersand H Progress Assessments, as a followup to the Tiger Team Assessments, and in the continuing effort to institutionalize the self-assessment process and line management accountability in the ES ampersand H areas. This manual documents the processes to be used to perform the ES ampersand H Progress Assessments. It was developed based upon the lessons learned from Tiger Team Assessments, the two pilot Progress Assessments, and Progress Assessments that have been completed. The manual will be updated periodically to reflect lessons learned or changes in policy

Laboratory Waste Disposal Manual. Revised Edition.

Science.gov (United States)

Stephenson, F. G., Ed.

This manual is designed to provide laboratory personnel with information about chemical hazards and ways of disposing of chemical wastes with minimum contamination of the environment. The manual contains a reference chart section which has alphabetical listings of some 1200 chemical substances with information on the health, fire and reactivity…

The 2018 Inter-agency field manual on reproductive health in humanitarian settings: revising the global standards.

Science.gov (United States)

Foster, Angel M; Evans, Dabney P; Garcia, Melissa; Knaster, Sarah; Krause, Sandra; McGinn, Therese; Rich, Sarah; Shah, Meera; Tappis, Hannah; Wheeler, Erin

2017-11-01

Since the 1990s, the Inter-agency field manual on reproductive health in humanitarian settings (IAFM) has provided authoritative guidance on reproductive health service provision during different phases of complex humanitarian emergencies. In 2018, the Inter-Agency Working Group on Reproductive Health in Crises will release a new edition of this global resource. In this article, we describe the collaborative and inter-sectoral revision process and highlight major changes in the 2018 IAFM. Key revisions to the manual include repositioning unintended pregnancy prevention within and explicitly incorporating safe abortion care into the Minimum Initial Service Package (MISP) chapter, which outlines a set of priority activities to be implemented at the outset of a humanitarian crisis; stronger guidance on the transition from the MISP to comprehensive sexual and reproductive health services; and the addition of a logistics chapter. In addition, the IAFM now places greater and more consistent emphasis on human rights principles and obligations, gender-based violence, and the linkages between maternal and newborn health, and incorporates a diverse range of field examples. We conclude this article with an outline of plans for releasing the 2018 IAFM and facilitating uptake by those working in refugee, crisis, conflict, and emergency settings.

NV/YMP radiological control manual, Revision 2

International Nuclear Information System (INIS)

Gile, A.L.

1996-11-01

The Nevada Test Site (NTS) and the adjacent Yucca Mountain Project (YMP) are located in Nye County, Nevada. The NTS has been the primary location for testing nuclear explosives in the continental US since 1951. Current activities include operating low-level radioactive and mixed waste disposal facilities for US defense-generated waste, assembly/disassembly of special experiments, surface cleanup and site characterization of contaminated land areas, and non-nuclear test operations such as controlled spills of hazardous materials at the hazardous Materials (HAZMAT) Spill Center (HSC). Currently, the major potential for occupational radiation exposure is associated with the burial of low-level nuclear waste and the handling of radioactive sources. Planned future remediation of contaminated land areas may also result in radiological exposures. The NV/YMP Radiological Control Manual, Revision 2, represents DOE-accepted guidelines and best practices for implementing Nevada Test Site and Yucca Mountain Project Radiation Protection Programs in accordance with the requirements of Title 10 Code of Federal Regulations Part 835, Occupational Radiation Protection. These programs provide protection for approximately 3,000 employees and visitors annually and include coverage for the on-site activities for both personnel and the environment. The personnel protection effort includes a DOE Laboratory Accreditation Program accredited dosimetry and personnel bioassay programs including in-vivo counting, routine workplace air sampling, personnel monitoring, and programmatic and job-specific As Low as Reasonably Achievable considerations

NV/YMP radiological control manual, Revision 2

Energy Technology Data Exchange (ETDEWEB)

Gile, A.L. [comp.

1996-11-01

The Nevada Test Site (NTS) and the adjacent Yucca Mountain Project (YMP) are located in Nye County, Nevada. The NTS has been the primary location for testing nuclear explosives in the continental US since 1951. Current activities include operating low-level radioactive and mixed waste disposal facilities for US defense-generated waste, assembly/disassembly of special experiments, surface cleanup and site characterization of contaminated land areas, and non-nuclear test operations such as controlled spills of hazardous materials at the hazardous Materials (HAZMAT) Spill Center (HSC). Currently, the major potential for occupational radiation exposure is associated with the burial of low-level nuclear waste and the handling of radioactive sources. Planned future remediation of contaminated land areas may also result in radiological exposures. The NV/YMP Radiological Control Manual, Revision 2, represents DOE-accepted guidelines and best practices for implementing Nevada Test Site and Yucca Mountain Project Radiation Protection Programs in accordance with the requirements of Title 10 Code of Federal Regulations Part 835, Occupational Radiation Protection. These programs provide protection for approximately 3,000 employees and visitors annually and include coverage for the on-site activities for both personnel and the environment. The personnel protection effort includes a DOE Laboratory Accreditation Program accredited dosimetry and personnel bioassay programs including in-vivo counting, routine workplace air sampling, personnel monitoring, and programmatic and job-specific As Low as Reasonably Achievable considerations.

Radiological Control Manual. Revision 0, January 1993

Energy Technology Data Exchange (ETDEWEB)

1993-04-01

This manual has been prepared by Lawrence Berkeley Laboratory to provide guidance for site-specific additions, supplements, and clarifications to the DOE Radiological Control Manual. The guidance provided in this manual is based on the requirements given in Title 10 Code of Federal Regulations Part 835, Radiation Protection for Occupational Workers, DOE Order 5480.11, Radiation Protection for Occupational Workers, and the DOE Radiological Control Manual. The topics covered are (1) excellence in radiological control, (2) radiological standards, (3) conduct of radiological work, (4) radioactive materials, (5) radiological health support operations, (6) training and qualification, and (7) radiological records.

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

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

HERMES II experimenters' manual (revised)

International Nuclear Information System (INIS)

Schuch, R.L.

1977-04-01

The HERMES II is a high-intensity laboratory photon source for gamma-ray radiation effects experiments as well as a high-energy pulsed electron beam generator for a variety of potential applications. The purpose of this manual is to serve as a basic source of information for prospective users of HERMES. Included is a brief discussion of the design and operation of the accelerator system as well as a summary of environmental data for x-ray operation and output characteristics for electron beam modes. The manual also contains a description of the HERMES experimental facilities, including geometry of the test cell, instrumentation and data collection capabilities, and services and support available to experimenters

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)

PFP MICON maintenance manual. Revision 1

International Nuclear Information System (INIS)

Silvan, G.R.

1995-01-01

This manual covers the use of maintenance displays, maintenance procedures, system alarms and common system failures. This manual is intended to supplement the MICON maintenance training not replace it. It also assumes that the user is familiar with the normal operation of the MICON A/S system. The MICON system is a distributed control computer and, among other things, controls the HVAC system for the Plutonium Finishing Plant

Quality assurance program manual for nuclear power plants. Volume I. Policies

International Nuclear Information System (INIS)

1976-01-01

The Consumers Power Company Quality Assurance Program Manual for Nuclear Power Plants consists of policies and procedures which comply with current NRC regulatory requirements and industry codes and standards in effect during the design, procurement, construction, testing, operation, refueling, maintenance, repair and modification activities associated with nuclear power plants. Specific NRC and industry documents that contain the requirements, including the issue dates in effect, are identified in each nuclear power plant's Safety Analysis Report. The requirements established by these documents form the basis for the Consumer Power Quality Assurance Program, which is implemented to control those structures, systems, components and operational safety actions listed in each nuclear power plant's Quality List (Q-List). As additional and revised requirements are issued by the NRC and professional organizations involved in nuclear activities, they will be reviewed for their impact on this manual, and changes will be made where considered necessary. CP Co 1--Consumers Power Company QA Program Topical Report is Volume I of this manual and contains Quality Assurance Program Policies applicable during all phases of nuclear power plant design, construction and operation

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...

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...

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

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.

Systematic safety evaluation of old nuclear power plants

International Nuclear Information System (INIS)

Dredemis, G.; Fourest, B.

1984-01-01

The French safety authorities have undertaken a systematic evaluation of the safety of old nuclear power plants. Apart from a complete revision of safety documents (safety analysis report, general operating rules, incident and accident procedures, internal emergency plan, quality organisation manual), this examination consisted of analysing the operating experience of systems frequently challenged and a systematic examination of the safety-related systems. This paper is based on an exercise at the Ardennes Nuclear Power Plant which has been in operation for 15 years. This paper also summarizes the main surveys and modifications relating to this power plant. (orig.)

Hanford External Dosimetry Technical Basis Manual PNL-MA-842

Energy Technology Data Exchange (ETDEWEB)

Rathbone, Bruce A.

2010-04-01

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at the U.S. Department of Energy (DOE) Hanford site. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with requirements of 10 CFR 835, the DOE Laboratory Accreditation Program, the DOE Richland Operations Office, DOE Office of River Protection, DOE Pacific Northwest Office of Science, and Hanford’s DOE contractors. The dosimetry system is operated by the Pacific Northwest National Laboratory (PNNL) Hanford External Dosimetry Program which provides dosimetry services to PNNL and all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since its inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNL’s Electronic Records & Information Capture Architecture database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving significant changes to all chapters in the document. Revision

Hanford External Dosimetry Technical Basis Manual PNL-MA-842

Energy Technology Data Exchange (ETDEWEB)

Rathbone, Bruce A.

2011-04-04

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at the U.S. Department of Energy (DOE) Hanford site. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with requirements of 10 CFR 835, the DOE Laboratory Accreditation Program, the DOE Richland Operations Office, DOE Office of River Protection, DOE Pacific Northwest Office of Science, and Hanford’s DOE contractors. The dosimetry system is operated by the Pacific Northwest National Laboratory (PNNL) Hanford External Dosimetry Program which provides dosimetry services to PNNL and all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since its inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNL’s Electronic Records & Information Capture Architecture database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving significant changes to all chapters in the document. Revision

Program desk manual for occupational safety and health -- U.S. Department of Energy Richland Operations, Office of Environment Safety and Health

International Nuclear Information System (INIS)

Musen, L.G.

1998-01-01

The format of this manual is designed to make this valuable information easily accessible to the user as well as enjoyable to read. Each chapter contains common information such as Purpose, Scope, Policy and References, as well as information unique to the topic at hand. This manual can also be provided on a CD or Hanford Internet. Major topics include: Organization and program for operational safety; Occupational medicine; Construction and demolition; Material handling and storage; Hoisting and rigging; Explosives; Chemical hazards; Gas cylinders; Electrical; Boiler and pressure vessels; Industrial fire protection; Industrial hygiene; and Safety inspection checklist

Program desk manual for occupational safety and health -- U.S. Department of Energy Richland Operations, Office of Environment Safety and Health

Energy Technology Data Exchange (ETDEWEB)

Musen, L.G.

1998-08-27

The format of this manual is designed to make this valuable information easily accessible to the user as well as enjoyable to read. Each chapter contains common information such as Purpose, Scope, Policy and References, as well as information unique to the topic at hand. This manual can also be provided on a CD or Hanford Internet. Major topics include: Organization and program for operational safety; Occupational medicine; Construction and demolition; Material handling and storage; Hoisting and rigging; Explosives; Chemical hazards; Gas cylinders; Electrical; Boiler and pressure vessels; Industrial fire protection; Industrial hygiene; and Safety inspection checklist.

Hanford External Dosimetry Technical Basis Manual PNL-MA-842

Energy Technology Data Exchange (ETDEWEB)

Rathbone, Bruce A.

2009-08-28

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL’s Hanford External Dosimetry Program (HEDP) which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee (HPDAC) which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNL’s Electronic Records & Information Capture Architecture (ERICA) database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document.

Environment, safety and health progress assessment manual

International Nuclear Information System (INIS)

1992-12-01

On June 27, 1989, the Secretary of Energy announced a 1O-Point Initiative to strengthen environment,safety, and health (ES ampersand H) programs, and waste management activities at involved conducting DOE production, research, and testing facilities. One of the points independent Tiger Team Assessments of DOE operating facilities. The Office of Special Projects (OSP), EH-5, in the Office of the Assistant Secretary for Environment, Safety and Health, EH-1, was assigned the responsibility to conduct the Tiger Team Assessments. Through June 1992, a total of 35 Tiger Team Assessments were completed. The Secretary directed that Corrective Action Plans be developed and implemented to address the concerns identified by the Tiger Teams. In March 1991, the Secretary approved a plan for assessments that are ''more focused, concentrating on ES ampersand H management, ES ampersand H corrective actions, self-assessment programs, and root-cause related issues.'' In July 1991, the Secretary approved the initiation of ES ampersand H Progress Assessments, as a followup to the Tiger Team Assessments, and in the continuing effort to institutionalize the self-assessment process and line management accountability in the ES ampersand H areas. This volume contains appendices to the Environment, Safety and Health Progress Assessment Manual

Fire and blast safety manual for fuel element manufacture

International Nuclear Information System (INIS)

Ensinger, U.; Koehler, B.; Mester, W.; Riotte, H.G.; Sehrbrock, H.W.

1988-01-01

The manual aims to enable people involved in the planning, operation, supervision, licensing or appraisal of fuel element factories to make a quick and accurate assessment of blast safety. In Part A, technical plant principles are shown, and a summary lists the flammable materials and ignition sources to be found in fuel element factories, together with theoretical details of what happens during a fire or a blast. Part B comprises a list of possible fires and explosions in fuel element factories and ways of preventing them. Typical fire and explosion scenarios are analysed more closely on the basis of experiments. Part B also contains a list and an assessment of actual fires and explosions which have occurred in fuel element factories. Part C contains safety measures to protect against fire and explosion, in-built fire safety, fire safety in plant design, explosion protection and measures to protect people from radiation and other hazards when fighting fires. A distinction is drawn between UO 2 , MOX and HTR fuel elements. (orig./DG) [de

Uranium hexafluoride: A manual of good handling practices. Revision 7

International Nuclear Information System (INIS)

1995-01-01

The United States Enrichment Corporation (USEC) is continuing the policy of the US Department of Energy (DOE) and its predecessor agencies in sharing with the nuclear industry their experience in the area of uranium hexafluoride (UF 6 ) shipping containers and handling procedures. The USEC has reviewed Revision 6 or ORO-651 and is issuing this new edition to assure that the document includes the most recent information on UF 6 handling procedures and reflects the policies of the USEC. This manual updates the material contained in earlier issues. It covers the essential aspects of UF 6 handling, cylinder filling and emptying, general principles of weighing and sampling, shipping, and the use of protective overpacks. The physical and chemical properties of UF 6 are also described. The procedures and systems described for safe handling of UF 6 presented in this document have been developed and evaluated during more than 40 years of handling vast quantities of UF 6 . With proper consideration for its nuclear properties, UF 6 may be safely handled in essentially the same manner as any other corrosive and/or toxic chemical

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

Nevada Test Site Radiological Control Manual

International Nuclear Information System (INIS)

2009-01-01

This document supersedes DOE/NV/11718--079, 'NV/YMP Radiological Control Manual,' Revision 5 issued in November 2004. Brief Description of Revision: A complete revision to reflect the recent changes in compliance requirements with 10 CFR 835, and for use as a reference document for Tenant Organization Radiological Protection Programs.

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.

Sandia SWiFT Wind Turbine Manual.

Energy Technology Data Exchange (ETDEWEB)

White, Jonathan; LeBlanc, Bruce Philip; Berg, Jonathan Charles; Bryant, Joshua; Johnson, Wesley D.; Paquette, Joshua

2016-01-01

The Scaled Wind Farm Technology (SWiFT) facility, operated by Sandia National Laboratories for the U.S. Department of Energy's Wind and Water Power Program, is a wind energy research site with multiple wind turbines scaled for the experimental study of wake dynamics, advanced rotor development, turbine control, and advanced sensing for production-scale wind farms. The SWiFT site currently includes three variable-speed, pitch-regulated, three-bladed wind turbines. The six volumes of this manual provide a detailed description of the SWiFT wind turbines, including their operation and user interfaces, electrical and mechanical systems, assembly and commissioning procedures, and safety systems. Further dissemination only as authorized to U.S. Government agencies and their contractors; other requests shall be approved by the originating facility or higher DOE programmatic authority. 111 UNCLASSIFIED UNLIMITED RELEASE Sandia SWiFT Wind Turbine Manual (SAND2016-0746 ) approved by: Department Manager SWiFT Site Lead Dave Minster (6121) Date Jonathan White (6121) Date SWiFT Site Supervisor Dave Mitchell (6121) Date Note: Document revision logs are found after the title page of each volume of this manual. iv

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)

Nevada Test Site Radiological Control Manual

Energy Technology Data Exchange (ETDEWEB)

Radiological Control Managers' Council - Nevada Test Site

2009-10-01

This document supersedes DOE/NV/11718--079, “NV/YMP Radiological Control Manual,” Revision 5 issued in November 2004. Brief Description of Revision: A complete revision to reflect the recent changes in compliance requirements with 10 CFR 835, and for use as a reference document for Tenant Organization Radiological Protection Programs.

FBR metallic materials test manual (English version)

International Nuclear Information System (INIS)

Odaka, Susumu; Kato, Shoichi; Yoshida, Eiichi

2003-06-01

For the development of the fast breeder reactor, this manual describes the method of in-air and in-sodium material tests and the method of organization the data. This previous manual has revised in accordance with the revision of Japanese Industrial Standard (JIS) and the conversion to the international unit. The test methods of domestic committees such as the VAMAS (Versailles Project on Advanced Materials and Standards) workshop were also refereed. The material test technologies accumulated in this group until now were also incorporated. This English version was prepared in order to provide more engineers with the FBR metallic materials test manual. (author)

Hanford External Dosimetry Technical Basis Manual PNL-MA-842

International Nuclear Information System (INIS)

Rathbone, Bruce A.

2007-01-01

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL's Hanford External Dosimetry Program (HEDP) which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee (HPDAC) which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. Rev. 0 marks the first revision to be released through PNNL's Electronic Records and Information Capture Architecture (ERICA) database. Revision numbers that are whole numbers reflect major revisions typically involving changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document. Revision Log: Rev. 0 (2/25/2005) Major revision and expansion. Rev. 0.1 (3/12/2007) Minor

Hanford External Dosimetry Technical Basis Manual PNL-MA-842

Energy Technology Data Exchange (ETDEWEB)

Rathbone, Bruce A.

2007-03-12

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL’s Hanford External Dosimetry Program (HEDP) which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee (HPDAC) which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. Rev. 0 marks the first revision to be released through PNNL’s Electronic Records & Information Capture Architecture (ERICA) database. Revision numbers that are whole numbers reflect major revisions typically involving changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document. Revision Log: Rev. 0 (2/25/2005) Major revision and expansion. Rev. 0.1 (3/12/2007) Minor

Unique safety manual for experimental personnel

International Nuclear Information System (INIS)

Busick, D.D.; Warren, G.J.

1979-01-01

Within a few months of the discovery of x-rays the first radiation injuries were reported (ta71). During the past thirty years both the number and complexity of x-ray analytical units have increased markedly. The world-wide number of incidents leading to severe injury has also increased. For analytical x-ray machines the need for engineered and administrative safeguards has long been recognized. At Stanford Synchrotron Radiation Laboratory (SSRL) the personnel protection system has been carefully designed to maximize safety and minimize experimental interference. However, all possible experimental configurations cannot be anticipated and some interference is to be expected. There are means by which safeguards can be substituted as long as these substitutions do not degrade the existing degree of safety. any substitutions must be evaluated by the Radiation Safety Committee, the SSRL staff and Operational Health Physics. Some studies have indicated that between fifty and ninety percent of serious radiation accidents are directly related to human errors, i.e., ignoring administrative proccedures, by-passing engineered safeguards or by inadequate training. Lindell has estimated the annual probability of serious injury to be about 1:100 per macchine. No matter what the real probability of serious injury is the personnel protection system should reduce this risk to a value that approaches zero. It is hoped that this manual will bring into sharper focus some of the more serious results of unnecessary risk taking. We also hope that it will convey the very real necessity for safeguards which may at times appear to be arbitrary and unnecessary impediments to experimental purposes

VIPRE-01: a thermal-hydraulic code for reactor cores. Volume 3: programmer's manual (Revision 2)

International Nuclear Information System (INIS)

Stewart, C.W.; Koontz, A.S.; Cuta, J.M.; Montgomery, S.D.

1985-07-01

The VIPRE thermal-hydraulic computer code for PWR and BWR core analysis has undergone a detailed design review by a committee of experts. A new version of the code, incorporating the committee's recommendations, has been submitted for NRC review and issuance of a safety evaluation report. The changes in the programmers's manual are given

Uranium hexafluoride: A manual of good handling practices. Revision 7

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-01-01

The United States Enrichment Corporation (USEC) is continuing the policy of the US Department of Energy (DOE) and its predecessor agencies in sharing with the nuclear industry their experience in the area of uranium hexafluoride (UF{sub 6}) shipping containers and handling procedures. The USEC has reviewed Revision 6 or ORO-651 and is issuing this new edition to assure that the document includes the most recent information on UF{sub 6} handling procedures and reflects the policies of the USEC. This manual updates the material contained in earlier issues. It covers the essential aspects of UF{sub 6} handling, cylinder filling and emptying, general principles of weighing and sampling, shipping, and the use of protective overpacks. The physical and chemical properties of UF{sub 6} are also described. The procedures and systems described for safe handling of UF{sub 6} presented in this document have been developed and evaluated during more than 40 years of handling vast quantities of UF{sub 6}. With proper consideration for its nuclear properties, UF{sub 6} may be safely handled in essentially the same manner as any other corrosive and/or toxic chemical.

Safety handling manual for high dose rate remote afterloading system

International Nuclear Information System (INIS)

1999-01-01

This manual is mainly for safety handling of 192 Ir-RALS (remote afterloading system) of high dose rate and followings were presented: Procedure and document format for the RALS therapy and for handling of its radiation source with the purpose of prevention of human errors and unexpected accidents, Procedure for preventing errors occurring in the treatment schedule and operation, and Procedure and format necessary for newly introducing the system into a facility. Consistency was intended in the description with the quality assurance guideline for therapy with small sealed radiation sources made by JASTRO (Japan Society for Therapeutic Radiology and Oncology). Use of the old type 60 Co-RALS was pointed out to be a serious problem remained and its safety handling procedure was also presented. (K.H.)

Towards a radiation safety culture at Universidad Nacional de Colombia

International Nuclear Information System (INIS)

Poveda, Jairo F.; Munera, Hector A.

2008-01-01

Full text: During the 20th century, nuclear and radiation techniques for research, teaching, and medical and engineering practice slowly appeared at the National University of Colombia, mainly at the Bogota, Medellin and Manizales branches. Each individual laboratory or researcher obtained the license for the use of the radioactive source, or radiation emitting apparatus. However, the University as a whole does not have as yet a Radiation Safety Manual, nor an inventory of laboratories using radiation. From the viewpoint of radiation safety and culture, this situation is undesirable, and may easily lead to inappropriate waste management practices, including the possibility of orphan sources (one such source has been already found). As part of the program of environmental management of dangerous wastes promoted by the National Division of Laboratories of our University, an office of radiation safety was created in the year 2006. This paper describes the situation that was found, the activities that have been carried out, some of the difficulties that we have met, and the plans that we have to help shape a safety culture at our institution. Currently we are pursuing an inventory of laboratories using radioactive sources and radiation emitting apparatuses, starting with the branches in Bogota and Manizales which are perceived as the most urgent to deal with. Fortunately, the branch in Medellin has been for about a decade under the care of a former radiation safety officer of our national Institute of Nuclear Affairs, who presently teaches there. During 2006 and 2007, 13 laboratories using radioactive sources were visited in the Bogota branch. Safety procedures and waste handling protocols were checked, safety manuals prepared and/or revised, and recommendations for safety culture provided. During 2008 we will visit Manizales, and will continue visiting a number of X-ray machines used in the Bogota branch for engineering, veterinary, and diagnostic, and surgery medical

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

Hanford External Dosimetry Technical Basis Manual PNL-MA-842

Energy Technology Data Exchange (ETDEWEB)

Rathbone, Bruce A.

2010-01-01

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL’s Hanford External Dosimetry Program (HEDP) which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee (HPDAC) which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since its inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. The first revision to be released through PNNL’s Electronic Records & Information Capture Architecture (ERICA) database was designated Revision 0. Revision numbers that are whole numbers reflect major revisions typically involving significant changes to all chapters in the document. Revision numbers that include a decimal fraction reflect minor revisions, usually restricted to selected chapters or selected pages in the document. Maintenance and distribution of controlled hard copies of the

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.

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

Manual on radiological safety in uranium and thorium mines and mills

International Nuclear Information System (INIS)

1976-01-01

The manual describes the personnel radiation hazards in uranium and thorium mines and mills. Measures which should be taken in order to protect the workers are outlined. The problems of air born radioactivity, external radiation, surface contamination and radioactive waste are treated. Safety standards in relation to the above mentioned subjects are given. An outline is given for monitoring programme. Monitoring methods, control methods and means of medical control are given

Manual on oil-gas industry waste utilization radioecological safety

International Nuclear Information System (INIS)

Kudryashev, V.A.; Lukashenko, S.N.; Tuleushev, A.Zh.; Marabaev, Zh.N.; Pasysaev, V.A.; Kayukov, P.G.; Kozhakhmetov, N.B.; Shevtsov, S.P.

2003-01-01

The development of a new document - 'Manual on radio-ecologically safe utilization of waste from oil-and-gas production' is carried out. This document regulates the whole cycle of environment protection measures at waste utilization for the named industry in Kazakhstan and is aimed on lowering the radiation risks and assurance of radioecological safety both at present and for the future. The document presents a set regulations necessary for radioactive wastes handling in the oil-gas industry. The normative document was agreed in both the Ministry of Health of the Republic of Kazakhstan (RK) and Ministry of Environment Protection of RK

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

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

The Effectiveness and Safety of Manual Therapy on Pain and Disability in Older Persons With Chronic Low Back Pain: A Systematic Review.

Science.gov (United States)

de Luca, Katie E; Fang, Sheng Hung; Ong, Justin; Shin, Ki-Soo; Woods, Samuel; Tuchin, Peter J

2017-09-01

The aim of this study was to perform a systematic review of the literature of the effectiveness and safety of manual therapy interventions on pain and disability in older persons with chronic low back pain (LBP). A literature search of 4 electronic databases was performed (PubMed, EMBASE, OVID, and CINAHL). Inclusion criteria included randomized controlled trials of manual therapy interventions on older persons who had chronic LBP. Effectiveness was determined by extracting and examining outcomes for pain and disability, with safety determined by the report of adverse events. The PEDro scale was used for quality assessment of eligible studies. The search identified 405 articles, and 38 full-text articles were assessed. Four studies met the inclusion criteria. All trials were of good methodologic quality and had a low risk of bias. The included studies provided moderate evidence supporting the use of manual therapy to reduce pain levels and alleviate disability. A limited number of studies have investigated the effectiveness and safety of manual therapy in the management of older people with chronic LBP. The current evidence to make firm clinical recommendations is limited. Research with appropriately designed trials to investigate the effectiveness and safety of manual therapy interventions in older persons with chronic LBP is required. Copyright © 2017. Published by Elsevier Inc.

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

ERIC User Services Manual. Revised Edition.

Science.gov (United States)

Wagner, Judith O., Comp.

This manual explains how the user services functions, usually performed by a User Services Coordinator, can be conducted in the 16 ERIC (Educational Resources Information Center) Clearinghouses and the various adjunct ERIC Clearinghouses. It provides guidelines, suggestions, and examples of how ERIC components currently perform the user services…

Biosafety Manual

Energy Technology Data Exchange (ETDEWEB)

King, Bruce W.

2010-05-18

Work with or potential exposure to biological materials in the course of performing research or other work activities at Lawrence Berkeley National Laboratory (LBNL) must be conducted in a safe, ethical, environmentally sound, and compliant manner. Work must be conducted in accordance with established biosafety standards, the principles and functions of Integrated Safety Management (ISM), this Biosafety Manual, Chapter 26 (Biosafety) of the Health and Safety Manual (PUB-3000), and applicable standards and LBNL policies. The purpose of the Biosafety Program is to protect workers, the public, agriculture, and the environment from exposure to biological agents or materials that may cause disease or other detrimental effects in humans, animals, or plants. This manual provides workers; line management; Environment, Health, and Safety (EH&S) Division staff; Institutional Biosafety Committee (IBC) members; and others with a comprehensive overview of biosafety principles, requirements from biosafety standards, and measures needed to control biological risks in work activities and facilities at LBNL.

Hanford Waste Vitrification Plant technical manual

Energy Technology Data Exchange (ETDEWEB)

Larson, D.E. [ed.; Watrous, R.A.; Kruger, O.L. [and others

1996-03-01

A key element of the Hanford waste management strategy is the construction of a new facility, the Hanford Waste Vitrification Plant (HWVP), to vitrify existing and future liquid high-level waste produced by defense activities at the Hanford Site. The HWVP mission is to vitrify pretreated waste in borosilicate glass, cast the glass into stainless steel canisters, and store the canisters at the Hanford Site until they are shipped to a federal geological repository. The HWVP Technical Manual (Manual) documents the technical bases of the current HWVP process and provides a physical description of the related equipment and the plant. The immediate purpose of the document is to provide the technical bases for preparation of project baseline documents that will be used to direct the Title 1 and Title 2 design by the A/E, Fluor. The content of the Manual is organized in the following manner. Chapter 1.0 contains the background and context within which the HWVP was designed. Chapter 2.0 describes the site, plant, equipment and supporting services and provides the context for application of the process information in the Manual. Chapter 3.0 provides plant feed and product requirements, which are primary process bases for plant operation. Chapter 4.0 summarizes the technology for each plant process. Chapter 5.0 describes the engineering principles for designing major types of HWVP equipment. Chapter 6.0 describes the general safety aspects of the plant and process to assist in safe and prudent facility operation. Chapter 7.0 includes a description of the waste form qualification program and data. Chapter 8.0 indicates the current status of quality assurance requirements for the Manual. The Appendices provide data that are too extensive to be placed in the main text, such as extensive tables and sets of figures. The Manual is a revision of the 1987 version.

Hanford Waste Vitrification Plant technical manual

International Nuclear Information System (INIS)

Larson, D.E.; Watrous, R.A.; Kruger, O.L.

1996-03-01

A key element of the Hanford waste management strategy is the construction of a new facility, the Hanford Waste Vitrification Plant (HWVP), to vitrify existing and future liquid high-level waste produced by defense activities at the Hanford Site. The HWVP mission is to vitrify pretreated waste in borosilicate glass, cast the glass into stainless steel canisters, and store the canisters at the Hanford Site until they are shipped to a federal geological repository. The HWVP Technical Manual (Manual) documents the technical bases of the current HWVP process and provides a physical description of the related equipment and the plant. The immediate purpose of the document is to provide the technical bases for preparation of project baseline documents that will be used to direct the Title 1 and Title 2 design by the A/E, Fluor. The content of the Manual is organized in the following manner. Chapter 1.0 contains the background and context within which the HWVP was designed. Chapter 2.0 describes the site, plant, equipment and supporting services and provides the context for application of the process information in the Manual. Chapter 3.0 provides plant feed and product requirements, which are primary process bases for plant operation. Chapter 4.0 summarizes the technology for each plant process. Chapter 5.0 describes the engineering principles for designing major types of HWVP equipment. Chapter 6.0 describes the general safety aspects of the plant and process to assist in safe and prudent facility operation. Chapter 7.0 includes a description of the waste form qualification program and data. Chapter 8.0 indicates the current status of quality assurance requirements for the Manual. The Appendices provide data that are too extensive to be placed in the main text, such as extensive tables and sets of figures. The Manual is a revision of the 1987 version

Public Affairs Manual. Revised 1976 Edition.

Science.gov (United States)

American Alliance for Health, Physical Education, and Recreation, Washington, DC.

This public affairs manual is designed for health, physical education, and recreation personnel. It begins with a position statement by the American Alliance for Health, Physical Education, and Recreation (AAHPER). In section two, resources and procedures for crises action at the local and state level are discussed. Several organizational models…

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

T-3 cask users' manual. Revision 1

International Nuclear Information System (INIS)

1986-06-01

This user's manual for the T-C spent fuel cask provides information on: operating procedures; inspection and maintenance procedures; criticality evaluation; shielding evaluation; thermal evaluation; structural evaluation; and limitations

49 CFR 236.919 - Operations and Maintenance Manual.

Science.gov (United States)

2010-10-01

..., INSPECTION, MAINTENANCE, AND REPAIR OF SIGNAL AND TRAIN CONTROL SYSTEMS, DEVICES, AND APPLIANCES Standards for Processor-Based Signal and Train Control Systems § 236.919 Operations and Maintenance Manual. (a... identify all software versions, revisions, and revision dates. Plans must be legible and correct. (c...

49 CFR 236.1039 - Operations and Maintenance Manual.

Science.gov (United States)

2010-10-01

..., INSPECTION, MAINTENANCE, AND REPAIR OF SIGNAL AND TRAIN CONTROL SYSTEMS, DEVICES, AND APPLIANCES Positive Train Control Systems § 236.1039 Operations and Maintenance Manual. (a) The railroad shall catalog and... software versions, revisions, and revision dates. Plans must be legible and correct. (c) Hardware, software...

EML procedures manual

International Nuclear Information System (INIS)

Volchok, H.L.; de Planque, G.

1982-01-01

This manual contains the procedures that are used currently by the Environmental Measurements Laboratory of the US Department of Energy. In addition a number of analytical methods from other laboratories have been included. These were tested for reliability at the Battelle, Pacific Northwest Laboratory under contract with the Division of Biomedical and Environmental Research of the AEC. These methods are clearly distinguished. The manual is prepared in loose leaf form to facilitate revision of the procedures and inclusion of additional procedures or data sheets. Anyone receiving the manual through EML should receive this additional material automatically. The contents are as follows: (1) general; (2) sampling; (3) field measurements; (4) general analytical chemistry; (5) chemical procedures; (6) data section; (7) specifications

SNL Abuse Testing Manual.

Energy Technology Data Exchange (ETDEWEB)

Orendorff, Christopher [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Lamb, Joshua [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Steele, Leigh Anna Marie [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2017-07-01

This report describes recommended abuse testing procedures for rechargeable energy storage systems (RESSs) for electric vehicles. This report serves as a revision to the FreedomCAR Electrical Energy Storage System Abuse Test Manual for Electric and Hybrid Electric Vehicle Applications (SAND2005-3123).

PETSc Users Manual Revision 3.7

Energy Technology Data Exchange (ETDEWEB)

Balay, S.; Brune, P.; Buschelman, K.; Gropp, W.; Karpeyev, D.; Kaushik, D.; Knepley, M.; McInnes, L. Curfman; Rupp, K.; Smith, B.; Zhang, H.; Abhyankar, S.; Adams, M.; Dalcin, L.; Zampini, S.; Zhang, H.

2016-04-01

This manual describes the use of PETSc for the numerical solution of partial differential equations and related problems on high-performance computers. The Portable, Extensible Toolkit for Scientific Computation (PETSc) is a suite of data structures and routines that provide the building blocks for the implementation of large-scale application codes on parallel (and serial) computers. PETSc uses the MPI standard for all message-passing communication.

PETSc Users Manual Revision 3.8

Energy Technology Data Exchange (ETDEWEB)

Balay, S. [Argonne National Lab. (ANL), Argonne, IL (United States); Abhyankar, S. [Argonne National Lab. (ANL), Argonne, IL (United States); Adams, M. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Brown, J. [Argonne National Lab. (ANL), Argonne, IL (United States); Brune, P. [Argonne National Lab. (ANL), Argonne, IL (United States); Buschelman, K. [Argonne National Lab. (ANL), Argonne, IL (United States); Dalcin, L. D. [King Abdullah Univ. of Science and Technology, Thuwal (Saudi Arabia); Eijkhout, V. [Univ. of Texas, Austin, TX (United States); Gropp, W. [Argonne National Lab. (ANL), Argonne, IL (United States); Kaushik, D. [Argonne National Lab. (ANL), Argonne, IL (United States); Knepley, M. [Argonne National Lab. (ANL), Argonne, IL (United States); May, D. [ETH Zurich (Switzerland); McInnes, L. Curfman [Argonne National Lab. (ANL), Argonne, IL (United States); Munson, T. [Argonne National Lab. (ANL), Argonne, IL (United States); Rupp, K. [Argonne National Lab. (ANL), Argonne, IL (United States); Sanan, P. [Univ. of Italian Switzerland, Lugano (Switzerland); Smith, B. [Argonne National Lab. (ANL), Argonne, IL (United States); Zampini, S. [King Abdullah Univ. of Science and Technology, Thuwal (Saudi Arabia); Zhang, H. [Illinois Inst. of Technology, Chicago, IL (United States); Zhang, H. [Argonne National Lab. (ANL), Argonne, IL (United States)

2017-09-01

This manual describes the use of PETSc for the numerical solution of partial differential equations and related problems on high-performance computers. The Portable, Extensible Toolkit for Scientific Computation (PETSc) is a suite of data structures and routines that provide the building blocks for the implementation of large-scale application codes on parallel (and serial) computers. PETSc uses the MPI standard for all message-passing communication.

SSC-K code users manual (rev.1)

International Nuclear Information System (INIS)

Kwon, Y. M.; Lee, Y. B.; Chang, W. P.; Hahn, D.

2002-01-01

The Supper System Code of KAERI (SSC-K) is a best-estimate system code for analyzing a variety of off-normal or accidents in the heat transport system of a pool type LMR design. It is being developed at Korea Atomic Energy Research Institution (KAERI) on the basis of SSC-L, originally developed at BNL to analyze loop-type LMR transients. SSC-K can handle both designs of loop and pool type LMRs. SSC-K contains detailed mechanistic models of transient thermal, hydraulic, neutronic, and mechanical phenomena to describe the response of the reactor core, coolant, fuel elements, and structures to accident conditions. This report provides a revised User's Manual (rev.1) of the SSC-K computer code, focusing on phenomenological model descriptions for new thermal, hydraulic, neutronic, and mechanical modules. A comprehensive description of the models for pool-type reactor is given in Chapters 2 and 3; the steady-state plant characterization, prior to the initiation of transient is described in Chapter 2 and their transient counterparts are discussed in Chapter 3. Discussions on the intermediate heat exchanger (IHX) and the electromagnetic (EM) pump are described in Chapter 4 and 5, respectively. A model of passive safety decay heat removal system (PSDRS) is discussed in Chapter 6, and models for various reactivity feedback effects are discussed in Chapter 7. In Chapter 8, constitutive laws and correlations required to execute the SSC-K are described. New models developed for SSC-K rev.1 are two dimensional hot pool model in Chapter 9, and long term cooling model in Chapter 10. Finally, a brief description of MINET code adopted to simulate BOP is presented in Chapter 11. Based on test runs for typical LMFBR accident analyses, it was found that the present version of SSC-K would be used for the safety analysis of KALIMER. However, the further validation of SSC-K is required for real applications. It is noted that the user's manual of SSC-K will be revised later with the

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

School Survey on Crime and Safety (SSOCS) 2000 Public-Use Data Files, User's Manual, and Detailed Data Documentation. [CD-ROM].

Science.gov (United States)

National Center for Education Statistics (ED), Washington, DC.

This CD-ROM contains the raw, public-use data from the 2000 School Survey on Crime and Safety (SSOCS) along with a User's Manual and Detailed Data Documentation. The data are provided in SAS, SPSS, STATA, and ASCII formats. The User's Manual and the Detailed Data Documentation are provided as .pdf files. (Author)

National Best Practices Manual for Building High Performance Schools (Revised)

Energy Technology Data Exchange (ETDEWEB)

2007-10-01

The Best Practices Manual was written as a part of the promotional effort for EnergySmart Schools, provided by the US Department of Energy, to educate school districts around the country about energy efficiency and renewable energy. Written specifically for architects and engineers, The Best Practices Manual is designed to help those who are responsible for designing or retrofitting schools, as well as their project managers. This manual will help design staff make informed decisions about energy and environmental issues important to the school systems and communities.

Quality assurance program manual for nuclear power plants. Volume I. Policies

International Nuclear Information System (INIS)

1975-01-01

Policies and procedures are presented which comply with current NRC regulatory requirements and industry codes and standards in effect during the design, procurement, construction, testing, operation, refueling, maintenance, repair and modification activities associated with nuclear power plants. Specific NRC and industry documents that contain the requirements, including the issue dates in effect, are identified in each nuclear power plant's Safety Analysis Report. The requirements established by these documents form the basis for the Consumers Power Quality Assurance Program, which is implemented to control those structures, systems, components and operational safety actions listed in each nuclear power plant's Quality List (Q-List). As additional and revised requirements are issued by the NRC and professional organizations involved in nuclear activities, they will be reviewed for their impact on this manual, and changes will be made where considered necessary

Washington Manual: A New Tool for Local School Accounting

Science.gov (United States)

Federal Aid Planner, 1972

1972-01-01

An advance glimpse of the revised financial accounting methods for school districts recommended in a new manual from the U. S. Office of Education. The manual is designed to help school districts modernize their financial accounting procedures and their entire range of fiscal management practices. (Author/DN)

PC based manual and safety logic card test setup for 235 MWe PHWRs

International Nuclear Information System (INIS)

Chandgadkar, G.M.; Kohli, A.K.; Agarwal, R.G.; Chandra, Rajesh

1992-01-01

Fuel handling controls for 235 MWe PHWR make use of Manual and Logic cards (MLCs) for providing safety interlocks. These cards consist of various type of logic blocks. By connecting these logic blocks all the safety interlocks required for fuel handling controls have been provided. Previously trouble shooting of these cards was done by means of logic probe. Since the method was manual, it was laborious and time consuming. PC based test setup has overcome this drawback and detects the fault at the component level within few seconds. It also gives printout of status of faulty MLC cards. Here motherboard has been designed having slots for insertion of MLC cards. The input/output connection of these cards are coming to two 50 pin FRC connectors. PC communicates through 144 line digital input/output card with MLC card under test. Software is user friendly and outputs suitable input patterns to the card under test and checks for output pattern. It compares this output pattern with compare pattern and detects the fault and displays the symptoms. This system is currently in use at test facility for fuelling machine for 235 MWe PHWR reactor at Refuelling Technology Division, Hall-7. This test setup has been proposed for use at NAPP and future reactors. (author). 4 figs., 1 annexure

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...

78 FR 4766 - Adoption of Updated EDGAR Filer Manual

Science.gov (United States)

2013-01-23

..., publication for notice and comment is not required under the Administrative Procedure Act (APA).\\7\\ It follows...-68644; 39-2488; IC-30348] Adoption of Updated EDGAR Filer Manual AGENCY: Securities and Exchange...) Filer Manual and related rules to reflect updates to the EDGAR system. The revisions are being made...

Estimator's electrical man-hour manual

CERN Document Server

Page, John S

1999-01-01

This manual's latest edition continues to be the best source available for making accurate, reliable man-hour estimates for electrical installation. This new edition is revised and expanded to include installation of electrical instrumentation, which is used in monitoring various process systems.

Manual on safety aspects of the design and equipment of hot laboratories. 1981 ed

International Nuclear Information System (INIS)

1981-01-01

This manual covers the general principles of planning and design of areas inside laboratories according to the varying potential radiation and contamination hazards; enclosures for radioactive material containment; viewing and lighting systems and various types of manipulators; transfer and transport of radioactive materials within the laboratories; air cleaning and ventilation systems, with particular reference to IAEA Safety Series No.17; techniques for controlling air pollution from the operation of nuclear facilities; various radioactive waste disposal systems; criticality control; fire protection; personnel monitoring, including changing-room monitoring and protective clothing; standardization and automation; and administrative controls. Although alpha, beta, gamma technologies have developed separately, equipment used in radioactive work is common to many operations. There is a step change in technology between work with uranium and plutonium and between work with plutonium and other transuranics; with plutonium one enters the field of alpha, beta, gamma technology. This manual reports the basic requirements and gives reference to more sophisticated techniques available. It is not concerned with work on a commercial scale. Other publications of interest in this context, for instance IAEA Safety Series No.39, are referenced for more detailed information.

US Department of Energy radiological control manual

International Nuclear Information System (INIS)

1994-04-01

This manual establishes practices for the conduct of Department of Energy radiological control activities. The Manual states DOE's positions and views on the best courses of action currently available in the area of radiological controls. Accordingly, the provisions in the Manual should be viewed by contractors as an acceptable technique, method or solution for fulfilling their duties and responsibilities. This Manual shall be used by DOE in evaluating the performance of its contractors. This Manual is not a substitute for Regulations; it is intended to be consistent with all relevant statutory and regulatory requirements and shall be revised whenever necessary to ensure such consistency. Some of the Manual provisions, however, challenge the user to go well beyond minimum requirements. Following the course of action delineated in the Manual will result in achieving and surpassing related statutory or regulatory requirements

Autism and the cognitive processing triad: a case for revising the criteria in the diagnostic and statistical manual.

Science.gov (United States)

Cashin, Andrew; Gallagher, Hilary; Newman, Claire; Hughes, Mark

2012-08-01

The next iteration of the Diagnostic and Statistical Manual of Mental Disorders is due for release in May 2013. The current diagnostic criteria for autism are based on a behavioral triad of impairment, which has been helpful for diagnosis and identifying the need for intervention, but is not useful with regard to developing interventions. Revised diagnostic criteria are needed to better inform research and therapeutic intervention. This article examines the research underpinning the behavioral triad of impairment to consider alternative explanations and a more useful framing for diagnosis and intervention. Contemporary research and literature on autism were used in this study. It is proposed that the cognitive processing triad of impaired abstraction, impaired theory of mind, and impaired linguistic processing become the triad of impairment for autism in the fifth edition of the Diagnostic and Statistical Manual of Mental Disorders. These are investigable at the diagnostic level and can usefully inform intervention. Further, in addressing the debate on whether restrictive and repetitive behavior should remain central to diagnosis or be replaced by a deficit in imagination, the authors argue that both behavioral manifestations are underpinned by impaired abstraction. © 2012 Wiley Periodicals, Inc.

User manual for NASA Lewis 10 by 10 foot supersonic wind tunnel. Revised

Science.gov (United States)

Soeder, Ronald H.

1995-01-01

This manual describes the 10- by 10-Foot Supersonic Wind Tunnel at the NASA Lewis Research Center and provides information for users who wish to conduct experiments in this facility. Tunnel performance operating envelopes of altitude, dynamic pressure, Reynolds number, total pressure, and total temperature as a function of test section Mach number are presented. Operating envelopes are shown for both the aerodynamic (closed) cycle and the propulsion (open) cycle. The tunnel test section Mach number range is 2.0 to 3.5. General support systems, such as air systems, hydraulic system, hydrogen system, fuel system, and Schlieren system, are described. Instrumentation and data processing and acquisition systems are also described. Pretest meeting formats and schedules are outlined. Tunnel user responsibility and personnel safety are also discussed.

Developing glovebox robotics to meet the national robot safety standard and nuclear safety criteria

International Nuclear Information System (INIS)

McMahon, T.T.; Sievers, R.H.

1991-09-01

Development of a glove box based robotic system by the Lawrence Livermore National Laboratory (LLNL) is reported. Safety issues addressed include planning to meet the special constraints of operations within a hazardous material glove box and with hostile environments, compliance with the current and draft national robotic system safety standards, and eventual satisfaction of nuclear material handling requirements. Special attention has been required for the revision to the robot and control system models which antedate adoption of the present national safety standard. A robotic test bed, using non-radioactive surrogates is being activated at the Lawrence Livermore National Laboratory to develop the material handling system and the process interfaces for future special nuclear material processing applications. Part of this effort is to define, test, and revise adequate safety controls to ensure success when the system is eventually deployed at a DOE site. The current system is primarily for demonstration and testing, but will evolve into the baseline configuration from which the production system is to be derived. This results in special hazards associated with research activities which may not be present on a production line. Nuclear safety is of paramount importance and has been successfully addressed for 50 years in the DOE weapons production complex. It carries its particular requirements for robot systems and manual operations, as summarized below: Criticality must be avoided (materials cannot consolidate or accumulate to approach a critical mass). Radioactive materials must be confined. The public and workers must be protected from accountable radiation exposure. Nuclear material must be readily retrievable. Nuclear safety must be conclusively demonstrated through hazards analysis. 7 refs

Radiological Safety Analysis Computer (RSAC) Program Version 7.0 Users’ Manual

Energy Technology Data Exchange (ETDEWEB)

Dr. Bradley J Schrader

2009-03-01

The Radiological Safety Analysis Computer (RSAC) Program Version 7.0 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users’ manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods.

Radiological Safety Analysis Computer (RSAC) Program Version 7.2 Users’ Manual

Energy Technology Data Exchange (ETDEWEB)

Dr. Bradley J Schrader

2010-10-01

The Radiological Safety Analysis Computer (RSAC) Program Version 7.2 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users’ manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods.

Radiological Safety Analysis Computer (RSAC) Program Version 7.0 Users Manual

International Nuclear Information System (INIS)

Schrader, Bradley J.

2009-01-01

The Radiological Safety Analysis Computer (RSAC) Program Version 7.0 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods

RELAP-7 Theory Manual

Energy Technology Data Exchange (ETDEWEB)

Berry, Ray Alden [Idaho National Lab. (INL), Idaho Falls, ID (United States); Zou, Ling [Idaho National Lab. (INL), Idaho Falls, ID (United States); Zhao, Haihua [Idaho National Lab. (INL), Idaho Falls, ID (United States); Zhang, Hongbin [Idaho National Lab. (INL), Idaho Falls, ID (United States); Peterson, John William [Idaho National Lab. (INL), Idaho Falls, ID (United States); Martineau, Richard Charles [Idaho National Lab. (INL), Idaho Falls, ID (United States); Kadioglu, Samet Yucel [Idaho National Lab. (INL), Idaho Falls, ID (United States); Andrs, David [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2016-03-01

This document summarizes the physical models and mathematical formulations used in the RELAP-7 code. In summary, the MOOSE based RELAP-7 code development is an ongoing effort. The MOOSE framework enables rapid development of the RELAP-7 code. The developmental efforts and results demonstrate that the RELAP-7 project is on a path to success. This theory manual documents the main features implemented into the RELAP-7 code. Because the code is an ongoing development effort, this RELAP-7 Theory Manual will evolve with periodic updates to keep it current with the state of the development, implementation, and model additions/revisions.

RADTRAN 4: Volume 4, Programmer's manual

International Nuclear Information System (INIS)

Kanipe, F.L.; Neuhauser, K.S.

1992-07-01

The RADTRAN 4 computer code is designed to analyze radiological consequences and accident risks of transporting radioactive material. This manual provides information useful for interpreting, troubleshooting, or debugging components of the code during development or revision of the program

Users Manual for TMY3 Data Sets (Revised)

Energy Technology Data Exchange (ETDEWEB)

Wilcox, S.; Marion, W.

2008-05-01

This users manual describes how to obtain and interpret the data in the Typical Meteorological Year version 3 (TMY3) data sets. These data sets are an update to the TMY2 data released by NREL in 1994.

RAVEN User Manual Revision 5

International Nuclear Information System (INIS)

Mandelli, Diego; Rabiti, Cristian; Cogliati, Joshua Joseph; Kinoshita, Robert Arthur; Alfonsi, Andrea; Sen, Ramazan Sonat; Wang, Congjian

2017-01-01

RAVEN is a generic software framework to perform parametric and probabilistic analy- sis based on the response of complex system codes. The initial development was aimed to provide dynamic risk analysis capabilities to the Thermo-Hydraulic code RELAP-7, currently under development at the Idaho National Laboratory (INL). Although the initial goal has been fully accomplished, RAVEN is now a multi-purpose probabilistic and uncer- tainty quantification platform, capable to agnostically communicate with any system code. This agnosticism includes providing Application Programming Interfaces (APIs). These APIs are used to allow RAVEN to interact with any code as long as all the parameters that need to be perturbed are accessible by inputs files or via python interfaces. RAVEN is capable of investigating the system response, and investigating the input space using Monte Carlo, Grid, or Latin Hyper Cube sampling schemes, but its strength is focused to- ward system feature discovery, such as limit surfaces, separating regions of the input space leading to system failure, using dynamic supervised learning techniques. The development of RAVEN has started in 2012, when, within the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program, the need to provide a modern risk evaluation framework became stronger. RAVEN principal assignment is to provide the necessary software and algorithms in order to employ the concept developed by the Risk Informed Safety Margin Characterization (RISMC) program. RISMC is one of the pathways defined within the Light Water Reactor Sustainability (LWRS) program. In the RISMC approach, the goal is not just the individuation of the frequency of an event potentially leading to a system failure, but the closeness (or not) to key safety-related events. Hence, the approach is in- terested in identifying and increasing the safety margins related to those events. A safety margin is a numerical value quantifying the probability that a safety metric (e

Revised SWAT. The integrated burnup calculation code system

International Nuclear Information System (INIS)

Suyama, Kenya; Mochizuki, Hiroki; Kiyosumi, Takehide

2000-07-01

SWAT is an integrated burnup code system developed for analysis of post irradiation examination, transmutation of radioactive waste, and burnup credit problem. This report shows an outline and a user's manual of revised SWAT. This revised SWAT includes expansion of functions, increasing supported machines, and correction of several bugs reported from users of previous SWAT. (author)

Revised SWAT. The integrated burnup calculation code system

Energy Technology Data Exchange (ETDEWEB)

Suyama, Kenya; Mochizuki, Hiroki [Department of Fuel Cycle Safety Research, Nuclear Safety Research Center, Tokai Research Establishment, Japan Atomic Energy Research Institute, Tokai, Ibaraki (Japan); Kiyosumi, Takehide [The Japan Research Institute, Ltd., Tokyo (Japan)

2000-07-01

SWAT is an integrated burnup code system developed for analysis of post irradiation examination, transmutation of radioactive waste, and burnup credit problem. This report shows an outline and a user's manual of revised SWAT. This revised SWAT includes expansion of functions, increasing supported machines, and correction of several bugs reported from users of previous SWAT. (author)

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

Developing a Manualized Occupational Therapy Diabetes Management Intervention: Resilient, Empowered, Active Living With Diabetes.

Science.gov (United States)

Pyatak, Elizabeth A; Carandang, Kristine; Davis, Shain

2015-07-01

This article reports on the development of a manualized occupational therapy intervention for diabetes management. An initial theoretical framework and core content areas for a Stage I intervention manual were developed based on an in-depth needs assessment and review of existing literature. After evaluation by a panel of experts and completion of a feasibility study, the intervention was revised into a Stage 2 manual in preparation for a randomized study evaluating the intervention's efficacy. In developing the initial manual, we delineated core theoretical principles to allow for flexible application and tailoring of the intervention's content areas. Expert panel feedback and feasibility study results led to changes to the intervention structure and content as we developed the Stage 2 manual. Through describing this process, we illustrate the dynamic evolution of intervention manuals, which undergo revisions due to both theoretical and practical considerations at each stage of the research-to-clinical practice pipeline.

Propensity scores-potential outcomes framework to incorporate severity probabilities in the highway safety manual crash prediction algorithm.

Science.gov (United States)

Sasidharan, Lekshmi; Donnell, Eric T

2014-10-01

Accurate estimation of the expected number of crashes at different severity levels for entities with and without countermeasures plays a vital role in selecting countermeasures in the framework of the safety management process. The current practice is to use the American Association of State Highway and Transportation Officials' Highway Safety Manual crash prediction algorithms, which combine safety performance functions and crash modification factors, to estimate the effects of safety countermeasures on different highway and street facility types. Many of these crash prediction algorithms are based solely on crash frequency, or assume that severity outcomes are unchanged when planning for, or implementing, safety countermeasures. Failing to account for the uncertainty associated with crash severity outcomes, and assuming crash severity distributions remain unchanged in safety performance evaluations, limits the utility of the Highway Safety Manual crash prediction algorithms in assessing the effect of safety countermeasures on crash severity. This study demonstrates the application of a propensity scores-potential outcomes framework to estimate the probability distribution for the occurrence of different crash severity levels by accounting for the uncertainties associated with them. The probability of fatal and severe injury crash occurrence at lighted and unlighted intersections is estimated in this paper using data from Minnesota. The results show that the expected probability of occurrence of fatal and severe injury crashes at a lighted intersection was 1 in 35 crashes and the estimated risk ratio indicates that the respective probabilities at an unlighted intersection was 1.14 times higher compared to lighted intersections. The results from the potential outcomes-propensity scores framework are compared to results obtained from traditional binary logit models, without application of propensity scores matching. Traditional binary logit analysis suggests that

New highway accident location manual for Missouri.

Science.gov (United States)

2013-12-01

The Missouri HAL manual is used to identify, analyze, and correct high crash locations, and has not been updated since : 1999. This new edition brings the manual up to date, while incorporating the methodology of the national Highway Safety : Manual ...

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

User manual Dieka PreProcessor

NARCIS (Netherlands)

Valkering, Kasper

2000-01-01

This is the user manual belonging to the Dieka-PreProcessor. This application was written by Wenhua Cao and revised and expanded by Kasper Valkering. The aim of this preproccesor is to be able to draw and mesh extrusion dies in ProEngineer, and do the FE-calculation in Dieka. The preprocessor makes

Update of the Dutch manual for costing studies in health care.

Directory of Open Access Journals (Sweden)

Tim A Kanters

Full Text Available Dutch health economic guidelines include a costing manual, which describes preferred research methodology for costing studies and reference prices to ensure high quality studies and comparability between study outcomes. This paper describes the most important revisions of the costing manual compared to the previous version.An online survey was sent out to potential users of the costing manual to identify topics for improvement. The costing manual was aligned with contemporary health economic guidelines. All methodology sections and parameter values needed for costing studies, particularly reference prices, were updated. An expert panel of health economists was consulted several times during the review process. The revised manual was reviewed by two members of the expert panel and by reviewers of the Dutch Health Care Institute.The majority of survey respondents was satisfied with content and usability of the existing costing manual. Respondents recommended updating reference prices and adding some particular commonly needed reference prices. Costs categories were adjusted to the international standard: 1 costs within the health care sector; 2 patient and family costs; and 3 costs in other sectors. Reference prices were updated to reflect 2014 values. The methodology chapter was rewritten to match the requirements of the costing manual and preferences of the users. Reference prices for nursing days of specific wards, for diagnostic procedures and nurse practitioners were added.The usability of the costing manual was increased and parameter values were updated. The costing manual became integrated in the new health economic guidelines.

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.

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

Oregon Pupil Transportation Manual. Revised Regulations and Responsibilities.

Science.gov (United States)

Oregon State Dept. of Education, Salem.

Designed for use by Oregon school bus drivers and administrators, this manual answers common questions about school bus transportation in Oregon, including those about the laws governing pupil transportation, the regulations governing pupil transportation administration, and the laws on school bus operation. A chapter of advisory materials covers…

RADTRAN 4: Volume 4, Programmer`s manual

Energy Technology Data Exchange (ETDEWEB)

Kanipe, F L [GRAM, Inc., Albuquerque, NM (United States); Neuhauser, K S [Sandia National Labs., Albuquerque, NM (United States)

1992-07-01

The RADTRAN 4 computer code is designed to analyze radiological consequences and accident risks of transporting radioactive material. This manual provides information useful for interpreting, troubleshooting, or debugging components of the code during development or revision of the program.

Free manual of cadaver dissection modifiable by other anatomists.

Science.gov (United States)

Chung, Beom Sun; Chung, Min Suk

2015-06-01

Even in the rapidly changing field of cadaver dissection, published guide books still play an important role in the anatomy lab. However, commercial manuals with lengthy volumes and inflexible copyrights have several limitations which can be complemented by open-source manuals. Recently, the authors have manufactured and distributed a free electronic dissection manual (anatomy.co.kr), where descriptions are written concisely and images are drawn schematically. Moreover, simplified signs are employed to represent the cadaver viewing angles and manner of dissection. Based on the original files of this manual, other anatomists can revise and utilize the descriptions and figures. We expect many updated versions of our manual to be shared between students all over the world.

The Waiter and Waitress Training Manual. Revised Edition.

Science.gov (United States)

Mitchell, Barbara J.

This manual is intended for use in pre-employment or upgrading training programs for persons who are planning to work or are presently working in the hotel and restaurant food service industry. Eleven chapters cover interpersonal relationships with employers, fellow employees, and customers; grooming and personal hygiene; sanitary food handling;…

Revision of the protective action guides manual for nuclear incidents

International Nuclear Information System (INIS)

DeCair, S.; MacKinney, J.

2007-01-01

EPA's 1992 Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, referred to as the PAG Manual, is a radiological emergency planning and response tool for emergency management officials at the Federal, state, tribal, and local levels. A Protective Action Guide is defined as, the projected dose to reference man, or other defined individual, from a release of radioactive material at which a specific protective action to reduce or avoid that dose is recommended'. The updated version of the PAG Manual accomplishes these key objectives: applying the existing 1992 protective action guides and protective actions to new radiological and nuclear scenarios of concern; updating the dosimetry basis; lowering the recommended dose for administration of stable iodine; providing new guidance concerning consumption of drinking water during or after a radiological emergency; updating the dosimetry basis for all derived levels, and, adding guidance for dealing with long-term site restoration following a major radiological release. (author)

Hanford External Dosimetry Technical Basis Manual PNL-MA-842

International Nuclear Information System (INIS)

Rathbone, Bruce A.

2006-01-01

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL's Hanford External Dosimetry Program which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. Rev. 0 marks the first revision to be released through PNNL's Electronic Records & Information Capture Architecture (ERICA) database

Hanford External Dosimetry Technical Basis Manual PNL-MA-842

Energy Technology Data Exchange (ETDEWEB)

Rathbone, Bruce A.

2005-02-25

The Hanford External Dosimetry Technical Basis Manual PNL-MA-842 documents the design and implementation of the external dosimetry system used at Hanford. The manual describes the dosimeter design, processing protocols, dose calculation methodology, radiation fields encountered, dosimeter response characteristics, limitations of dosimeter design under field conditions, and makes recommendations for effective use of the dosimeters in the field. The manual describes the technical basis for the dosimetry system in a manner intended to help ensure defensibility of the dose of record at Hanford and to demonstrate compliance with 10 CFR 835, DOELAP, DOE-RL, ORP, PNSO, and Hanford contractor requirements. The dosimetry system is operated by PNNL’s Hanford External Dosimetry Program which provides dosimetry services to all Hanford contractors. The primary users of this manual are DOE and DOE contractors at Hanford using the dosimetry services of PNNL. Development and maintenance of this manual is funded directly by DOE and DOE contractors. Its contents have been reviewed and approved by DOE and DOE contractors at Hanford through the Hanford Personnel Dosimetry Advisory Committee which is chartered and chaired by DOE-RL and serves as means of coordinating dosimetry practices across contractors at Hanford. This manual was established in 1996. Since inception, it has been revised many times and maintained by PNNL as a controlled document with controlled distribution. Rev. 0 marks the first revision to be released through PNNL’s Electronic Records & Information Capture Architecture (ERICA) database.

The Intelligent Monitoring System: Generic Database Interface (GDI). User Manual. Revision

Science.gov (United States)

1994-01-03

Summary of Lo=catos Nan* Decufptin Directory Location User Manual FrameMaker ’ source organized inlo, a book UBSW~ftbendb~doclim/user-manual named gdibk A...functions. LNSRCf1bgenrdb/srC I. Framemaker is a docment publishing tool fium Fame Technology Cororation Baseline: 21.1 3-1 anoAW ftnua ?bewd uw on 3.2

ENDF/B-5 formats manual 1984

Energy Technology Data Exchange (ETDEWEB)

Kinsey, R; Magurno, B A

1986-09-01

The ENDF-5 Format, originally the format of the US Evaluated Nuclear Data File ENDF/B-5, was internationally recommended for the computer storage, processing and exchange of evaluated neutron nuclear data. The present document contains the original Formats Manual of 1979, updated with revisions of Nov. 1983. (author) Figs, tabs

Operating manual for the Bulk Shielding Reactor

International Nuclear Information System (INIS)

1983-04-01

The BSR is a pool-type reactor. It has the capabilities of continuous operation at a power level of 2 MW or at any desired lower power level. This manual presents descriptive and operational information. The reactor and its auxillary facilities are described from physical and operational viewpoints. Detailed operating procedures are included which are applicable from source-level startup to full-power operation. Also included are procedures relative to the safety of personnel and equipment in the areas of experiments, radiation and contamination control, emergency actions, and general safety. This manual supercedes all previous operating manuals for the BSR

Operating manual for the Bulk Shielding Reactor

International Nuclear Information System (INIS)

1987-03-01

The BSR is a pool-type reactor. It has the capabilities of continuous operation at a power level of 2 MW or at any desired lower power level. This manual presents descriptive and operational information. The reactor and its auxiliary facilities are described from physical and operational viewpoints. Detailed operating procedures are included which are applicable from source-level startup to full-power operation. Also included are procedures relative to the safety of personnel and equipment in the areas of experiments, radiation and contamination control, emergency actions, and general safety. This manual supersedes all previous operating manuals for the BSR

Operating manual for the Bulk Shielding Reactor

Energy Technology Data Exchange (ETDEWEB)

1987-03-01

The BSR is a pool-type reactor. It has the capabilities of continuous operation at a power level of 2 MW or at any desired lower power level. This manual presents descriptive and operational information. The reactor and its auxiliary facilities are described from physical and operational viewpoints. Detailed operating procedures are included which are applicable from source-level startup to full-power operation. Also included are procedures relative to the safety of personnel and equipment in the areas of experiments, radiation and contamination control, emergency actions, and general safety. This manual supersedes all previous operating manuals for the BSR.

Operating manual for the Bulk Shielding Reactor

Energy Technology Data Exchange (ETDEWEB)

1983-04-01

The BSR is a pool-type reactor. It has the capabilities of continuous operation at a power level of 2 MW or at any desired lower power level. This manual presents descriptive and operational information. The reactor and its auxillary facilities are described from physical and operational viewpoints. Detailed operating procedures are included which are applicable from source-level startup to full-power operation. Also included are procedures relative to the safety of personnel and equipment in the areas of experiments, radiation and contamination control, emergency actions, and general safety. This manual supercedes all previous operating manuals for the BSR.

Fire Protection Program Manual

Energy Technology Data Exchange (ETDEWEB)

Sharry, J A

2012-05-18

This manual documents the Lawrence Livermore National Laboratory (LLNL) Fire Protection Program. Department of Energy (DOE) Orders 420.1B, Facility Safety, requires LLNL to have a comprehensive and effective fire protection program that protects LLNL personnel and property, the public and the environment. The manual provides LLNL and its facilities with general information and guidance for meeting DOE 420.1B requirements. The recommended readers for this manual are: fire protection officers, fire protection engineers, fire fighters, facility managers, directorage assurance managers, facility coordinators, and ES and H team members.

The Radiological Safety Analysis Computer Program (RSAC-5) user's manual

International Nuclear Information System (INIS)

Wenzel, D.R.

1994-02-01

The Radiological Safety Analysis Computer Program (RSAC-5) calculates the consequences of the release of radionuclides to the atmosphere. Using a personal computer, a user can generate a fission product inventory from either reactor operating history or nuclear criticalities. RSAC-5 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated through the inhalation, immersion, ground surface, and ingestion pathways. RSAC+, a menu-driven companion program to RSAC-5, assists users in creating and running RSAC-5 input files. This user's manual contains the mathematical models and operating instructions for RSAC-5 and RSAC+. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-5 and RSAC+. These programs are designed for users who are familiar with radiological dose assessment methods

Mediation in Special Education: A Resource Manual for Mediators. Revised and Updated.

Science.gov (United States)

Schrag, Judy A.

This resource manual presents information on mediation practices in special education disagreements between the school and parents. The manual provides an overview of requirements in the Individuals with Disabilities Education Act (IDEA) and gives definitions for alternative dispute resolution processes, such as arbitration and litigation. A chart…

Nevada National Security Site Radiological Control Manual

International Nuclear Information System (INIS)

2012-01-01

This document supersedes DOE/NV/25946--801, 'Nevada Test Site Radiological Control Manual,' Revision 1 issued in February 2010. Brief Description of Revision: A complete revision to reflect a recent change in name for the NTS; changes in name for some tenant organizations; and to update references to current DOE policies, orders, and guidance documents. Article 237.2 was deleted. Appendix 3B was updated. Article 411.2 was modified. Article 422 was re-written to reflect the wording of DOE O 458.1. Article 431.6.d was modified. The glossary was updated. This manual contains the radiological control requirements to be used for all radiological activities conducted by programs under the purview of the U.S. Department of Energy (DOE) and the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations (CFR) Part 835, 'Occupational Radiation Protection.' Programs covered by this manual are located at the Nevada National Security Site (NNSS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Livermore, California; and Andrews Air Force Base, Maryland. In addition, fieldwork by NNSA/NSO at other locations is covered by this manual. Current activities at NNSS include operating low-level radioactive and mixed waste disposal facilities for United States defense-generated waste, assembly and execution of subcritical experiments, assembly/disassembly of special experiments, the storage and use of special nuclear materials, performing criticality experiments, emergency responder training, surface cleanup and site characterization of contaminated land areas, environmental activity by the University system, and nonnuclear test operations, such as controlled spills of hazardous materials at the Hazardous Materials Spill Center. Currently, the major potential for occupational radiation exposure is associated with the burial of

Nevada National Security Site Radiological Control Manual

Energy Technology Data Exchange (ETDEWEB)

Radiological Control Managers’ Council

2012-03-26

This document supersedes DOE/NV/25946--801, 'Nevada Test Site Radiological Control Manual,' Revision 1 issued in February 2010. Brief Description of Revision: A complete revision to reflect a recent change in name for the NTS; changes in name for some tenant organizations; and to update references to current DOE policies, orders, and guidance documents. Article 237.2 was deleted. Appendix 3B was updated. Article 411.2 was modified. Article 422 was re-written to reflect the wording of DOE O 458.1. Article 431.6.d was modified. The glossary was updated. This manual contains the radiological control requirements to be used for all radiological activities conducted by programs under the purview of the U.S. Department of Energy (DOE) and the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations (CFR) Part 835, 'Occupational Radiation Protection.' Programs covered by this manual are located at the Nevada National Security Site (NNSS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Livermore, California; and Andrews Air Force Base, Maryland. In addition, fieldwork by NNSA/NSO at other locations is covered by this manual. Current activities at NNSS include operating low-level radioactive and mixed waste disposal facilities for United States defense-generated waste, assembly and execution of subcritical experiments, assembly/disassembly of special experiments, the storage and use of special nuclear materials, performing criticality experiments, emergency responder training, surface cleanup and site characterization of contaminated land areas, environmental activity by the University system, and nonnuclear test operations, such as controlled spills of hazardous materials at the Hazardous Materials Spill Center. Currently, the major potential for occupational radiation exposure is associated with the burial of

Fuel Element Technical Manual

Energy Technology Data Exchange (ETDEWEB)

Burley, H.H. [ed.

1956-08-01

It is the purpose of the Fuel Element Technical Manual to Provide a single document describing the fabrication processes used in the manufacture of the fuel element as well as the technical bases for these processes. The manual will be instrumental in the indoctrination of personnel new to the field and will provide a single data reference for all personnel involved in the design or manufacture of the fuel element. The material contained in this manual was assembled by members of the Engineering Department and the Manufacturing Department at the Hanford Atomic Products Operation between the dates October, 1955 and June, 1956. Arrangement of the manual. The manual is divided into six parts: Part I--introduction; Part II--technical bases; Part III--process; Part IV--plant and equipment; Part V--process control and improvement; and VI--safety.

Accident Prevention: A Workers' Education Manual.

Science.gov (United States)

International Labour Office, Geneva (Switzerland).

Devoted to providing industrial workers with a greater knowledge of precautionary measures undertaken and enforced by industries for the protection of workers, this safety education manual contains 14 lessons ranging from "The Problems of Accidents during Work" to "Trade Unions and Workers and Industrial Safety." Fire protection, safety equipment…

National Radiobiology Archives Distributed Access User`s Manual, Version 1.1. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Smith, S.K.; Prather, J.C.; Ligotke, E.K.; Watson, C.R.

1992-06-01

This supplement to the NRA Distributed Access User`s manual (PNL-7877), November 1991, describes installation and use of Version 1.1 of the software package; this is not a replacement of the previous manual. Version 1.1 of the NRA Distributed Access Package is a maintenance release. It eliminates several bugs, and includes a few new features which are described in this manual. Although the appearance of some menu screens has changed, we are confident that the Version 1.0 User`s Manual will provide an adequate introduction to the system. Users who are unfamiliar with Version 1.0 may wish to experiment with that version before moving on to Version 1.1.

Operations and Maintenance Manual, Atmospheric Contaminant Sensor, Revision B.

Science.gov (United States)

National Aeronautics and Space Administration, Washington, DC.

The sensor is a mass spectrometer system which continuously monitors the atmospheric constituents of hydrogen, water vapor, nitrogen, oxygen, and carbon dioxide, and monitors the Freons on a demand sampling basis. The manual provides a system description, operational procedures, and maintenance and troubleshooting instructions. Circuit diagrams…

The Container Tree Nursery Manual: Volume 7, Seedling processing, storage, and outplanting

Science.gov (United States)

Thomas D. Landis; R. Kasten Dumroese; Diane L. Haase

2010-01-01

This manual is based on the best current knowledge of container nursery management and should be used as a general reference. Recommendations were made using the best information available at the time and are, therefore, subject to revision as more knowledge becomes available. Much of the information in this manual was primarily developed from information on growing...

Manual for Accessibility: [Conference, Meeting, and Lodging Facilities]. Revised.

Science.gov (United States)

National Rehabilitation Association, Alexandria, VA.

This illustrated manual and survey forms are designed to be used by organizations, hotel and restaurant associations, interested individuals and others as a guide for selecting accessible conference, meeting, and lodging facilities. The guidelines can also be used with existing facilities to identify specific modifications and accommodations. The…

Training manual on food irradiation technology and techniques. 2. ed.

International Nuclear Information System (INIS)

1982-01-01

The objective of the revised Training Manual is to help scientists to acquire the necessary knowledge needed for performing proper research and development work in the field of food irradiation. The Manual presents an up-to-date picture of the current state of food irradiation and reflects the important advances made in the technology of food irradiation, in the radiation chemistry of foods, in the microbiology of irradiated foods, in wholesomeness and standardization. It contains the following chapters: (1) Radionuclides and radiation; (2) Radiation detection and measurement; (3) Radiation protection; (4) Radiation chemistry; (5) Effects of radiation on living organisms; (6) Preservation of foods; (7) Radiation preservation of foods; (8) Packaging; (9) Combination processes; (10) Limitations of food irradiation; (11) Wholesomeness of irradiated foods; (12) Government regulation of irradiated foods; (13) Food irradiation facilities; (14) Commercial aspects of food irradiation; (15) Literature sources. The practical part of the Manual contains a revised and expanded series of detailed laboratory exercises in the use of ionizing radiation for food processing

Polarized proton target-III. Operations manual, revision B

International Nuclear Information System (INIS)

Hill, D.; Moretti, A.; Onesto, F.; Rynes, P.

1978-01-01

The manual presented contains certain standard operating procedures for the vacuum, cryogenic, and electronic systems of PPT-III. In total, these systems comprise the following major divisions: (1) the target cryostat; (2) the 4 He pumping system; (3) the 3 He pumping system; (4) the remote monitors and controls; (5) the microwave system; (6) the magnet and power supply; (7) the computerized polarization monitor; (8) the 4 He liquefier and gas recovery system; and (9) miscellaneous auxiliary equipment

Manual on JSSL (JAERI scientific subroutine library)

International Nuclear Information System (INIS)

Fujimura, Toichiro; Nishida, Takahiko; Asai, Kiyoshi

1977-05-01

A manual on the revised JAERI scientific subroutine library is presented. The library is a collection of subroutines developed or modified in JAERI which complements the library installed for FACOM 230-75 computer. It is subject to further extension in the future, since the present one is still insufficient for scientific calculations. (auth.)

User's Manual. Vocational Education Readiness Test (VERT). Revised Edition.

Science.gov (United States)

Thomas, Edward L.; And Others

This user's manual provides information suggesting various ways in which educational personnel may wish to utilize the eight modules included in the Vocational Education Readiness Test (VERT). The introductory section presents questions which can be used by school personnel to determine whether or not VERT will be useful in their school system.…

Advertising, a Distributive Education Manual and Answer Book.

Science.gov (United States)

Martin, Charles H.; Cyrus, Cinda L.

This revised manual for individualized instruction of distributive education trainees at the high school or junior college level in basic advertising and sales promotion activities includes 15 self-study assignments, teaching suggestions, and a bibliography. Together with a separate answer key, each assignment provides student questions and…

Timber designers' manual

CERN Document Server

Ozelton, E C

2008-01-01

This major reference manual covers both overall and detail design of structural timber, including aspects such as shear deflection, creep, dynamic and lateral stability considerations for flexural members.Available for the first time in paperback, the Third Edition was substantially revised to take account of the many changes since the previous edition was published in 1984. It is based on British Standard BS 5268-2: 2002, which brought design concepts closer to European practice and Eurocode 5.Features of the Third Edition include:* information on bolt values including

Environmental Measurements Laboratory (EML) procedures manual

International Nuclear Information System (INIS)

Chieco, N.A.; Bogen, D.C.; Knutson, E.O.

1990-11-01

Volume 1 of this manual documents the procedures and existing technology that are currently used by the Environmental Measurements Laboratory. A section devoted to quality assurance has been included. These procedures have been updated and revised and new procedures have been added. They include: sampling; radiation measurements; analytical chemistry; radionuclide data; special facilities; and specifications. 228 refs., 62 figs., 37 tabs. (FL)

Manual on JSSL (JAERI scientific subroutine library)

International Nuclear Information System (INIS)

Fujimura, Toichiro; Nishida, Takahiko; Asai, Kiyoshi

1979-11-01

A manual on the revised version of JAERI scientific subroutine library is presented. The library is a collection of subroutines developed or modified in JAERI. They are classified into fifteen fields. It is subject to further extension in the future, since there are some fields still insufficient for scientific calculations in the present library. (author)

TA-55 change control manual

International Nuclear Information System (INIS)

Blum, T.W.; Selvage, R.D.; Courtney, K.H.

1997-11-01

This manual is the guide for initiating change at the Plutonium Facility, which handles the processing of plutonium as well as research on plutonium metallurgy. It describes the change and work control processes employed at TA-55 to ensure that all proposed changes are properly identified, reviewed, approved, implemented, tested, and documented so that operations are maintained within the approved safety envelope. All Laboratory groups, their contractors, and subcontractors doing work at TA-55 follow requirements set forth herein. This manual applies to all new and modified processes and experiments inside the TA-55 Plutonium Facility; general plant project (GPP) and line item funded construction projects at TA-55; temporary and permanent changes that directly or indirectly affect structures, systems, or components (SSCs) as described in the safety analysis, including Facility Control System (FCS) software; and major modifications to procedures. This manual does not apply to maintenance performed on process equipment or facility SSCs or the replacement of SSCs or equipment with documented approved equivalents

Why is the Diagnostic and Statistical Manual of Mental Disorders so hard to revise? Path-dependence and "lock-in" in classification.

Science.gov (United States)

Cooper, Rachel

2015-06-01

The latest edition of the Diagnostic and Statistical Manual of Mental Disorders, the D.S.M.-5, was published in May 2013. In the lead up to publication, radical changes to the classification were anticipated; there was widespread dissatisfaction with the previous edition and it was accepted that a "paradigm shift" might be required. In the end, however, and despite huge efforts at revision, the published D.S.M.-5 differs far less than originally envisaged from its predecessor. This paper considers why it is that revising the D.S.M. has become so difficult. The D.S.M. is such an important classification that this question is worth asking in its own right. The case of the D.S.M. can also serve as a study for considering stasis in classification more broadly; why and how can classifications become resistant to change? I suggest that classifications like the D.S.M. can be thought of as forming part of the infrastructure of science, and have much in common with material infrastructure. In particular, as with material technologies, it is possible for "path dependent" development to cause a sub-optimal classification to become "locked in" and hard to replace. Copyright © 2015 Elsevier Ltd. All rights reserved.

Uranium hexafluoride: A manual of good practice ORO 651 revision 6

Energy Technology Data Exchange (ETDEWEB)

Dyer, R.H. [Department of Energy, Oak Ridge, TN (United States)

1991-12-31

The United States Department of Energy publishes a document containing UF{sub 6} handling procedures and descriptions of the approved UF{sub 6} cylinders. Since its initial publication in 1966, it has been frequently revised to provide more and better information. The principle additions to the sixth revision which will be discussed are: (1) more detail on the physical and chemical properties of UF{sub 6}; (2) cold trap description and operation; (3) cylinder emptying and filling concepts; (4) basis for cylinder fill limits; (5) short- and long-term cylinder storage; and (6) cylinder photographs and drawings showing major dimensions.

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.

Online Training and Practice Manual for ERIC Data Base Searchers. 2nd Edition.

Science.gov (United States)

Markey, Karen; Cochrane, Pauline A.

Revised to reflect changes in both DIALOG and ERIC, this second edition of a self-improvement manual for online searchers who wish to refine their skills presents three basic approaches to searching and provides illustrations from DIALOG's ERIC ONTAP database. The manual is divided into two parts: an 8-step model of the total search process which…

Brief Report: An Exploratory Study Comparing Diagnostic Outcomes for Autism Spectrum Disorders under DSM-IV-TR with the Proposed DSM-5 Revision

Science.gov (United States)

Gibbs, Vicki; Aldridge, Fiona; Chandler, Felicity; Witzlsperger, Ellen; Smith, Karen

2012-01-01

The proposed revision for Autism spectrum disorders (ASDs) in the Diagnostic and Statistical Manual of Mental Disorders-Fifth Edition (DSM-5) represents a shift from the Diagnostic and Statistical Manual of Mental Disorders-Fourth Edition, Text Revision (DSM-IV-TR). As the proposed DSM-5 criteria require a higher minimum number of symptoms to be…

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

Photoshop Elements 6 The Missing Manual

CERN Document Server

Brundage, Barbara

2009-01-01

With Photoshop Elements 6, the most popular photo-editing program on Earth just keeps getting better. It's perfect for scrapbooking, email-ready slideshows, Web galleries, you name it. But knowing what to do and when is tricky. That's why our Missing Manual is the bestselling book on the topic. This fully revised guide explains not only how the tools and commands work, but when to use them.

[The Revision and 5th Edition of the Diagnostic and Statistical Manual of Mental Disorders (DSM-5): Consequences for the Diagnostic Work with Children and Adolescents].

Science.gov (United States)

Zulauf Logoz, Marina

2014-01-01

The Revision and 5th Edition of the Diagnostic and Statistical Manual of Mental Disorders (DSM-5): Consequences for the Diagnostic Work with Children and Adolescents.The present paper describes and discusses the major revisions in DSM-5 for children and adolescents. A major modification is that the separate chapter for disorders first diagnosed in childhood and adolescence was abandoned in favour of the integration of these clinical pictures into the relevant disorder-specific chapters. Several new diagnoses and diagnostic groups were introduced: "Disruptive mood regulation disorder" is a new diagnosis; the different diagnoses for autism were brought together into one, and a new diagnostic group for obsessive-compulsive disorders has been established. The developmental approach of DSM-5 and the integration of dimensional assessment tools are to be welcomed. Practice will show if the critiques afraid of possible increases in prevalences or those who approve the changes will end up being right.

Health physics manual of good practices for reducing radiation exposure to levels that are as low as reasonably achievable (ALARA)

International Nuclear Information System (INIS)

Herrington, W.N.; Higby, D.P.; Kathren, R.L.; Merwin, S.E.; Stoetzel, G.A.

1988-06-01

A primary objective of the US Department of Energy (DOE) health physics and radiation protection program has been to limit radiation exposures to those levels that are as low as reasonably achievable (ALARA). As a result, the ALARA concept developed into a program and a set of operational principles to ensure that the objective was consistently met. Implementation of these principles required that a guide be produced. The original ALARA guide was issued by DOE in 1980 to promote improved understanding of ALARA concepts within the DOE community and to assist those responsible for operational ALARA activities in attaining their goals. Since 1980, additional guidance has been published by national and international organizations to provide further definition and clarification to ALARA concepts. As basic ALARA experience increased, the value and role of the original guide prompted the DOE Office of Nuclear Safety (ONS) to support a current revision. The revised manual of good practices includes six sections: 1.0 Introduction, 2.0 Administration, 3.0 Optimization, 4.0 Setting and Evaluating ALARA Goals, 5.0 Radiological Design, and 6.0 Conduct of Operations. The manual is directed primarily to contractor and DOE staff who are responsible for conduct and overview of radiation protection and ALARA programs at DOE facilities. The intent is to provide sufficient guidance such that the manual, if followed, will ensure that radiation exposures are maintained as low as reasonably achievable and will establish the basis for a formally structured and auditable program. 118 refs., 16 figs., 3 tabs

Requirements to be met by the operation manual

International Nuclear Information System (INIS)

1981-03-01

The rule applies to the contents and the lay-out of the operating manual for stationary nuclear power plants. The draft contains: 1. General requirement to be met by the contents of the operating manual. The operating manual to be arranged in 4 parts (part 1: internal rules and regulations; part 2: operation overall plant; part 3: incidents; part 4: operation systems). Safety specifications to be included in the manual, the exemption being the system of technical documentation. 2. General requirements to be met by the lay-out of the operating manual. Comprehensibility; legibility; structure and subdivisions; arrangement of the instructions and design of the manuals cover. 3. Requirements to be met by part 1. Defining the various internal rules and regulations (personnel management); rules and regulations concerning inspections and shift work; maintenance and repair; radiation protection; guard duty and admission; alarm; fire protection; first aid. 4. Requirements to be met by part 2. Provisions and operational limitations; limit values important from the point of view of safety; normal operation; anomalous operation; in-service inspections. 6. Requirements to be met by part 3. 7. Annex: Rules, regulations and stipulations mentioned in the rule draft. (orig.)

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.

Surface Environmental Surveillance Procedures Manual

Energy Technology Data Exchange (ETDEWEB)

RW Hanf; TM Poston

2000-09-20

Environmental surveillance data are used in assessing the impact of current and past site operations on human health and the environment, demonstrating compliance with applicable local, state, and federal environmental regulations, and verifying the adequacy of containment and effluent controls. SESP sampling schedules are reviewed, revised, and published each calendar year in the Hanford Site Environmental Surveillance Master Sampling Schedule. Environmental samples are collected by SESP staff in accordance with the approved sample collection procedures documented in this manual.

Diagnostic and treatment manual of urological cancer

International Nuclear Information System (INIS)

Paz y Mino, Milton; Tafur, Fausto; Cornejo, Francisco; Gaibor, Jose; Bueno, Cesar; Basantes, Amparito

2004-01-01

This book compiles different opinions about researches, diagnosis, methods, procedures and treatment of urological cancer, which will be useful for physicians and specialists of this illness. This manual is well structured in eight chapters with references, illustrations, figures and tables about neoplasms of kidney, urinary tract, urogenital system. This document is a bibliographic revision about ecuadorian experience in urological cancer

Efficacy and Safety of Manual Partial Red Cell Exchange in the Management of Severe Complications of Sickle Cell Disease in a Developing Country

Directory of Open Access Journals (Sweden)

B. F. Faye

2017-01-01

Full Text Available Introduction. The realization of red cell exchange (RCE in Africa faces the lack of blood, transfusion safety, and equipment. We evaluated its efficacy and safety in severe complications of sickle cell disease. Patients and Method. Manual partial RCE was performed among sickle cell patients who had severe complications. Efficacy was evaluated by clinical evolution, blood count, and electrophoresis of hemoglobin. Safety was evaluated on adverse effects, infections, and alloimmunization. Results. We performed 166 partial RCE among 44 patients including 41 homozygous (SS and 2 heterozygous composites SC and 1 S/β0-thalassemia. The mean age was 27.9 years. The sex ratio was 1.58. The regression of symptoms was complete in 100% of persistent vasoocclusive crisis and acute chest syndrome, 56.7% of intermittent priapism, and 30% of stroke. It was partial in 100% of leg ulcers and null in acute priapism. The mean variations of hemoglobin and hematocrit rate after one procedure were, respectively, +1.4 g/dL and +4.4%. That of hemoglobin S after 2 consecutive RCE was −60%. Neither alloimmunization nor viral seroconversion was observed. Conclusion. This work shows the feasibility of manual partial RCE in a low-resource setting and its efficacy and safety during complications of SCD outside of acute priapism.

Efficacy and Safety of Manual Partial Red Cell Exchange in the Management of Severe Complications of Sickle Cell Disease in a Developing Country

Science.gov (United States)

Sow, D.; Seck, M.; Dieng, N.; Toure, S. A.; Gadji, M.; Senghor, A. B.; Gueye, Y. B.; Sy, D.; Sall, A.; Dieye, T. N.; Toure, A. O.; Diop, S.

2017-01-01

Introduction The realization of red cell exchange (RCE) in Africa faces the lack of blood, transfusion safety, and equipment. We evaluated its efficacy and safety in severe complications of sickle cell disease. Patients and Method Manual partial RCE was performed among sickle cell patients who had severe complications. Efficacy was evaluated by clinical evolution, blood count, and electrophoresis of hemoglobin. Safety was evaluated on adverse effects, infections, and alloimmunization. Results We performed 166 partial RCE among 44 patients including 41 homozygous (SS) and 2 heterozygous composites SC and 1 S/β0-thalassemia. The mean age was 27.9 years. The sex ratio was 1.58. The regression of symptoms was complete in 100% of persistent vasoocclusive crisis and acute chest syndrome, 56.7% of intermittent priapism, and 30% of stroke. It was partial in 100% of leg ulcers and null in acute priapism. The mean variations of hemoglobin and hematocrit rate after one procedure were, respectively, +1.4 g/dL and +4.4%. That of hemoglobin S after 2 consecutive RCE was −60%. Neither alloimmunization nor viral seroconversion was observed. Conclusion This work shows the feasibility of manual partial RCE in a low-resource setting and its efficacy and safety during complications of SCD outside of acute priapism. PMID:28584527

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)

Microbial ecology laboratory procedures manual NASA/MSFC

Science.gov (United States)

Huff, Timothy L.

1990-01-01

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

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)

VIPRE-01: a thermal-hydraulic code for reactor cores. Volume 2: user's manual (Revision 2)

International Nuclear Information System (INIS)

Cuta, J.M.; Koontz, A.S.; Stewart, C.W.; Montgomery, S.D.; Nomura, K.K.

1985-07-01

Revisions to the VIPRE code documents for Volume 2 are presented. These revisions conform to the changes made to VIPRE-01, CYCLE-00 to produce the new version of the code denoted by VIPRE-01, CYCLE-01. The first pages of the revisions specify where the replacement pages are to be inserted and which pages of the original documents should be retained

Update of the Dutch manual for costing studies in health care

NARCIS (Netherlands)

T.A. Kanters (Tim A.); C.A.M. Bouwmans-Frijters (Clazien); N. van der Linden (Naomi); S.S. Tan (Siok Swan); L. van Hakkaart-van Roijen (Leona)

2017-01-01

textabstractObjectives: Dutch health economic guidelines include a costing manual, which describes preferred research methodology for costing studies and reference prices to ensure high quality studies and comparability between study outcomes. This paper describes the most important revisions of the

Dry-run of site investigation planning using the manual for preliminary investigation in Japan

International Nuclear Information System (INIS)

Akamura, Shigeki; Miwa, Tadashi; Tanaka, Tatsuya; Shiratsuchi, Hiroshi; Horio, Atsushi

2011-01-01

A stepwise site selection process has been adopted for geological disposal of HLW in Japan. Literature surveys, followed by preliminary investigations (PI) and, finally, detailed investigations in underground facilities will be carried out in the successive selection stages. In the PI stage, surface-based investigations such as borehole surveys and geophysical prospecting will be implemented. In order to conduct the PI appropriately and efficiently within a restricted timeframe and budget, planning and management of PI are very important. NUMO therefore compiled existing knowledge and experience in the planning and managing of investigations in the form of manuals to be used to improve and maintain internal expertise. The first editions of the two manuals were prepared on the basis of experience overseas, and then they were revised by taking technological environment, laws and regulation in Japan into consideration. This paper introduces the procedure of PI planning using manual as well as the results of the dry-run, with the Yokosuka area as a hypothetical PI area, where the monstraction study is under way. Based on the dry-run, applicability of the manual is checked and, at the same time, further revisions are made to improve the content. (author)

Revised SNAP III Training Manual

Energy Technology Data Exchange (ETDEWEB)

Moss, Calvin Elroy [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Gonzales, Samuel M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Myers, William L. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Nelson, Mark Andrew [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Rothrock, Richard Brian [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Salazar, Samuel A. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Sorensen, Eric Byron [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Sundby, Gary M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-11-21

The Shielded Neutron Assay Probe (SNAP) technique was developed to determine the leakage neutron source strength of a radioactive object. The original system consisted of an Eberline^TM Mini-scaler and discrete neutron detector. The system was operated by obtaining the count rate with the Eberline^TM instrument, determining the absolute efficiency from a graph, and calculating the neutron source strength by hand. In 2003 the SNAP III, shown in Figure 1, was designed and built. It required the operator to position the SNAP, and then measure the source-to-detector and detectorto- reflector distances. Next the operator entered the distance measurements and started the data acquisition. The SNAP acquired the required count rate and then calculated and displayed the leakage neutron source strength (NSS). The original design of the SNAP III is described in SNAP III Training Manual (ER-TRN-PLN-0258, Rev. 0, January 2004, prepared by William Baird) This report describes some changes that have been made to the SNAP III. One important change is the addition of a LEMO connector to provide neutron detection output pulses for input to the MC-15. This feature is useful in active interrogation with a neutron generator because the MC-15 has the capability to only record data when it is not gated off by a pulse from the neutron generator. This avoids recording of a lot of data during the generator pulses that are not useful. Another change was the replacement of the infrared RS-232 serial communication output by a similar output via a 4-pin LEMO connector. The current document includes a more complete explanation of how to estimate the amount of moderation around a neutron-emitting source.

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

Outline of manual on measurement and assessment of doses from external radiation

Energy Technology Data Exchange (ETDEWEB)

Yoshizawa, Michio [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Tsujimura, Norio

2001-03-01

The external exposure part in the manual for measurement and assessment of doses from external radiation is described since the part is changed in accordance with the revision of the Law Concerning Prevention from Radiation Hazard due to Radioisotopes, Etc. The manual contains general remarks, control of external exposure and its methods, person monitoring, site monitoring, correction of instruments and storage of records. The 2nd and 3rd chapters are described in details, because which are considerably changed together with appendices concerning the operational quantity for measuring external dose, conversion coefficients, and correlations of 3 mm, 1 cm and 70 {mu}m dose equivalents. Making manuals unique to the individual offices, etc. is recommended in compliance with the above manual.(K.H.)

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

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

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

Field Manual of Wildlife Diseases

Science.gov (United States)

Franson, J. Christian; Friend, Milton; Gibbs, Samantha E.J.; Wild, Margaret A.

2015-01-01

Welcome to a new version of the “Field Manual of Wildlife Diseases.” Unlike the previous printed versions of this publication, this new version is being developed as a “living“ electronic publication. Content will periodically be added and (or) updated as warranted, and it will always be reviewed by scientific experts (“peer reviewed”) before it is released. Thus, this publication will never be completed, and readers should download revised versions of specific chapters, glossaries, and the appendixes whenever they visit the publication Web site.

Relating safety, productivity and company type for motor-manual logging operations in the Italian Alps.

Science.gov (United States)

Montorselli, Niccolò Brachetti; Lombardini, Carolina; Magagnotti, Natascia; Marchi, Enrico; Neri, Francesco; Picchi, Gianni; Spinelli, Raffaele

2010-11-01

The study compared the performance of four different logging crews with respect to productivity, organization and safety. To this purpose, the authors developed a data collection method capable of providing a quantitative analysis of risk-taking behavior. Four crews were tested under the same working conditions, representative of close-to-nature alpine forestry. Motor-manual working methods were applied, since these methods are still prevalent in the specific study area, despite the growing popularity of mechanical processors. Crews from public companies showed a significantly lower frequency of risk-taking behavior. The best safety performance was offered by the only (public) crew that had been administered formal safety training. The study seems to deny the common prejudice that safety practice is inversely proportional to productivity. Instead, productivity is increased by introducing more efficient working methods and equipment. The quantitative analysis of risk-taking behavior developed in this study can be applied to a number of industrial fields besides forestry. Characterizing risk-taking behavior for a given case may eventually lead to the development of custom-made training programmes, which may address problem areas while avoiding that the message is weakened by the inclusion of redundant information. In the specific case of logging crews in the central Alps, the study suggests that current training courses may be weak on ergonomics, and advocates a staged training programme, focusing first on accident reduction and then expanding to the prevention of chronic illness. 2010 Elsevier Ltd. All rights reserved.

Health and Safety Audit Design Manual

Energy Technology Data Exchange (ETDEWEB)

Ternes, Mark P. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Langley, Brandon R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Accawi, Gina K. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Malhotra, Mini [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2017-10-01

The Health and Safety Audit is an electronic audit tool developed by the Oak Ridge National Laboratory to assist in the identification and selection of health and safety measures when a home is being weatherized (i.e., receiving home energy upgrades), especially as part of the US Department of Energy (DOE) Weatherization Assistance Program, or during home energy-efficiency retrofit or remodeling jobs. The audit is specifically applicable to existing single-family homes (including mobile homes), and is generally applicable to individual dwelling units in low-rise multifamily buildings. The health and safety issues covered in the audit are grouped in nine categories: mold and moisture, lead, radon, asbestos, formaldehyde and volatile organic compounds (VOCs), combustion, pest infestation, safety, and ventilation. Development of the audit was supported by the US Department of Housing and Urban Development Office of Healthy Homes and Lead Hazard Control and the DOE Weatherization Assistance Program.

Gunner's Mate G 3 and 2; Rate Training Manual. Revised.

Science.gov (United States)

Naval Education and Training Command, Pensacola, FL.

The rate training manual has been prepared for men of the regular Navy and of the Naval Reserve for the purpose of advancement to increase knowledge in the various aspects of the Gunner's Mate rating (G 3 and 2). Chapters 1 through 14 deal with the following topics: the requirements of the Gunner's Mate G Rating, explosives and pyrotechnics,…

Stirling engine design manual, 2nd edition

Science.gov (United States)

Martini, W. R.

1983-01-01

This manual is intended to serve as an introduction to Stirling cycle heat engines, as a key to the available literature on Stirling engines and to identify nonproprietary Stirling engine design methodologies. Two different fully described Stirling engines are discussed. Engine design methods are categorized as first order, second order, and third order with increased order number indicating increased complexity. FORTRAN programs are listed for both an isothermal second order design program and an adiabatic second order design program. Third order methods are explained and enumerated. In this second edition of the manual the references are updated. A revised personal and corporate author index is given and an expanded directory lists over 80 individuals and companies active in Stirling engines.

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

L-059: EPR-First responders: Radiological emergency manual for first responders

International Nuclear Information System (INIS)

2011-01-01

This conference is an emergency manual review about the first responders knowledge. The IAEA safety standard manuals, the medical gestion, the security forces and the fast communications are very important in a radiological emergency

Should Social Workers Use "Diagnostic and Statistical Manual of Mental Disorders-5?"

Science.gov (United States)

Frances, Allen; Jones, K. Dayle

2014-01-01

Up until now, social workers have depended on the "Diagnostic and Statistical Manual of Mental Disorders" ("DSM") as the primary diagnostic classification for mental disorders. However, the "DSM-5" revision includes scientifically unfounded, inadequately tested, and potentially dangerous diagnoses that may lead them…

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

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)

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.

WAM-E user's manual

International Nuclear Information System (INIS)

Rayes, L.G.; Riley, J.E.

1986-07-01

The WAM-E series of mainframe computer codes have been developed to efficiently analyze the large binary models (e.g., fault trees) used to represent the logic relationships within and between the systems of a nuclear power plant or other large, multisystem entity. These codes have found wide application in reliability and safety studies of nuclear power plant systems. There are now nine codes in the WAM-E series, with six (WAMBAM/WAMTAP, WAMCUT, WAMCUT-II, WAMFM, WAMMRG, and SPASM) classified as Type A Production codes and the other three (WAMFTP, WAMTOP, and WAMCONV) classified as Research codes. This document serves as a combined User's Guide, Programmer's Manual, and Theory Reference for the codes, with emphasis on the Production codes. To that end, the manual is divided into four parts: Part I, Introduction; Part II, Theory and Numerics; Part III, WAM-E User's Guide; and Part IV, WAMMRG Programmer's Manual

Calibration of dosimeters used in radiotherapy. A manual

International Nuclear Information System (INIS)

1994-01-01

The present manual is a revision of IAEA Technical Reports Series No.185, published in 1979. This manual is intended for use by the network of Secondary Standard Dosimetry Laboratories (SSDLs) which was set up by the IAEA and the World Health Organization (WHO). The objectives of the SSDL network are to: calibrate radiation dosimeters and ancillary instruments; serve as a link between primary standard laboratories and radiation users; and provide advice and assistance in all aspects of radiation metrology. The various calibration procedures are described, their relative advantages and disadvantages are discussed, and criteria are put forward to help an SSDL decide which procedure is the best to use in order to meet a particular requirement. The information in this manual should also be of value to other similar laboratories, usually associated with hospitals, which are not formally part of the IAEA/WHO network of SSDLs. 26 refs, 6 figs, 6 tabs

Operating manual for the Health Physics Research Reactor

International Nuclear Information System (INIS)

1985-11-01

This manual is intended to serve as a guide in the operation and maintenance of the Health Physics Researh Reactor (HPRR) of the Health Physics Dosimetry Applications Research (DOSAR) Facility. It includes descriptions of the HPRR and of associated equipment such as the reactor positioning devises and the derrick. Procedures for routine operation of the HPRR are given in detail, and checklists for the various steps are provided where applicable. Emergency procedures are similarly covered, and maintenance schedules are outlined. Also, a bibliography of references giving more detailed information on the DOSAR Facility is included. Changes to this manual will be approved by at least two of the following senior staff members: (1) the Operations Division Director, (2) the Reactor Operations Department Head, (3) the Supervisor of Reactor Operations TSF-HPRR Areas. The master copy and the copy of the manual issued to the HPRR Operations Supervisor will always reflect the latest revision. 22 figs

Monitoring Manual for Determining Compliance with Public Law 94-142. Revised.

Science.gov (United States)

South Carolina State Dept. of Education, Columbia.

Designed to assist service providers as they strive to provide a full service goal for all handicapped pupils, this manual consists of checklists for monitoring compliance with Public Law 94-142 (Education for All Handicapped Children Act). Checklists of components in general policy areas are: (1) policy requirements (LEAs - Local Educational…

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

ETAP user's manual

International Nuclear Information System (INIS)

Watanabe, Norio; Higuchi, Suminori.

1990-11-01

The event tree analysis technique has been used in Probabilistic Safety Assessment for LWRs to delineate various accident scenarios leading to core melt or containment failure and to evaluate their frequencies. This technique often requires manual preparation of event trees with iterative process and time-consuming work in data handling. For the purpose of reducing manual efforts in event tree analysis, we developed a new software package named ETAP (Event Tree Analysis Supporting Program) for event tree analysis. ETAP is an interactive PC-based program which has the ability to construct, update, document, and quantify event trees. Because of its fast running capability to quantify event trees, use of the EATP program can make it easy to perform the sensitivity studies on a variety of system/containment performance issues. This report provides a user's manual for ETAP, which describes the structure, installation, and use of EATP. This software runs on NEC/PC-9800 or compatible PCs that have a 640 KB memory and MS-DOS 2.11 or higher. (author)

OSH technical reference manual

Energy Technology Data Exchange (ETDEWEB)

1993-11-01

In an evaluation of the Department of Energy (DOE) Occupational Safety and Health programs for government-owned contractor-operated (GOCO) activities, the Department of Labor`s Occupational Safety and Health Administration (OSHA) recommended a technical information exchange program. The intent was to share written safety and health programs, plans, training manuals, and materials within the entire DOE community. The OSH Technical Reference (OTR) helps support the secretary`s response to the OSHA finding by providing a one-stop resource and referral for technical information that relates to safe operations and practice. It also serves as a technical information exchange tool to reference DOE-wide materials pertinent to specific safety topics and, with some modification, as a training aid. The OTR bridges the gap between general safety documents and very specific requirements documents. It is tailored to the DOE community and incorporates DOE field experience.

An evaluation of methods assessing the physical demands of manual lifting in scaffolding

NARCIS (Netherlands)

Beek, van der A.J.; Mathiassen, S.E.; Windhorst, J.; Burdorf, A.

2005-01-01

Four methods assessing the physical demands of manual lifting were compared. The scaffolding job was evaluated and three distinct scaffolding tasks were ranked using: (1) the revised NIOSH lifting equation (NIOSH method), (2) lifting guidelines for the Dutch construction industry (Arbouw method),

Manual on panoramic gamma irradiators (categories 2 and 4). Incorporating: Applications guide, procedures guide, basics guide

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-03-01

The document is the first revision of a previous one published in 1993 to provide guidance on the safe use and regulation of self-contained gamma irradiators (Co-60 or Cs-137 sources) in different fields of application. It includes three parts: Applications Guide, which describes the main applications of self-contained gamma irradiators, the type of equipment, including safety systems, operation and maintenance, and how to deal with incidents. Procedures Guide, which gives step by step instructions on how to carry out the practice. Basics Guide, which explains the fundamentals of radiation, the system of units, interaction of radiation with matter radiation detection, etc. The manual is aimed primarily at persons handling such radiation sources on a daily routine basis, as well as at the competent authorities for training of workers in radiation protection or for setting up local radiation protection rules.

Manual on panoramic gamma irradiators (categories 2 and 4). Incorporating: Applications guide, procedures guide, basics guide

International Nuclear Information System (INIS)

1996-01-01

The document is the first revision of a previous one published in 1993 to provide guidance on the safe use and regulation of self-contained gamma irradiators (Co-60 or Cs-137 sources) in different fields of application. It includes three parts: Applications Guide, which describes the main applications of self-contained gamma irradiators, the type of equipment, including safety systems, operation and maintenance, and how to deal with incidents. Procedures Guide, which gives step by step instructions on how to carry out the practice. Basics Guide, which explains the fundamentals of radiation, the system of units, interaction of radiation with matter radiation detection, etc. The manual is aimed primarily at persons handling such radiation sources on a daily routine basis, as well as at the competent authorities for training of workers in radiation protection or for setting up local radiation protection rules

HANSF 1.3 Users Manual FAI/98-40-R2 Hanford Spent Nuclear Fuel (SNF) Safety Analysis Model [SEC 1 and 2

Energy Technology Data Exchange (ETDEWEB)

DUNCAN, D.R.

1999-10-07

The HANSF analysis tool is an integrated model considering phenomena inside a multi-canister overpack (MCO) spent nuclear fuel container such as fuel oxidation, convective and radiative heat transfer, and the potential for fission product release. This manual reflects the HANSF version 1.3.2, a revised version of 1.3.1. HANSF 1.3.2 was written to correct minor errors and to allow modeling of condensate flow on the MCO inner surface. HANSF 1.3.2 is intended for use on personal computers such as IBM-compatible machines with Intel processors running under Lahey TI or digital Visual FORTRAN, Version 6.0, but this does not preclude operation in other environments.

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

U.S. Department of Energy Vehicle Technologies Program: Battery Test Manual For Plug-In Hybrid Electric Vehicles

Energy Technology Data Exchange (ETDEWEB)

Christophersen, Jon P. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2014-09-01

This battery test procedure manual was prepared for the United States Department of Energy (DOE), Office of Energy Efficiency and Renewable Energy (EERE), Vehicle Technologies Office. It is based on technical targets for commercial viability established for energy storage development projects aimed at meeting system level DOE goals for Plug-in Hybrid Electric Vehicles (PHEV). The specific procedures defined in this manual support the performance and life characterization of advanced battery devices under development for PHEV’s. However, it does share some methods described in the previously published battery test manual for power-assist hybrid electric vehicles. Due to the complexity of some of the procedures and supporting analysis, future revisions including some modifications and clarifications of these procedures are expected. As in previous battery and capacitor test manuals, this version of the manual defines testing methods for full-size battery systems, along with provisions for scaling these tests for modules, cells or other subscale level devices. The DOE-United States Advanced Battery Consortium (USABC), Technical Advisory Committee (TAC) supported the development of the manual. Technical Team points of contact responsible for its development and revision are Renata M. Arsenault of Ford Motor Company and Jon P. Christophersen of the Idaho National Laboratory. The development of this manual was funded by the Unites States Department of Energy, Office of Energy Efficiency and Renewable Energy, Vehicle Technologies Office. Technical direction from DOE was provided by David Howell, Energy Storage R&D Manager and Hybrid Electric Systems Team Leader. Comments and questions regarding the manual should be directed to Jon P. Christophersen at the Idaho National Laboratory (jon.christophersen@inl.gov).

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.

Manual on industrial radiography

International Nuclear Information System (INIS)

1981-08-01

This manual is intended as a source of educational material to personnel seeking certification as industrial radiographers, and as a guide and reference text for educational organizations that are providng courses in industrial radiography. It covers the basic principles of x-ray and gamma radiation, radiation safety, films and film processing, welding, casting and forging, aircraft structures and components, radiographic techniques, and records

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)

Methane measurements manual; Handbok metanmaetningar

Energy Technology Data Exchange (ETDEWEB)

Holmgren, Magnus Andreas (SP Technical research institute of Sweden, Boraas (Sweden))

2011-02-15

Emissions to air in different parts of the system may arise in biogas plants, where there is biological treatment of organic matter by anaerobic degradation, and during upgrading of biogas to vehicle fuel. There are mainly four reasons why these emissions must be minimized. These are safety, greenhouse gas emissions, economy and smell. This manual gathers experience of several years of work with measurement of methane emissions from biogas and upgrading facilities. This work has been done mainly in the context of Swedish Waste Management's system of voluntary commitment. The purpose of this manual is to standardize methods and procedures when methane measurements are carried out so that the results are comparable between different providers. The main target group of the manual is measurement consultants performing such measurements. Calculation template in Excel is part of the manual, which further contributes to the measurements evaluated in a standardized way. The manual contains several examples which have been calculated in the accompanying Excel template. The handbook also contains a chapter mainly intended for facility staff, in which implementation of accurate leak detection is described, and where there are hints of a system of so-called intermediate inspections to detect leaks in time

A systematic approach for safety evidence collection in the safety-critical domain

NARCIS (Netherlands)

Lin, H.; Wu, Ji; Yuan, C.; Luo, Y.; Brand, van den M.G.J.; Engelen, L.J.P.

2015-01-01

In order to show that the required safety objectives are met, it is necessary to collect safety evidence in the form of consistent and complete data. However, manual safety evidence collection is usually tedious and time-consuming, due to a large number of artifacts and implicit relations between

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

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.

14 CFR 135.23 - Manual contents.

Science.gov (United States)

2010-01-01

... AND ON DEMAND OPERATIONS AND RULES GOVERNING PERSONS ON BOARD SUCH AIRCRAFT General § 135.23 Manual... this section, to assist each crewmember and person performing or directly supervising the following job... Analysis establishing runway safety margins at destination airports, taking into account the following...

Surface Environmental Surveillance Procedures Manual

International Nuclear Information System (INIS)

Hanf, Robert W.; Poston, Ted M.

2000-01-01

Shows and explains certain procedures needed for surface environmental surveillance. Hanford Site environmental surveillance is conducted by the Pacific Northwest National Laboratory (PNNL) for the U.S. Department of Energy (DOE) under the Surface Environmental Surveillance Project (SESP). The basic requirements for site surveillance are set fourth in DOE Order 5400.1, General Environmental Protection Program Requirements. Guidance for the SESP is provided in DOE Order 5484.1, Environmental Protection, Safety, and Health Protection Information Reporting Requirements and DOE Order 5400.5, Radiation Protection of the Public and Environment. Guidelines for environmental surveillance activities are provided in DOE/EH-0173T, Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance. An environmental monitoring plan for the Hanford Site is outlined in DOE/RL 91-50 Rev. 2, Environmental Monitoring Plan, United States Department of Energy, Richland Operations Office. Environmental surveillance data are used in assessing the impact of current and past site operations on human health and the environment, demonstrating compliance with applicable local, state, and federal environmental regulations, and verifying the adequacy of containment and effluent controls. SESP sampling schedules are reviewed, revised, and published each calendar year in the Hanford Site Environmental Surveillance Master Sampling Schedule. Environmental samples are collected by SESP staff in accordance with the approved sample collection procedures documented in this manual. Personnel training requirements are documented in SESP-TP-01 Rev.2, Surface Environmental Surveillance Project Training Program.

Considerations to improve the safety of cervical spine manual therapy.

Science.gov (United States)

Hutting, Nathan; Kerry, Roger; Coppieters, Michel W; Scholten-Peeters, Gwendolijne G M

2018-02-01

Manipulation and mobilisation of the cervical spine are well established interventions in the management of patients with headache and/or neck pain. However, their benefits are accompanied by potential, yet rare risks in terms of serious adverse events, including neurovascular insult to the brain. A recent international framework for risk assessment and management offers directions in the mitigation of this risk by facilitating sound clinical reasoning. The aim of this article is to critically reflect on and summarize the current knowledge about cervical spine manual therapy and to provide guidance for clinical reasoning for cervical spine manual therapy. Copyright © 2017 Elsevier Ltd. All rights reserved.

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)

H. W. Laboratory manual: 100 Area section

Energy Technology Data Exchange (ETDEWEB)

1950-07-01

The purpose of this manual is to present a Hazard Breakdown of all jobs normally encountered in the laboratory work of the three sections comprising the Analytic Section, Metallurgy and Control Division of the Technical Department. A Hazard Breakdown is a careful analysis of any job in which the source of possible dangers is clearly indicated for each particular step. The analysis is prepared by individuals who are thoroughly familiar with the specific job or procedure. It is felt that if the hazards herein outlined are recognized by the Laboratory personnel and the suggested safety cautions followed, the chance for injury will be minimized and the worker will become generally more safety conscious. The manual, which is prefaced by the general safety rules applying to all the laboratories, is divided into three main sections, one for each of the three sections into which the Laboratories Division is divided. These sections are as follows: Section 1 -- 200 Area Control; Section 2 -- 100 Area Control; Section 3 -- 300 Area Control, Essential Materials, and Methods Improvement.

A Manual for the Anchorage School District Bilingual Education Program Revised Scope and Sequence, K-3.

Science.gov (United States)

Heinrich, Maria Nieves Bumanlag Lilagan

The manual offers a systematic set of procedures and relevant information to facilitate effective use of the Anchorage school district (ASD) bilingual education program (BEP). The historical background of the program's development is presented, available manuals for teaching English to limited English proficiency (LEP) students and related…

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.

Polymer Exemption Guidance Manual for premanufacture notices for new chemicals under the Toxic Substances Control Act (TSCA)

Science.gov (United States)

A technical manual to accompany, but not supersede the Premanufacture Notification Exemptions; Revisions of Exemptions for Polymers; Final Rule found at 40 CFR Part 723, (60) FR 16316-16336, published Wednesday, March 29, 1995.

World of Work--Personality Development. Kit No. WW-703. Instructor's Manual. Revised.

Science.gov (United States)

Miles, Mamie Rose; Frank, Louise

This instructor's manual contains activities for teaching students about desirable and objectionable personality traits, the role that physical appearance plays in the way that others perceive them, business manners, and character traits. It is designed for use in three to four periods in classes in prevocational education in South Carolina. The…

Manual on quality assurance for the survey, evaluation and confirmation of nuclear power plant sites

International Nuclear Information System (INIS)

1987-04-01

The present Manual on Quality Assurance for the Survey, Evaluation and Confirmation of Nuclear Power Plant Sites contains supporting material and illustrates examples for implementing the requirements contained in the Code of Practice on Quality Assurance for Safety in Nuclear Power Plants to the activities of survey, evaluation and confirmation of nuclear power plant sites. At the same time the Code of Practice for Safety in Nuclear Power Plant Siting, and Safety Guides in the siting series contain requirements and recommendations to implement a quality assurance programme in selected activities of the siting process. This manual is intended to provide guidance and illustrate examples on this implementation. During preparation and reviews of this Manual it was found out that the methodology of implementation of the quality assurance programme in siting activities is still under development. For these reasons it was considered appropriate to publish this Manual as a temporary publication for trial use

Naturalistic driving observations of manual and visual-manual interactions with navigation systems and mobile phones while driving.

NARCIS (Netherlands)

Christoph, M. Nes, N. van & Knapper, A.

2014-01-01

This paper discusses a naturalistic driving study on the use of mobile phones and navigation systems while driving. Manual interactions with these devices while driving can cause distraction from the driving task and reduce traffic safety. In this study 21 subjects were observed for 5 weeks. Their

A diagnostic and statistical manual of mental disorders history of premenstrual dysphoric disorder.

Science.gov (United States)

Zachar, Peter; Kendler, Kenneth S

2014-04-01

The proposals to include a menstruation-related mood disorder in the Diagnostic and Statistical Manual of Mental Disorders, Revised Third Edition (DSM-III-R), and DSM-IV led to intense public and behind-the-scenes controversy. Although the controversies surrounding the DSM-5 revision were greater in number than the controversies of the earlier revisions, the DSM-5 proposal to include a menstruation-related mood disorder was not among them. Premenstrual dysphoric disorder was made an official disorder in the DSM-5 with no significant protest. To understand the factors that led to this change, we interviewed those psychiatrists and psychologists who were most involved in the DSM-IV revision. On the basis of these interviews, we offer a list of empirical and nonempirical considerations that led to the DSM-IV compromise and explore how key alterations in these considerations led to a different outcome for the DSM-5.

Making an Adjustable C-Clamp. Kit No. 603. Instructor's Manual [and] Student Learning Activity Manual. [Revised.] T & I--Metalwork.

Science.gov (United States)

White, Jim; Alexander, Larry

This student activity kit consists of a programmed, self-instructional learning guide and an accompanying instructor's manual for use in teaching trade and industrial education students how to make an adjustable C-clamp. The student guide contains step-by-step instructions in the following areas: basic layout principles; use of a hack saw, file,…

Integration of a browser based operator manual in the system environment of a process computer system

International Nuclear Information System (INIS)

Weber, Andreas; Erfle, Robert; Feinkohl, Dirk

2012-01-01

The integration of a browser based operator manual in the system environment of a process computer system is an optimization of the operating procedure in the control room and a safety enhancement due to faster and error-free access to the manual contents. Several requirements by the authorities have to be fulfilled: the operating manual has to be available as hard copy, the format has to be true to original, protection against manipulation has to be provided, the manual content of the browser-based version and the hard copy have to identical, and the display presentation has to be consistent with ergonomic principals. The integration of the on-line manual in the surveillance process computer system provides the operator with the relevant comments to the surveillance signal. The described integration of the on-line manual is an optimization of the operator's everyday job with respect to ergonomics and safety (human performance).

Survey Procedures Manual for the Environmental Survey and Site Assessment Program (ESSAP). Revision 10

International Nuclear Information System (INIS)

2000-01-01

The Environmental Survey and Site Assessment Program (ESSAP) of the Oak Ridge Institute for Science and Education (ORISE) conducts radiological survey activities under a contract with the U. S. Department of Energy (DOE) and for the U.S. Nuclear Regulatory Commission (NRC). ORISE and its programs are operated by Oak Ridge Associated Universities (ORAU) through a contract with DOE. The purpose of this Procedures Manual is to provide a standardized set of procedures that document activities of the program in an auditable manner. These procedures are applicable to both DOE and NRC operations. Procedures presented in this manual are limited to those associated with site survey activities

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

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.

International Cooperative Programme for Assessment and Monitoring of Acidification of Rivers and Lakes. Programme Manual

Energy Technology Data Exchange (ETDEWEB)

Bowman, J.; Forsius, M.; Jeffries, D. [and others

1996-12-31

The International Cooperative Programme for Assessment of Acidification of Rivers and lakes (ICP Waters) was established in 1985 by the UN/ECE Executive Body for the Convention of Long-Range Transboundary Air Pollution. Achieving the programme objectives requires that both the temporally intensive and regionally extensive data are collected on a continuing basis. To guide the development and harmonization of the various national contributions, a manual was worked out. The present report is an expanded and consolidated revision of that manual. 33 refs., 3 tabs.

Tracer manual on crops and soils

International Nuclear Information System (INIS)

1976-01-01

The manual serves as a reference for agricultural scientists planning to use nuclear techniques. Training courses are held at various locations with different staff. The existence of a laboratory training manual is helpful to organizers, visiting lecturers, demonstrators and participants. It was primarily written for soil scientists from developing countries participating in training courses on the use of isotopes and radiation in soil-water-plant relations research. The training courses are designed to give soil scientists the basic terms and principles necessary for understanding ionizing radiation, its detection and measurement, its associated hazards and most of the more common applications. Due consideration is also given to the detection of stable isotopes and providing a clear understanding of their potential in research on crops and soils. Each experiment included this revised and updated manual (see IAEA Technical Reports Series No. 29: The Laboratory Training Manual on the Use of Isotopes and Radiation in Soil-Plant Relations Research, published in 1964) has been performed and tested for suitability in training courses. To facilitate the task of organizers in preparing for and planning the programmes of training courses, detailed information is provided on each experiment, indicating the time required for its performance and the necessary equipment, glassware, isotopes, chemicals, etc. A comprehensive glossary is included so that scientists may easily understand terms, units and expressions commonly used in this work. The glossary may also serve as an index since it includes the page number referring to the first mention of the term or expression

Manual on self-contained gamma irradiators (categories 1 and 3). Incorporating: Applications guide, procedures guide, basics guide

International Nuclear Information System (INIS)

1996-01-01

The document is the first revision of a previous one published in 1993 to provide guidance on the safe use and regulation of panoramic gamma irradiators (Co-60 or Cs-137 sources) in different fields of application. It includes three parts: Applications Guide, which describes the main applications of panoramic gamma irradiators, the type of equipment, including safety systems, operation and maintenance, and how to deal with incidents. Procedures Guide, which gives step by step instructions on how to carry out the practice. Basics Guide, which explains the fundamentals of radiation, the system of units, interaction of radiation with matter radiation detection, etc. and which is common to all documents in the series. The manual is aimed primarily at persons handling such radiation sources on a daily routine basis, as well as at the competent authorities for training of workers in radiation protection or for setting up local radiation protection rules

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)

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)

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

Construction safety program for the National Ignition Facility, Appendix B

Energy Technology Data Exchange (ETDEWEB)

Cerruti, S.J.

1997-06-26

This Appendix contains material from the LLNL Health and Safety Manual as listed below. For sections not included in this list, please refer to the Manual itself. The areas covered are: asbestos, lead, fire prevention, lockout, and tag program confined space traffic safety.

Construction safety program for the National Ignition Facility, Appendix B

International Nuclear Information System (INIS)

Cerruti, S.J.

1997-01-01

This Appendix contains material from the LLNL Health and Safety Manual as listed below. For sections not included in this list, please refer to the Manual itself. The areas covered are: asbestos, lead, fire prevention, lockout, and tag program confined space traffic safety

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.)

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.

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.

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…

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

2011 Annual Criticality Safety Program Performance Summary

Energy Technology Data Exchange (ETDEWEB)

Andrea Hoffman

2011-12-01

TSR limits fuel plate bundles to 1085 grams U-235, which is the maximum loading of an ATR fuel element. The overloaded fuel plate bundle contained 1097 grams U-235 and was assembled under an 1100 gram U-235 limit in 1982. In 2003, the limit was reduced to 1085 grams citing a new criticality safety evaluation for ATR fuel elements. The fuel plate bundle inventories were not checked for compliance prior to implementing the reduced limit. A subsequent review of the NMIS inventory did not identify further violations. Requirements Management - The INL Criticality Safety program is organized and well documented. The source requirements for the INL Criticality Safety Program are from 10 CFR 830.204, DOE Order 420.1B, Chapter III, 'Nuclear Criticality Safety,' ANSI/ANS 8-series Industry Standards, and DOE Standards. These source requirements are documented in LRD-18001, 'INL Criticality Safety Program Requirements Manual.' The majority of the criticality safety source requirements are contained in DOE Order 420.1B because it invokes all of the ANSI/ANS 8-Series Standards. DOE Order 420.1B also invokes several DOE Standards, including DOE-STD-3007, 'Guidelines for Preparing Criticality Safety Evaluations at Department of Energy Non-Reactor Nuclear Facilities.' DOE Order 420.1B contains requirements for DOE 'Heads of Field Elements' to approve the criticality safety program and specific elements of the program, namely, the qualification of criticality staff and the method for preparing criticality safety evaluations. This was accomplished by the approval of SAR-400, 'INL Standardized Nuclear Safety Basis Manual,' Chapter 6, 'Prevention of Inadvertent Criticality.' Chapter 6 of SAR-400 contains sufficient detail and/or reference to the specific DOE and contractor documents that adequately describe the INL Criticality Safety Program per the elements specified in DOE Order 420.1B. The Safety Evaluation Report for SAR-400

S-HAL : safety handbook for locals.

Science.gov (United States)

2014-01-01

The Safety Handbook for Locals (S-HAL) is intended to be a comprehensive : traffic safety resource for all local communities in Missouri, be it cities or : counties. The S-HAL mirrors the national Highway Safety Manual (HSM) : (AASHTO, 2010) in using...

Maintenance manual. Vol. 1. Maintenance management; 2. completely rev. ed.; Handbuch Instandhaltung. Bd. 1. Instandhaltungsmanagement

Energy Technology Data Exchange (ETDEWEB)

Warnecke, H.J. [ed.] [Fraunhofer-Institut fuer Produktionstechnik und Automatisierung (IPA), Stuttgart (Germany)

1992-12-31

This manual is the second, completely revised edition of the standard manual ``Maintenance - Fundamentals``, which was first published in 1981. It presents an outline of all relevant fields of maintenance today and contains practical information on new and established methods of maintenance management and technology. With its comprehensive concept, which addresses any industrial enterprise that wants to remain competitive, the manual is indispensable for maintenance managers in industry, service enterprises and consultancies. Vol.1, ``Maintenance Management``, informs the reader on fundamentals, design with a view to maintenance, organisation of maintenance work, personnel management, industrial safety and economic aspects of maintenance. Current issues such as product liability, electronic data processing, expert systems, environmental protection, controlling based on characteristic data, etc. are gone into. Graphical representations, concrete procedural information and exemplary solutions may be used directly as working tools for the practice of maintenance. (orig.) [Deutsch] Das vorliegende Handbuch ist die zweite, voellig ueberarbeitete und erweiterte Auflage des Standardwerkes ``Instandhaltung - Grundlagen``, das 1981 erstmals erschien. Es gibt einen Ueberblick ueber alle relevanten Gebiete einer modernen Instandhaltung und vermittelt praxisnahes Wissen ueber neue und bewaehrte Methoden und Verfahren des Instandhaltungsmanagements und der Instandhaltungstechnik. Mit dieser umfassenden Konzeption, die auf die Belange des im Wettbewerb stehenden Industriebetriebes ausgerichtet ist, wendet sich das Handbuch an die Fuehrungskraefte der Instandhaltung in der Industrie sowie an Dienstleistungs- und Beratungsunternehmen. Im Band 1 ``Instandhaltungsmanagement`` kann sich der Leser ueber Grundlagen, instandhaltungsgerechtes Konstruieren, Organisation der Instandhaltung, Personalmanagement, Arbeitssicherheit sowie Wirtschaftlichkeit der Instandhaltung informieren

Generic communications index: User's manual

International Nuclear Information System (INIS)

Dean, R.S.; Steinbrecher, D.H.; Hennick, A.

1987-12-01

This report is a manual for providing information required to use a special computer program developed by the NRC for indexing generic communications. The program is written in a user-friendly menu driven form using dBASE III programming language. It facilitates use of the required dBASE III search and sort capabilities to access records in a database called Generic Communications Index. This index is made up of one record each for all bulletins, circulars, and information notices, including revisions and supplements, from 1971, when such documentation started, through 1986 (or to the latest update). The program is designed for use by anyone modestly acquainted with the general use of IBM-compatible personal computers. The manual contains both a brief overview and a detailed description of the program, as well as detailed instructions for getting started using the program on a personal computer with either a two-floppy disk or a hard disk system. Included at the end are a brief description of how to handle problems which might occur, and notes on the makeup of the program and database files for help in adding records of communications for future years

Ergonomics intervention in manual handling of oxygen

Directory of Open Access Journals (Sweden)

M Motamedzadeh

2013-05-01

Conclusion: With the implementation of ergonomic intervention is casting unit, the risk of exposure to musculoskeletal disorders caused by manual handling of oxygen cylinders was eliminated and safety of employees against the risk of explosion of the cylinders in comparison with before the intervention was improved.

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

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...

A User’s Manual for the Revised Defense Translator Model

Science.gov (United States)

1990-06-01

Sed emmsabt f t bebon *aMs w swq s ulma o6 ig embalm of iwumbe. SAin m ggidam fo muft Odm hkinuso V WUm&gmn beadawimo Swnle. 0omM fot hngmma ft Osmdm wd...Subsequently, the translator has undergone a series of revisions in order to reflect changes in computational methods and in the amount and types of goods...ELECTRONIC COMPONENTS, N.E.C. 0.13643 341 STORAGE BATTERIES 0.03045 342 PRIMARY BATTERIES, DRY & WET 0.09329 343 X-RAY APPRATUS & TUBES 0.00415 345 ELECTRICAL

Road safety audits: The way forward

CSIR Research Space (South Africa)

Labuschagne, FJJ

2010-08-01

Full Text Available The South African Road Safety Manual (SARSM) was published in 1999 and includes guidelines on road safety audits (RSA). The development of SARSM was a proactive process for improving the road environment with respect to road safety but was never...

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

Laboratory Safety Manual for Alabama Schools. Bulletin 1975. No. 20.

Science.gov (United States)

Alabama State Dept. of Education, Montgomery.

This document presents the Alabama State Department of Education guidelines for science laboratory safety, equipment, storage, chemical safety, rocket safety, electrical safety, safety with radioisotopes, and safety with biologicals. Also included is a brief bibliography, a teacher's checklist, a listing of laser facts and regulations, and a…

Automated Transportation Management System (ATMS) user's manual. Revision 1

International Nuclear Information System (INIS)

Smith, P.D.

1994-01-01

The Automated Transportation Management System (ATMS) Software User Guide (SUG) constitutes the user procedures for the ATMS System. Information in this document will be used by the user to operate the automated system. It is intended to be used as a reference manual to guide and direct the user(s) through the ATMS software product and its environment. The objectives of ATMS are as follows: to better support the Procurement function with freight rate information; to free Transportation Logistics personnel from routine activities such as the auditing and input of freight billing information; to comply with Headquarters Department of Energy-Inspector General (DOE-IG) audit findings to automate transportation management functions; to reduce the keying of data into the Shipment Mobility Accountability Collection (SMAC) database; and to provide automation for the preparing of Bill of Lading, Declaration of Dangerous Goods, Emergency Response Guide and shipping Labels using HM181 Retrieval of hazardous material table text information

Manual for JSSL (JAERI Scientific Subroutine Library)

International Nuclear Information System (INIS)

Fujimura, Toichiro; Tsutsui, Tsuneo

1991-09-01

JSSL (JAERI Scientific Subroutine Library) is a library of scientific subroutines developed or modified in JAERI. They are classified into sixteen fields (Special Functions, Linear Problems, Eigenvalue and Eigenvector Problems, Non Linear Problems, Mathematical Programming, Extreme Value Problems, Transformations, Functional Approximation Methods, Numerical Differential and Integral Methods, Numerical Differential and Integral Equations, Statistical Functions, Physical Problems, I/O Routines, Plotter Routines, Computer System Functions and Others). This report is the user manual for the revised version of JSSL which involves evaluated subroutines selected from the previous compilation of JSSL, applied in almost all the fields. (author)

Creating a web site the missing manual

CERN Document Server

MacDonald, Matthew

2008-01-01

Think you have to be a technical wizard to build a great web site? Think again. If you want to create an engaging web site, this thoroughly revised, completely updated edition of Creating a Web Site: The Missing Manual demystifies the process and provides tools, techniques, and expert guidance for developing a professional and reliable web presence. Whether you want to build a personal web site, an e-commerce site, a blog, or a web site for a specific occasion or promotion, this book gives you detailed instructions and clear-headed advice for: Everything from planning to launching. From pi

Right Of Way Pest Control. Manual 88.

Science.gov (United States)

Missouri Univ., Columbia. Agricultural Experiment Station.

This training manual provides information needed to meet the minimum EPA standards for certification as a commercial applicator of pesticides in the right-of-way pest control category. The text discusses types of vegetation, the nature of herbicides, application methods, use for specific situations, and safety precautions. (CS)

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)

World of Work--Choosing a Career. Kit No. WW-704. Instructor's Manual. Revised.

Science.gov (United States)

Miles, Mamie Rose; Killingsworth, Linda

This instructor's manual contains activities for teaching students about occupational categories, job requirements versus personal characteristics, the steps to take in making an occupational choice, and the vocational training programs offered by area vocational centers. It is designed for use in six to eight periods in classes in prevocational…

Manual Development and Pilot Testing of a Mindfulness- and Acceptance-Based Intervention for Increasing Cardiorespiratory Fitness in Sedentary Adults

OpenAIRE

Martin, Emily Cecile

2012-01-01

The aim of this research project was to conduct a manual development study and an open clinical trial in order to demonstrate the feasibility and efficacy of a mindfulness and acceptance based intervention for increasing cardiorespiratory fitness (CRF) in sedentary adults through adherence to a fitness walking program. Development of the treatment manual followed a 3-phase process (literature review and initial draft preparation, expert review, draft revision) based on expert systems analysis...

Waste Management Technical Manual

Energy Technology Data Exchange (ETDEWEB)

Buckingham, J.S. [ed.

1967-08-31

This Manual has been prepared to provide a documented compendium of the technical bases and general physical features of Isochem Incorporated`s Waste Management Program. The manual is intended to be used as a means of training and as a reference handbook for use by personnel responsible for executing the Waste Management Program. The material in this manual was assembled by members of Isochem`s Chemical Processing Division, Battelle Northwest Laboratory, and Hanford Engineering Services between September 1965 and March 1967. The manual is divided into the following parts: Introduction, contains a summary of the overall Waste Management Program. It is written to provide the reader with a synoptic view and as an aid in understanding the subsequent parts; Feed Material, contains detailed discussion of the type and sources of feed material used in the Waste Management Program, including a chapter on nuclear reactions and the formation of fission products; Waste Fractionization Plant Processing, contains detailed discussions of the processes used in the Waste Fractionization Plant with supporting data and documentation of the technology employed; Waste Fractionization Plant Product and Waste Effluent Handling, contains detailed discussions of the methods of handling the product and waste material generated by the Waste Fractionization Plant; Plant and Equipment, describes the layout of the Waste Management facilities, arrangement of equipment, and individual equipment pieces; Process Control, describes the instruments and analytical methods used for process control; and Safety describes process hazards and the methods used to safeguard against them.

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

Directory of Open Access Journals (Sweden)

Giorgia Bagagiolo

2017-12-01

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

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

Safety of SSRIs during pregnancy: a controlled study.

Science.gov (United States)

Altamura, A C; De Gaspari, I F; Rovera, C; Colombo, E M; Mauri, M C; Fedele, L

2013-01-01

The objective of our study was to analyze the efficacy and the safety of SSRIs during pregnancy. A group of 30 pregnant women affected by Major Depressive Disorder by SCID I interview (Diagnostic and Statistical Manual of Mental Disorders, Fourth Edition Text Revision criteria) and treated with selective serotonin reuptake inhibitor (SSRI) were included in the study. They were matched to a comparison group of 26 pregnant women. There were no statistically significant differences in any of the pregnancy outcomes of interest between the treated women and comparison group. There was no statistically significant association in newborns of women treated with an SSRI and the control group in the first and fifth minute Apgar score, and no newborns were admitted to neonatal Intensive Care Units. No definitive association between use of SSRIs during pregnancy and an increased risk of birth defects or other adverse outcomes could be found. Copyright © 2012 John Wiley & Sons, Ltd.

Computer Program of SIE ASME-NH (Revision 1.0) Code

Energy Technology Data Exchange (ETDEWEB)

Koo, Gyeong Hoi; Lee, J. H

2008-01-15

In this report, the SIE ASME (Structural Integrity Evaluations by ASME-NH) (Revision 1.0), which has a computerized implementation of ASME Pressure Vessels and Piping Code Section III Subsection NH rules, is developed to apply to the next generation reactor design subjecting to the elevated temperature operations over 500 .deg. C and over 30 years design lifetime, and the user's manual for this program is described in detail.

Computer Program of SIE ASME-NH (Revision 1.0) Code

International Nuclear Information System (INIS)

Koo, Gyeong Hoi; Lee, J. H.

2008-01-01

In this report, the SIE ASME (Structural Integrity Evaluations by ASME-NH) (Revision 1.0), which has a computerized implementation of ASME Pressure Vessels and Piping Code Section III Subsection NH rules, is developed to apply to the next generation reactor design subjecting to the elevated temperature operations over 500 .deg. C and over 30 years design lifetime, and the user's manual for this program is described in detail

The structure of Diagnostic and Statistical Manual of Mental Disorders (4th edition, text revision) personality disorder symptoms in a large national sample.

Science.gov (United States)

Trull, Timothy J; Vergés, Alvaro; Wood, Phillip K; Jahng, Seungmin; Sher, Kenneth J

2012-10-01

We examined the latent structure underlying the criteria for DSM-IV-TR (American Psychiatric Association, 2000, Diagnostic and statistical manual of mental disorders (4th ed., text revision). Washington, DC: Author.) personality disorders in a large nationally representative sample of U.S. adults. Personality disorder symptom data were collected using a structured diagnostic interview from approximately 35,000 adults assessed over two waves of data collection in the National Epidemiologic Survey on Alcohol and Related Conditions. Our analyses suggested that a seven-factor solution provided the best fit for the data, and these factors were marked primarily by one or at most two personality disorder criteria sets. A series of regression analyses that used external validators tapping Axis I psychopathology, treatment for mental health problems, functioning scores, interpersonal conflict, and suicidal ideation and behavior provided support for the seven-factor solution. We discuss these findings in the context of previous studies that have examined the structure underlying the personality disorder criteria as well as the current proposals for DSM-5 personality disorders. (PsycINFO Database Record (c) 2012 APA, all rights reserved).

An analysis of teacher’s preparation in implementing 2013 revision edition curriculum on mathematics specialization learning

Science.gov (United States)

Susilo, T.; Suryawan, A.

2018-05-01

This study aimed to determine the pedagogical competence of teachers, the readiness of planning and implementation of learning related to the implementation 2013 revised edition curriculum on mathematics specialization learning for senior high schools Wonogiri. Informants in this study there are 6 high school mathematics teachers X and XI class who teach in the school district Wonogiri. Data were collected using questionnaire method, interview, observation and documentation. Qualitative data analysis is done interactively through 4 paths: data collection, data reduction, data display, drawing conclusion. The results showed that high school mathematics teacher class X and XI in school district of Wonogiri City. The results show that most high school mathematics teachers in grade X and XI are ready to implement the 2013 revised edition curriculum and a few have not been able to implement due to internal or external factors. High school math teachers at Wonogiri district who are ready to face the 2013 revised edition curriculum have applied 10 teacher pedagogic competency indicators according to Regulation of the national education ministry Number 16 Year 2007 in learning. The readiness and implementation of mathematics learning is in line with the demands of the 2013 revised edition curriculum. Based on the teachers who are not ready, data on issues that arise in the implementation of the 2013 revised edition curriculum. Especially the problems in learning, namely mismatch of Core Competence (KI) and Basic Competence (KD) in teacher manual, material disregard in student handbook and lack of examples of problems that exist in teacher manual.

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)

Safety system status monitoring

International Nuclear Information System (INIS)

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

1984-03-01

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

Safety system status monitoring

Energy Technology Data Exchange (ETDEWEB)

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

1984-03-01

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

User's manual for BINIAC: A computer code to translate APET bins

International Nuclear Information System (INIS)

Gough, S.T.

1994-03-01

This report serves as the user's manual for the FORTRAN code BINIAC. BINIAC is a utility code designed to format the output from the Defense Waste Processing Facility (DWPF) Accident Progression Event Tree (APET) methodology. BINIAC inputs the accident progression bins from the APET methodology, converts the frequency from occurrences per hour to occurrences per year, sorts the progression bins, and converts the individual dimension character codes into facility attributes. Without the use of BINIAC, this process would be done manually at great time expense. BINIAC was written under the quality assurance control of IQ34 QAP IV-1, revision 0, section 4.1.4. Configuration control is established through the use of a proprietor and a cognizant users list

Spent nuclear fuel project cold vacuum drying facility safety equipment list

International Nuclear Information System (INIS)

IRWIN, J.J.

1999-01-01

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

Application of condition-based HRA method for a manual actuation of the safety features in a nuclear power Plant

International Nuclear Information System (INIS)

Kang, Hyun Gook; Jang, Seung-Cheol

2006-01-01

A practical approach to develop a more realistic fault-tree model with a consideration of various conditions endured by a human operator is proposed. In safety-critical systems, the generation failure of an actuation signal is caused by the concurrent failures of the automated systems and an operator action. These two sources of safety signals are complicatedly correlated. The failures of sensors or automated systems will cause a lack of necessary information for a human operator and result in error-forcing contexts such as the loss of corresponding alarms and indications. It is well known that the error-forcing contexts largely affect the operator's performance. An automated system which consists of multiple processing channels and complex components is also affected by the availability of the sensors. This paper proposes a condition-based human reliability assessment (CBHRA) method in order to address these complicated conditions in a practical way. We apply the CBHRA method to the manual actuation of the safety features such as a reactor trip and auxiliary feedwater actuation in Korean Standard Nuclear Power Plants. Even the human error probability of each given condition is simply assumed, the application results prove that the CBHRA effectively accommodates the complicated error-forcing contexts into the fault trees

Culture and Context in Mental Health Diagnosing: Scrutinizing the DSM-5 Revision.

Science.gov (United States)

Bredström, Anna

2017-12-28

This article examines the revision of the Diagnostic and Statistical Manual of Mental Disorders (DSM-5) and its claim of incorporating a "greater cultural sensitivity." The analysis reveals that the manual conveys mixed messages as it explicitly addresses the critique of being ethnocentric and having a static notion of culture yet continues in a similar fashion when culture is applied in diagnostic criteria. The analysis also relates to current trends in psychiatric nosology that emphasize neurobiology and decontextualize distress and points to how the DSM-5 risks serving as an ethnic dividing line in psychiatry by making sociocultural context relevant only for some patients.

Radioactive Materials Packaging (RAMPAC) Radioactive Materials Incident Report (RMIR). RAMTEMP users manual

International Nuclear Information System (INIS)

Tyron-Hopko, A.K.; Driscoll, K.L.

1985-10-01

The purpose of this document is to familiarize the potential user with RadioActive Materials PACkaging (RAMPAC), Radioactive Materials Incident Report (RMIR), and RAMTEMP databases. RAMTEMP is a minor image of RAMPAC. This reference document will enable the user to access and obtain reports from databases while in an interactive mode. This manual will be revised as necessary to reflect enhancements made to the system

The environmental survey manual

International Nuclear Information System (INIS)

1987-08-01

The purpose of this manual is to provide guidance to the Survey and Sampling and Analysis teams that conduct the one-time Environmental Survey of the major US Department of Energy (DOE) operating facilities. This manual includes a discussion of DOE's policy on environmental issues, a review of statutory guidance as it applies to the Survey, the procedures and protocols to be used by the Survey teams, criteria for the use of the Survey teams in evaluating existing environmental data for the Survey effort, generic technical checklists used in every Survey, health and safety guidelines for the personnel conducting the Survey, including the identification of potential hazards, prescribed protective equipment, and emergency procedures, the required formats for the Survey reports, guidance on identifying environmental problems that need immediate attention by the Operations Office responsible for the particular facility, and procedures and protocols for the conduct of sampling and analysis

World of Work--Education and Jobs. Kit No. WW-705. Instructor's Manual. Revised.

Science.gov (United States)

Miles, Mamie Rose; Killingsworth, Linda

This instructor's manual contains activities for teaching students about the benefits derived from completing high school, sources of training for occupations, and information on finding job openings and on working part-time and full-time. It is designed for use in five periods in classes in prevocational education in South Carolina. The guide…

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)

General Mechanical Repair. Minor Automotive Maintenance, Small Engine [Repair, and] Welding: Student Manual.

Science.gov (United States)

Hamlin, Larry

This document is a student manual for a general mechanical repair course. Following a list of common essential elements of trade and industrial education, the manual is divided into three sections. The first section, on minor automotive maintenance, contains 13 units: automotive shop safety; engine principles; fuel system operation and repair;…

Applicator Training Manual for: Agricultural Animal Pest Control.

Science.gov (United States)

Christensen, Christian M.

This manual discusses pesticide safety and environmental considerations, pesticide toxicity, residue potential, pesticide formulations, and application techniques. In addition, descriptions of, and methods for controlling insects and related pests that attack cattle, sheep and goats, swine, horses and other equines, and poultry are given. These…

Light Water Reactor Generic Safety Issues Database (LWRGSIDB). User's manual

International Nuclear Information System (INIS)

1999-01-01

The IAEA Conference on 'The Safety of Nuclear Power: Strategy for the Future' in 1991 was a milestone in nuclear safety. The objective of this conference was to review nuclear power safety issues for which achieving international consensus would be desirable, to address concerns on nuclear safety and to formulate recommendations for future actions by national and international authorities to advance nuclear safety to the highest level. Two of the important items addressed by this conference were ensuring and enhancing safety of operating plants and treatment of nuclear power plants built to earlier safety standards. Some of the publications related to these two items that have been issued subsequent to this conference are: A Common Basis for Judging the Safety of Nuclear Power Plants Built to Earlier Standards, INSAG-8 (1995), the IAEA Safety Guide 50-SG-O12, Periodic Safety Review of Operational Nuclear Power Plants (1994) and IAEA Safety Reports Series No. 12, Evaluation of the Safety of Operating Nuclear Power Plants Built to Earlier Standards: A Common Basis for Judgement (1998). Some of the findings of the 1991 conference have not yet been fully addressed. An IAEA Symposium on Reviewing the Safety of Existing Nuclear Power Plants in 1996 showed that there is an urgent need for operating organizations and national authorities to review those operating nuclear power plants which do not reach the high safety levels of the vast majority of plants and to undertake improvements with assistance from the international community if required. Safety reviews of operating nuclear power plants take on added importance in the context of the Convention on Nuclear Safety and its implementation. In order to perform safety reviews and to reassess the safety of operating nuclear power plants in a uniform manner, it is imperative to have an internationally accepted reference. Existing guidance needs to be complemented by a list of safety issues which have been encountered and

Methodology for assessing the safety of Hydrogen Systems: HyRAM 1.1 technical reference manual

Energy Technology Data Exchange (ETDEWEB)

Groth, Katrina; Hecht, Ethan; Reynolds, John Thomas; Blaylock, Myra L.; Erin E. Carrier

2017-03-01

The HyRAM software toolkit provides a basis for conducting quantitative risk assessment and consequence modeling for hydrogen infrastructure and transportation systems. HyRAM is designed to facilitate the use of state-of-the-art science and engineering models to conduct robust, repeatable assessments of hydrogen safety, hazards, and risk. HyRAM is envisioned as a unifying platform combining validated, analytical models of hydrogen behavior, a stan- dardized, transparent QRA approach, and engineering models and generic data for hydrogen installations. HyRAM is being developed at Sandia National Laboratories for the U. S. De- partment of Energy to increase access to technical data about hydrogen safety and to enable the use of that data to support development and revision of national and international codes and standards. This document provides a description of the methodology and models contained in the HyRAM version 1.1. HyRAM 1.1 includes generic probabilities for hydrogen equipment fail- ures, probabilistic models for the impact of heat flux on humans and structures, and computa- tionally and experimentally validated analytical and first order models of hydrogen release and flame physics. HyRAM 1.1 integrates deterministic and probabilistic models for quantifying accident scenarios, predicting physical effects, and characterizing hydrogen hazards (thermal effects from jet fires, overpressure effects from deflagrations), and assessing impact on people and structures. HyRAM is a prototype software in active development and thus the models and data may change. This report will be updated at appropriate developmental intervals.

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

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.

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

Safety critical systems handbook a straightforward guide to functional safety : IEC 61508 (2010 edition) and related standards

CERN Document Server

Smith, David J

2010-01-01

Electrical, electronic and programmable electronic systems increasingly carry out safety functions to guard workers and the public against injury or death and the environment against pollution. The international functional safety standard IEC 61508 was revised in 2010, and this is the first comprehensive guide available to the revised standard. As functional safety is applicable to many industries, this book will have a wide readership beyond the chemical and process sector, including oil and gas, power generation, nuclear, aircraft, and automotive industries, plus project, instrumentation, design, and control engineers. * The only comprehensive guide to IEC 61508, updated to cover the 2010 amendments, that will ensure engineers are compliant with the latest process safety systems design and operation standards* Helps readers understand the process required to apply safety critical systems standards* Real-world approach helps users to interpret the standard, with case studies and best practice design examples...

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.

MORT User's Manual for use with the Management Oversight and Risk Tree analytical logic diagram. [Contains a list of System Safety Development Center publications

Energy Technology Data Exchange (ETDEWEB)

Knox, N.W.; Eicher, R.W.

1992-02-01

This report contains the User's Manual for MORT (Management Oversight and Risk Tree), a logic diagram in the form of a work sheet'' that illustrates a long series of interrelated questions. MORT is a comprehensive analytical procedure that provides a disciplined method for determining the causes and contributing factors of major accidents. Alternatively, it serves as a tool to evaluate the quality of an existing system. While similar in many respects to fault tree analysis, MORT is more generalized and presents over 1,500 specific elements of an ideal universal'' management program for optimizing environment, safety and health, and other programs. This User's Manual is intended to be used with the MORT diagram dated February 1992.

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.

HANSF 1.3.2 User's Manual

International Nuclear Information System (INIS)

DUNCAN, D.R.

1999-01-01

The HANSF analysis tool is an integrated model considering phenomena inside a multi-canister overpack (MCO) spent nuclear fuel container such as fuel oxidation, convective and radiative heat transfer, and the potential for fission product release. This manual reflects the HANSF version 1.3.2, a revised version of 1.3.1. HANSF 1.3.2 was written to correct minor errors and to allow modeling of condensate flow on the MCO inner surface. HANSF 1.3.2 is intended for use on personal computers such as IBM-compatible machines with Intel processors running under Lahey TI or digital Visual FORTRAN, Version 6.0, but this does not preclude operation in other environments

Safety of Nuclear Power Plants: Design. Specific Safety Requirements (Spanish Edition)

International Nuclear Information System (INIS)

2012-01-01

This publication is a revision of Safety Requirements No. NS-R-1, Safety of Nuclear Power Plants: Design. It establishes requirements applicable to the design of nuclear power plants and elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. It will be useful for organizations involved in the design, manufacture, construction, modification, maintenance, operation and decommissioning of nuclear power plants, as well as for regulatory bodies. Contents: 1. Introduction; 2. Applying the safety principles and concepts; 3. Management of safety in design; 4. Principal technical requirements; 5. General plant design; 6. Design of specific plant systems.

Safety of Nuclear Power Plants: Design. Specific Safety Requirements (Russian Edition)

International Nuclear Information System (INIS)

2012-01-01

This publication is a revision of Safety Requirements No. NS-R-1, Safety of Nuclear Power Plants: Design. It establishes requirements applicable to the design of nuclear power plants and elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear power plant. It will be useful for organizations involved in the design, manufacture, construction, modification, maintenance, operation and decommissioning of nuclear power plants, as well as for regulatory bodies. Contents: 1. Introduction; 2. Applying the safety principles and concepts; 3. Management of safety in design; 4. Principal technical requirements; 5. General plant design; 6. Design of specific plant systems.

Contribution from Belgium - Belgian contribution to the PWG1 Generic Study on Undetected Failures of Safety systems

International Nuclear Information System (INIS)

Vincke, Marc

1997-01-01

In the frame of its participation to the PWG 1 generic study on 'Undetected Failures of Safety Systems', AVN performed a search of such cases among the Belgian plants, using the proposed criterion: to find significant events where equipment remained inoperable, or would have been unable to fulfil correctly its safety function for an extended period of time until their condition was discovered. An extended period of time means one cycle duration or several test interval periods at least; if unknown, it has to be estimated w.r.t. plant lifetime. Note that non safety systems preventing safety systems to perform their function are to be included. As a first information source, a screening of AVN's DIANE (Domestic Information about Nuclear Events) database, for undetected failures of safety systems was performed. This database is used to store and retrieve information on a selection of events which have occurred in the Belgian NPPs since 1985. The sources of information are the incident reports which AVN receives from the utilities, completed with the reports of our inspectors on site. The coding system used within this database is based on the IRS Coding Manual. This coding system does not always allow for an easy retrieval of events related to a specific subject. In addition the DIANE-coding system does not allow for direct retrieval of undetected failures. In a first step, the following systems were scanned: reactor coolant system, reactor heat removal system, emergency core cooling system, chemical and volume control, containment spray, main and auxiliary feedwater, component cooling water, control rod drives. For each system, records were selected by examining their title. Careful reading of the 64 reports selected this way finally led to two cases compatible with the criteria. The decennial revision studies formed a second set of information sources. An inquiry to AVN's engineers responsible for the decennial revision projects allowed to

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

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)

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

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

Manual for JSSL (JAERI scientific subroutine library)

International Nuclear Information System (INIS)

Inoue, Shuji; Fujimura, Toichiro; Tsutsui, Tsuneo; Nishida, Takahiko

1982-09-01

A manual on revised version of JAERI scientific subroutine library, which is a collection of scientific subroutines developed or modified in JAERI. They are classified into fifteen fields (Special Functions, Linear Problems, Eigenvalue and Eigen vector Problems, Non linear Problems, Mathematical Programming, Extreme Value Problems, Transformations, Functional Approximation Methods, Numerical Differential and Integral Methods, Numerical Differential and Integral Equations, Statistical Functions, Physical Problems, I/O Routines, Plotter Routines, Computer System Functions and Others). Main expansion of this version is in the fields of mathematical programming and statistical functions. The present library may be said to be a comprehensive compilation of scientific subroutines covering almost all the important fields. (author)

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...

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

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.

Aquifer thermal energy storage reference manual: seasonal thermal energy storage program

Energy Technology Data Exchange (ETDEWEB)

Prater, L.S.

1980-01-01

This is the reference manual of the Seasonal Thermal Energy Storage (STES) Program, and is the primary document for the transfer of technical information of the STES Program. It has been issued in preliminary form and will be updated periodically to include more technical data and results of research. As the program progresses and new technical data become available, sections of the manual will be revised to incorporate these data. This primary document contains summaries of: the TRW, incorporated demonstration project at Behtel, Alaska, Dames and Moore demonstration project at Stony Brook, New York, and the University of Minnesota demonstration project at Minneapolis-St. Paul, Minnesota; the technical support programs including legal/institutional assessment; economic assessment; environmental assessment; field test facilities; a compendia of existing information; numerical simulation; and non-aquifer STES concepts. (LCL)

Time Based Workload Analysis Method for Safety-Related Operator Actions in Safety Analysis

Energy Technology Data Exchange (ETDEWEB)

Kim, Yun Goo; Oh, Eung Se [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

2016-05-15

During the design basis event, the safety system performs safety functions to mitigate the event. The most of safety system is actuated by automatic system however, there are operator manual actions that are needed for the plant safety. These operator actions are classified as important human actions in human factors engineering design. The human factors engineering analysis and evaluation is needed for these important human actions to assure that operator successfully perform their tasks for plant safety and operational goals. The work load analysis is one of the required analysis for the important human actions.

Time Based Workload Analysis Method for Safety-Related Operator Actions in Safety Analysis

International Nuclear Information System (INIS)

Kim, Yun Goo; Oh, Eung Se

2016-01-01

During the design basis event, the safety system performs safety functions to mitigate the event. The most of safety system is actuated by automatic system however, there are operator manual actions that are needed for the plant safety. These operator actions are classified as important human actions in human factors engineering design. The human factors engineering analysis and evaluation is needed for these important human actions to assure that operator successfully perform their tasks for plant safety and operational goals. The work load analysis is one of the required analysis for the important human actions.

Safety of Nuclear Power Plants: Commissioning and Operation

International Nuclear Information System (INIS)

2011-01-01

This publication is a revision of Safety Requirements 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 operation of nuclear power plants. Over recent years there have been developments in areas such as long term operation, plant ageing, periodic safety review, probabilistic safety analysis 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 Fundamental Safety Principles. Contents: 1. Introduction; 2. Safety objectives and principles; 3. The management and organizational structure of the operating organization; 4. Management of operational safety; 5. Operational safety programmes; 6. Plant commissioning; 7. Plant operations; 8. Maintenance, testing, surveillance and inspection; 9. Preparation for decommissioning.

Manual on theory and practical aspects of bioassay

International Nuclear Information System (INIS)

Nuraini Hambali.

1985-06-01

This manual is set to provide necessary basic guidance on theory and practical aspects of bioassay specially for the newcomer in this field and the man in the laboratory. The first part is a brief information on the entry of radionuclides into the body, the metabolism and the programs of bioassay. All other factors to be considered in assessing internal contamination in man have also been brought up. In the second part, various procedures of radiochemical separations, detection and measurements are abstracted from journals and other revisions. Some methods have been attempted and to be followed where appropriate. (author)

INES: The International Nuclear Event Scale user's manual

International Nuclear Information System (INIS)

1992-09-01

The revised and extended addition of the International Nuclear Event Scale is presented. The manual is comprised of four parts. Part 1 contains a summary of the basis of the scale and of the procedure to be used for rating events. Part 2 contains the detailed guidance required to rate events in terms of off-site and on-site impact. These two parts are applicable to all nuclear facilities. Parts 3 and 4 contain the detailed guidance required to rate events in terms of defence in depth for reactors and other facilities, respectively. 5 figs, 2 tabs

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

Procedures manual for the Oak Ridge Electron Linear Accelerator

International Nuclear Information System (INIS)

Todd, H.A.

1979-01-01

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

Manual on quality assurance programme auditing

International Nuclear Information System (INIS)

1984-01-01

The objective of this Manual is to provide guidance and illustrative examples of the methodology and techniques of internal and external audits that are consistent with the requirements and recommendations of the Code and the Safety Guide. The methodology and techniques are based on the practices of Member States having considerable experience in auditing QA programmes. This Manual is directed primarily towards QA programme auditors and managers and presents methods and techniques considered appropriate for the preparation and performance of audits and the evaluation of results. Its scope includes the techniques and methods used to carry out QA programme audits variously described as 'System', 'Product' and 'Process' audits. The techniques and methods described here may be used as one approach to the evaluation of suppliers' QA capabilities as defined in 50-SG-QA10. Although the Manual is primarily directed towards purchasers and suppliers, it is also relevant to regulatory organizations, such as government offices responsible for quality assurance, which carry out external audits independent of purchasers and suppliers. In such cases similar methods, procedures and techniques may be used

Safety management systems and their role in achieving high standards of operational safety

International Nuclear Information System (INIS)

Coulston, D.J.; Baylis, C.C.

2000-01-01

Achieving high standards of operational safety requires a robust management framework that is visible to all personnel with responsibility for its implementation. The structure of the management framework must ensure that all processes used to manage safety interlink in a logical and coherent manner, that is, they form a management system that leads to continuous improvement in safety performance. This Paper describes BNFL's safety management system (SMS). The SMS has management processes grouped within 5 main elements: 1. Policy, 2. Organisation, 3. Planning and Implementation, 4. Measuring and Reviewing Performance, 5. Audit. These elements reflect the overall process of setting safety objective (from Policy), measuring success and reviewing the performance. Effective implementation of the SMS requires senior managers to demonstrate leadership through their commitment and accountability. However, the SMS as a whole reflects that every employee at every level within BNFL is responsible for safety of operations under their control. The SMS therefore promotes a proactive safety culture and safe operations. The system is formally documented in the Company's Environmental, Health and Safety (EHS) Manual. Within in BNFL Group, the Company structures enables the Manual to provide overall SMS guidance and co-ordination to its range of nuclear businesses. Each business develops the SMS to be appropriate at all levels of its organisation, but ensuring that each level is consistent with the higher level. The Paper concludes with a summary of BNFL's safety performance. (author)

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

Functional safety measurement in the automotive domain : adaptation of PSM

NARCIS (Netherlands)

Luo, Y.; Stelma, J.; Brand, van den M.G.J.

2015-01-01

In the safety domain, safety standards are used as a development guideline to keep the risk at an acceptable level. Safety of the safety-critical systems can be assessed according to those safety standards. This assessment process is called safety assurance. Due to the manual work, the safety

SRL process hazards review manual

International Nuclear Information System (INIS)

1980-08-01

The principal objective of the Process Hazards Management Program is to provide a regular, systematic review of each process at the Savannah River Laboratory (SRL) to eliminate injuries and to minimize property damage resulting from process hazards of catastrophic potential. Management effort is directed, through the Du Pont Safety Program, toward those controls and practices that ensure this objective. The Process Hazards Management Program provides an additional dimension to further ensure the health and safety of employees and the public. Du Pont has concluded that an organized approach is essential to obtain an effective and efficient process hazards review. The intent of this manual is to provide guidance in creating such an organized approach to performing process hazards reviews on a continuing basis

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

Federal Transit Administration's noise and vibration Guidance Manual: Updates after 10 years of experience

Science.gov (United States)

Hanson, Carl E.

2005-09-01

In April 1995, the Federal Transit Administration of the U.S. Department of Transportation issued its guidance manual, ``Transit Noise and Vibration Impact Assessment.'' The manual was written to provide direction for the preparation of noise and vibration sections of environmental documents for public transportation projects in the interest of promoting quality and uniformity in assessments. In the 10 years since its release, the guidance manual has been used as the basis of noise and vibration assessments in over 80 environmental documents and has been used worldwide as a standard method for performing transit noise analyses. An updated version has recently been prepared that takes account of improvements in tools, changes in the environmental assessment procedures, modifications of impact criteria, and experience with mitigation measures. These factors, and other background information, will be discussed to provide insight regarding the revisions in the new edition.

PETSc Users Manual Revision 3.3

Energy Technology Data Exchange (ETDEWEB)

Balay, S. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Brown, J. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Buschelman, K. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Eijkhout, V. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Gropp, W. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Kaushik, D. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Knepley, M. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; McInnes, L. Curfman [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Smith, B. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Zhang, H. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division

2013-05-11

This manual describes the use of PETSc for the numerical solution of partial differential equations and related problems on high-performance computers. The Portable, Extensible Toolkit for Scientific Computation (PETSc) is a suite of data structures and routines that provide the building blocks for the implementation of large-scale application codes on parallel (and serial) computers. PETSc uses the MPI standard for all message-passing communication. PETSc includes an expanding suite of parallel linear, nonlinear equation solvers and time integrators that may be used in application codes written in Fortran, C, C++, Python, and MATLAB (sequential). PETSc provides many of the mechanisms needed within parallel application codes, such as parallel matrix and vector assembly routines. The library is organized hierarchically, enabling users to employ the level of abstraction that is most appropriate for a particular problem. By using techniques of object-oriented programming, PETSc provides enormous flexibility for users. PETSc is a sophisticated set of software tools; as such, for some users it initially has a much steeper learning curve than a simple subroutine library. In particular, for individuals without some computer science background, experience programming in C, C++ or Fortran and experience using a debugger such as gdb or dbx, it may require a significant amount of time to take full advantage of the features that enable efficient software use. However, the power of the PETSc design and the algorithms it incorporates may make the efficient implementation of many application codes simpler than “rolling them” yourself; For many tasks a package such as MATLAB is often the best tool; PETSc is not intended for the classes of problems for which effective MATLAB code can be written. PETSc also has a MATLAB interface, so portions of your code can be written in MATLAB to “try out” the PETSc solvers. The resulting code will not be scalable however because

PETSc Users Manual Revision 3.5

Energy Technology Data Exchange (ETDEWEB)

Balay, S. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Abhyankar, S. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Adams, M. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Brown, J. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Brune, P. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Buschelman, K. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Eijkhout, V. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Gropp, W. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Kaushik, D. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Knepley, M. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; McInnes, L. Curfman [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Rupp, K. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Smith, B. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Zhang, H. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division

2014-09-08

This manual describes the use of PETSc for the numerical solution of partial differential equations and related problems on high-performance computers. The Portable, Extensible Toolkit for Scientific Computation (PETSc) is a suite of data structures and routines that provide the building blocks for the implementation of large-scale application codes on parallel (and serial) computers. PETSc uses the MPI standard for all message-passing communication. PETSc includes an expanding suite of parallel linear, nonlinear equation solvers and time integrators that may be used in application codes written in Fortran, C, C++, Python, and MATLAB (sequential). PETSc provides many of the mechanisms needed within parallel application codes, such as parallel matrix and vector assembly routines. The library is organized hierarchically, enabling users to employ the level of abstraction that is most appropriate for a particular problem. By using techniques of object-oriented programming, PETSc provides enormous flexibility for users. PETSc is a sophisticated set of software tools; as such, for some users it initially has a much steeper learning curve than a simple subroutine library. In particular, for individuals without some computer science background, experience programming in C, C++ or Fortran and experience using a debugger such as gdb or dbx, it may require a significant amount of time to take full advantage of the features that enable efficient software use. However, the power of the PETSc design and the algorithms it incorporates may make the efficient implementation of many application codes simpler than “rolling them” yourself. ;For many tasks a package such as MATLAB is often the best tool; PETSc is not intended for the classes of problems for which effective MATLAB code can be written. PETSc also has a MATLAB interface, so portions of your code can be written in MATLAB to “try out” the PETSc solvers. The resulting code will not be scalable however because

PETSc Users Manual Revision 3.4

Energy Technology Data Exchange (ETDEWEB)

Balay, S. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Brown, J. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Buschelman, K. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Eijkhout, V. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Gropp, W. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Kaushik, D. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Knepley, M. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; McInnes, L. Curfman [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Smith, B. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division; Zhang, H. [Argonne National Lab. (ANL), Argonne, IL (United States). Mathematics and Computer Science Division

2014-06-29

This manual describes the use of PETSc for the numerical solution of partial differential equations and related problems on high-performance computers. The Portable, Extensible Toolkit for Scientific Computation (PETSc) is a suite of data structures and routines that provide the building blocks for the implementation of large-scale application codes on parallel (and serial) computers. PETSc uses the MPI standard for all message-passing communication. PETSc includes an expanding suite of parallel linear, nonlinear equation solvers and time integrators that may be used in application codes written in Fortran, C, C++, Python, and MATLAB (sequential). PETSc provides many of the mechanisms needed within parallel application codes, such as parallel matrix and vector assembly routines. The library is organized hierarchically, enabling users to employ the level of abstraction that is most appropriate for a particular problem. By using techniques of object-oriented programming, PETSc provides enormous flexibility for users. PETSc is a sophisticated set of software tools; as such, for some users it initially has a much steeper learning curve than a simple subroutine library. In particular, for individuals without some computer science background, experience programming in C, C++ or Fortran and experience using a debugger such as gdb or dbx, it may require a significant amount of time to take full advantage of the features that enable efficient software use. However, the power of the PETSc design and the algorithms it incorporates may make the efficient implementation of many application codes simpler than “rolling them” yourself; For many tasks a package such as MATLAB is often the best tool; PETSc is not intended for the classes of problems for which effective MATLAB code can be written. PETSc also has a MATLAB interface, so portions of your code can be written in MATLAB to “try out” the PETSc solvers. The resulting code will not be scalable however because

SCALE: A modular code system for performing standardized computer analyses for licensing evaluation. Miscellaneous -- Volume 3, Revision 4

Energy Technology Data Exchange (ETDEWEB)

Petrie, L.M.; Jordon, W.C. [Oak Ridge National Lab., TN (United States); Edwards, A.L. [Oak Ridge National Lab., TN (United States)]|[Lawrence Livermore National Lab., CA (United States)] [and others

1995-04-01

SCALE--a modular code system for Standardized Computer Analyses Licensing Evaluation--has been developed by Oak Ridge National Laboratory at the request of the US Nuclear Regulatory Commission. The SCALE system utilizes well-established computer codes and methods within standard analysis sequences that (1) allow an input format designed for the occasional user and/or novice; (2) automate the data processing and coupling between modules, and (3) provide accurate and reliable results. System developments has been directed at problem-dependent cross-section processing and analysis of criticality safety, shielding, heat transfer, and depletion/decay problems. Since the initial release of SCALE in 1980, the code system has been heavily used for evaluation of nuclear fuel facility and package designs. This revision documents Version 4.2 of the system. This manual is divided into three volumes: Volume 1--for the control module documentation, Volume 2--for the functional module documentation, and Volume 3--for the data libraries and subroutine libraries.

SCALE: A modular code system for performing standardized computer analyses for licensing evaluation. Miscellaneous -- Volume 3, Revision 4

International Nuclear Information System (INIS)

Petrie, L.M.; Jordon, W.C.; Edwards, A.L.

1995-04-01

SCALE--a modular code system for Standardized Computer Analyses Licensing Evaluation--has been developed by Oak Ridge National Laboratory at the request of the US Nuclear Regulatory Commission. The SCALE system utilizes well-established computer codes and methods within standard analysis sequences that (1) allow an input format designed for the occasional user and/or novice; (2) automate the data processing and coupling between modules, and (3) provide accurate and reliable results. System developments has been directed at problem-dependent cross-section processing and analysis of criticality safety, shielding, heat transfer, and depletion/decay problems. Since the initial release of SCALE in 1980, the code system has been heavily used for evaluation of nuclear fuel facility and package designs. This revision documents Version 4.2 of the system. This manual is divided into three volumes: Volume 1--for the control module documentation, Volume 2--for the functional module documentation, and Volume 3--for the data libraries and subroutine libraries

Accelerator safety program at the Lawrence Livermore Laboratory

International Nuclear Information System (INIS)

Graham, C.L.

1976-01-01

A proposed accelerator safety standard for the Lawrence Livermore Laboratory (LLL) is given. All accelerators will comply with this standard when it is included in the LLL Health and Safety Manual. The radiation alarm and radiation safety system for a radiography facility are also described

Manual on public health action in radiation emergencies

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-31

Over the years, the World Health Organization (WHO) has issued a series of reports and publications providing guidance on the public health aspects of nuclear power production, in line with target 11 of the European policy for health for all, which calls for the reduction of injury, disability and death from accidents. Immediately after the nuclear accident at Chernobyl in April 1986, the WHO Regional Office for Europe established an emergency operation to provide technical cooperation and communication links with Member States. A special project on the public health dimensions of radiation emergencies was subsequently established, which included a series of activities related both directly to the Chernobyl accident and to emergency planning for future accidents. This manual brings together the experience gained in the special project to improve the planning for and response to emergencies. It has been prepared to meet public health needs arising from all types of major radiation emergency in the European Region. The manual describes the guiding principles and advises on the practical application of measures to protect and inform the public in a radiation emergency. It is hoped that the manual will promote close interaction between the WHO Member States in this field. The advice given in earlier WHO publications on radiation emergencies has been examined and revised in the light of recent experience 12 refs, 4 figs, 4 tabs

Manual on public health action in radiation emergencies

International Nuclear Information System (INIS)

1994-01-01

Over the years, the World Health Organization (WHO) has issued a series of reports and publications providing guidance on the public health aspects of nuclear power production, in line with target 11 of the European policy for health for all, which calls for the reduction of injury, disability and death from accidents. Immediately after the nuclear accident at Chernobyl in April 1986, the WHO Regional Office for Europe established an emergency operation to provide technical cooperation and communication links with Member States. A special project on the public health dimensions of radiation emergencies was subsequently established, which included a series of activities related both directly to the Chernobyl accident and to emergency planning for future accidents. This manual brings together the experience gained in the special project to improve the planning for and response to emergencies. It has been prepared to meet public health needs arising from all types of major radiation emergency in the European Region. The manual describes the guiding principles and advises on the practical application of measures to protect and inform the public in a radiation emergency. It is hoped that the manual will promote close interaction between the WHO Member States in this field. The advice given in earlier WHO publications on radiation emergencies has been examined and revised in the light of recent experience

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.

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

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)

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...

Development of the advanced PHWR technology -Design and analysis of CANDU advanced fuel-

Energy Technology Data Exchange (ETDEWEB)

Suk, Hoh Chun; Shim, Kee Sub; Byun, Taek Sang; Park, Kwang Suk; Kang, Heui Yung; Kim, Bong Kee; Jung, Chang Joon; Lee, Yung Wook; Bae, Chang Joon; Kwon, Oh Sun; Oh, Duk Joo; Im, Hong Sik; Ohn, Myung Ryong; Lee, Kang Moon; Park, Joo Hwan; Lee, Eui Joon [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1995-07-01

This is the `94 annual report of the CANDU advanced fuel design and analysis project, and describes CANFLEX fuel design and mechanical integrity analysis, reactor physics analysis and safety analysis of the CANDU-6 with the CANFLEX-NU. The following is the R and D scope of this fiscal year : (1) Detail design of CANFLEX-NU and detail analysis on the fuel integrity, reactor physics and safety. (a) Detail design and mechanical integrity analysis of the bundle (b) CANDU-6 refueling simulation, and analysis on the Xe transients and adjuster system capability (c) Licensing strategy establishment and safety analysis for the CANFLEX-NU demonstration demonstration irradiation in a commercial CANDU-6. (2) Production and revision of CANFLEX-NU fuel design documents (a) Production and approval of CANFLEX-NU reference drawing, and revisions of fuel design manual and technical specifications (b) Production of draft physics design manual. (3) Basic research on CANFLEX-SEU fuel. 55 figs, 21 tabs, 45 refs. (Author).

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)

Operating Manual of Helium Refrigerator (Rev. 2)

Energy Technology Data Exchange (ETDEWEB)

Song, K.M.; Son, S.H.; Kim, K.S.; Lee, S.K.; Kim, M.S. [Korea Electric Power Research Institute, Taejon (Korea)

2002-07-01

A helium refrigerator was installed as a supplier of 20K cold helium to the cryogenic distillation system of WTRF pilot plant. The operating procedures of the helium refrigerator, helium compressor and auxiliary apparatus are described for the safety and efficient operation in this manual. The function of the helium refrigerator is to remove the impurities from the compressed helium of about 250psig, to cool down the helium from ambient temperature to 20K through the heat exchanger and expansion engine and to transfer the cold helium to the cryogenic distillation system. For the smoothly operation of helium refrigerator, the preparation, the start-up, the cool-down and the shut-down of the helium refrigerator are described in this operating manual. (author). 3 refs., 14 tabs.

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

Manual therapy in the treatment of patients with hemophilia B and inhibitor.

Science.gov (United States)

Cuesta-Barriuso, Rubén; Trelles-Martínez, Roberto O

2018-01-22

The main clinical manifestations of hemophilia are muscle and joint bleeding. Recurrent bleeding leads to a degenerative process known as hemophilic arthropathy. The development of inhibitors (antibodies against FVIII/FIX concentrates) is the main complication in the treatment of hemophilia. The objective was to assess the safety and efficacy of manual therapy treatment in a patient with hemophilia and inhibitor. A 26-year-old patient with hemophilia B and inhibitor received physiotherapy treatment based on manual therapy for 3 months, with a frequency of 2 sessions per week. The joint status was evaluated using the Hemophilia Joint Health Score; pain was assessed with the Visual Analog Scale; and the range of movement was evaluated using a universal goniometer. The patient developed no joint bleeding in the knees or ankles as a result of the physiotherapy treatment. Following treatment, improvements were noted in the range of movement of knees and ankles, the perception of pain in both knees, and ankle functionality. Until now, manual therapy using joint traction was contraindicated in patients with hemophilia and inhibitor, as it was feared to cause possible joint bleeding. This is the first case study to address the safety and efficacy of manual therapy in a patient with hemophilia and an inhibitor. The results of this study may help to establish which manual therapy treatments are indicated in patients with hemophilic arthropathy and inhibitors. Thus, a physiotherapy program based on manual therapy may be safe in patients with hemophilia and inhibitor and such therapy may improve joint condition, pain, and joint range of motion in patients with hemophilia and inhibitor. Randomized clinical trials are needed to confirm the results of this case study.

SCALE: A modular code system for performing standardized computer analyses for licensing evaluation. Control modules -- Volume 1, Revision 4

Energy Technology Data Exchange (ETDEWEB)

Landers, N.F.; Petrie, L.M.; Knight, J.R. [Oak Ridge National Lab., TN (United States)] [and others

1995-04-01

SCALE--a modular code system for Standardized Computer Analyses Licensing Evaluation--has been developed by Oak Ridge National Laboratory at the request of the US Nuclear Regulatory Commission. The SCALE system utilizes well-established computer codes and methods within standard analysis sequences that (1) allow an input format designed for the occasional user and/or novice, (2) automate the data processing and coupling between modules, and (3) provide accurate and reliable results. System development has been directed at problem-dependent cross-section processing and analysis of criticality safety, shielding, heat transfer, and depletion/decay problems. Since the initial release of SCALE in 1980, the code system has been heavily used for evaluation of nuclear fuel facility and package designs. This revision documents Version 4.2 of the system. This manual is divided into three volumes: Volume 1--for the control module documentation, Volume 2--for the functional module documentation, and Volume 3 for the documentation of the data libraries and subroutine libraries.

SCALE: A modular code system for performing standardized computer analyses for licensing evaluation. Control modules -- Volume 1, Revision 4

International Nuclear Information System (INIS)

Landers, N.F.; Petrie, L.M.; Knight, J.R.

1995-04-01

SCALE--a modular code system for Standardized Computer Analyses Licensing Evaluation--has been developed by Oak Ridge National Laboratory at the request of the US Nuclear Regulatory Commission. The SCALE system utilizes well-established computer codes and methods within standard analysis sequences that (1) allow an input format designed for the occasional user and/or novice, (2) automate the data processing and coupling between modules, and (3) provide accurate and reliable results. System development has been directed at problem-dependent cross-section processing and analysis of criticality safety, shielding, heat transfer, and depletion/decay problems. Since the initial release of SCALE in 1980, the code system has been heavily used for evaluation of nuclear fuel facility and package designs. This revision documents Version 4.2 of the system. This manual is divided into three volumes: Volume 1--for the control module documentation, Volume 2--for the functional module documentation, and Volume 3 for the documentation of the data libraries and subroutine libraries

HANSF 1.3 user's manual

International Nuclear Information System (INIS)

PLYS, M.G.

1999-01-01

The HANSF analysis tool is an integrated model considering phenomena inside a multi-canister overpack (MCO) spent nuclear fuel container such as fuel oxidation, convective and radiative heat transfer, and the potential for fission product release. It may be used for all phases of spent fuel disposition including cold vacuum drying, transportation, and storage. This manual reflects HANSF version 1.3, a revised version of version 1.2a. HANSF 1.3 was written to add new models for axial nodalization, add new features for ease of usage, and correct errors. HANSF 1.3 is intended for use on personal computers such as IBM-compatible machines with Intel processors running under a DOS-type operating system. HANSF 1.3 is known to compile under Lahey TI and Digital Visual FORTRAN, Version 6.0, but this does not preclude operation in other environments

Health physics manual of good practices for accelerator facilities

International Nuclear Information System (INIS)

Casey, W.R.; Miller, A.J.; McCaslin, J.B.; Coulson, L.V.

1988-04-01

It is hoped that this manual will serve both as a teaching aid as well as a useful adjunct for program development. In the context of application, this manual addresses good practices that should be observed by management, staff, and designers since the achievement of a good radiation program indeed involves a combined effort. Ultimately, radiation safety and good work practices become the personal responsibility of the individual. The practices presented in this manual are not to be construed as mandatory rather they are to be used as appropriate for the specific case in the interest of radiation safety. As experience is accrued and new data obtained in the application of this document, ONS will update the guidance to assure that at any given time the guidance reflects optimum performance consistent with current technology and practice.The intent of this guide therefore is to: define common health physics problems at accelerators; recommend suitable methods of identifying, evaluating, and managing accelerator health physics problems; set out the established safety practices at DOE accelerators that have been arrived at by consensus and, where consensus has not yet been reached, give examples of safe practices; introduce the technical literature in the accelerator health physics field; and supplement the regulatory documents listed in Appendix D. Many accelerator health physics problems are no different than those at other kinds of facilities, e.g., ALARA philosophy, instrument calibration, etc. These problems are touched on very lightly or not at all. Similarly, this document does not cover other hazards such as electrical shock, toxic materials, etc. This does not in any way imply that these problems are not serious. 160 refs

Safety Precautions. Child Health and Safety Series (Module I).

Science.gov (United States)

Iscoe, Louise; And Others

This manual for parents and child care personnel in day care homes and centers provides guidelines and information on indoor and outdoor safety precautions, emergency preparation and first aid. Contents focus on monitoring arrivals and departures, prevention of suffocation and strangulation, control of pets and other animals, preventing and…

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

Safety syringes and anti-needlestick devices in orthopaedic surgery.

Science.gov (United States)

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

2011-09-07

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

Criticality Safety Basics for INL Emergency Responders

Energy Technology Data Exchange (ETDEWEB)

Valerie L. Putman

2012-08-01

This document is a modular self-study guide about criticality safety principles for Idaho National Laboratory emergency responders. This guide provides basic criticality safety information for people who, in response to an emergency, might enter an area that contains much fissionable (or fissile) material. The information should help responders understand unique factors that might be important in responding to a criticality accident or in preventing a criticality accident while responding to a different emergency.

This study guide specifically supplements web-based training for firefighters (0INL1226) and includes information for other Idaho National Laboratory first responders. However, the guide audience also includes other first responders such as radiological control personnel.

For interested readers, this guide includes clearly marked additional information that will not be included on tests. The additional information includes historical examples (Been there. Done that.), as well as facts and more in-depth information (Did you know …).

INL criticality safety personnel revise this guide as needed to reflect program changes, user requests, and better information. Revision 0, issued May 2007, established the basic text. Revision 1 incorporates operation, program, and training changes implemented since 2007. Revision 1 increases focus on first responders because later responders are more likely to have more assistance and guidance from facility personnel and subject matter experts. Revision 1 also completely reorganized the training to better emphasize physical concepts behind the criticality controls that help keep emergency responders safe. The changes are based on and consistent with changes made to course 0INL1226.

Program Management System manual

International Nuclear Information System (INIS)

1986-01-01

The Program Management System (PMS), as detailed in this manual, consists of all the plans, policies, procedure, systems, and processes that, taken together, serve as a mechanism for managing the various subprograms and program elements in a cohesive, cost-effective manner. The PMS is consistent with the requirements of the Nuclear Waste Policy Act of 1982 and the ''Mission Plan for the Civilian Radioactive Waste Management Program'' (DOE/RW-0005). It is based on, but goes beyond, the Department of Energy (DOE) management policies and procedures applicable to all DOE programs by adapting these directives to the specific needs of the Civilian Radioactive Waste Management program. This PMS Manual describes the hierarchy of plans required to develop and maintain the cost, schedule, and technical baselines at the various organizational levels of the Civilian Radioactive Waste Management Program. It also establishes the management policies and procedures used in the implementation of the Program. These include requirements for internal reports, data, and other information; systems engineering management; regulatory compliance; safety; quality assurance; and institutional affairs. Although expanded versions of many of these plans, policies, and procedures are found in separate documents, they are an integral part of this manual. The PMS provides the basis for the effective management that is needed to ensure that the Civilian Radioactive Waste Management Program fulfills the mandate of the Nuclear Waste Policy Act of 1982. 5 figs., 2 tabs

A warm welcome to the diagnostic and statistical manual of mental disorders, fifth edition?

Science.gov (United States)

Razzaghi, Emran Mohammad

2014-01-01

The present article discusses the reaction of psychiatric professionals and specifically the academia in Iran to the publication of the Diagnostic and Statistical Manual of Mental Disorders, Fifth Edition, (DSM-5). It is argued that the reaction to changes and the approach of the new revision of DSM has been neither technical, nor emotional. This argument has further been examined for the previous revisions of the DSM and the conclusion is that the Iranian psychiatry has become alienated from the need and necessity of classification of mental disorders from a local and national point of view. The reason for this alienation has further been discussed and has been focused on the lack of contact between the psychiatric catchment areas and the academia. None.

Safety of Nuclear Power Plants: Commissioning and Operation (Spanish Edition)

International Nuclear Information System (INIS)

2012-01-01

This publication is a revision of Safety Requirements 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 operation of nuclear power plants. Over recent years there have been developments in areas such as long term operation, plant ageing, periodic safety review, probabilistic safety analysis 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 Fundamental Safety Principles. Contents: 1. Introduction; 2. Safety objectives and principles; 3. The management and organizational structure of the operating organization; 4. Management of operational safety; 5. Operational safety programmes; 6. Plant commissioning; 7. Plant operations; 8. Maintenance, testing, surveillance and inspection; 9. Preparation for decommissioning.

Safety of Nuclear Power Plants: Commissioning and Operation (French Edition)

International Nuclear Information System (INIS)

2012-01-01

This publication is a revision of Safety Requirements 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 operation of nuclear power plants. Over recent years there have been developments in areas such as long term operation, plant ageing, periodic safety review, probabilistic safety analysis 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 Fundamental Safety Principles. Contents: 1. Introduction; 2. Safety objectives and principles; 3. The management and organizational structure of the operating organization; 4. Management of operational safety; 5. Operational safety programmes; 6. Plant commissioning; 7. Plant operations; 8. Maintenance, testing, surveillance and inspection; 9. Preparation for decommissioning.

Safety of Nuclear Power Plants: Commissioning and Operation. Arabic Edition

International Nuclear Information System (INIS)

2011-01-01

This publication is a revision of Safety Requirements 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 operation of nuclear power plants. Over recent years there have been developments in areas such as long term operation, plant ageing, periodic safety review, probabilistic safety analysis 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 Fundamental Safety Principles. Contents: 1. Introduction; 2. Safety objectives and principles; 3. The management and organizational structure of the operating organization; 4. Management of operational safety; 5. Operational safety programmes; 6. Plant commissioning; 7. Plant operations; 8. Maintenance, testing, surveillance and inspection; 9. Preparation for decommissioning.

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

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

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.

Safety Management System in Croatia Control Ltd.

OpenAIRE

Pavlin, Stanislav; Sorić, Vedran; Bilać, Dragan; Dimnik, Igor; Galić, Daniel

2009-01-01

International Civil Aviation Organization and other international aviation organizations regulate the safety in civil aviation. In the recent years the International Civil Aviation Organization has introduced the concept of the safety management system through several documents among which the most important is the 2006 Safety Management Manual. It treats the safety management system in all the segments of civil aviation, from carriers, aerodromes and air traffic control to design, constructi...

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

Nuclear Criticality Safety Handbook, Version 2. English translation

International Nuclear Information System (INIS)

2001-08-01

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 the Nuclear Criticality Safety Handbook, published in 1988. The following two points are new: (1) exemplifying safety margins related to modeled dissolution and extraction processes, (2) describing evaluation methods and alarm system for criticality accidents. Revision has been made based on previous studies for the chapter that treats modeling the fuel system: e.g., the fuel grain size that the system can be regarded as homogeneous, non-uniformity effect of fuel solution, an burnup credit. This revision has solved the inconsistencies found in the first version between the evaluation of errors found in JACS code system and the criticality condition data that were calculated based on the evaluation. This report is an English translation of the Nuclear Criticality Safety Handbook, Version 2, originally published in Japanese as JAERI 1340 in 1999. (author)

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

Quality assurance manual for the development of digital systems

International Nuclear Information System (INIS)

Lee, Cheol Kwon; Kwon, Kee Choon; You, Young Eun; Kim, Kwan Hyun; Park, Jung Woo; Park, Chan Seok

2001-12-01

A digital safety system is being developed by three companies under the Korea Nuclear I and C System R and D Program. This Quality Assurance Manual (QAM) is written to ensure the safety and reliability of the system and to meet the regulatory requirements associated with quality assurance. This QAM describes eighteen elements of quality assurance criteria required for the development of the system, which are coincident with the criteria specified in Nuclear Energy Laws and Enforcement Regulations of Nuclear Energy Laws and 10CFR50 Appendix B. This QAM is submitted to the regulatory body with other documents related to the quality assurance activities performed during the system development. And its safety, validity and fulfillment are reviewed and audited in the review process of topical report of the digital safety system

Solutions manual to accompany An introduction to numerical methods and analysis

CERN Document Server

Epperson, James F

2014-01-01

A solutions manual to accompany An Introduction to Numerical Methods and Analysis, Second Edition An Introduction to Numerical Methods and Analysis, Second Edition reflects the latest trends in the field, includes new material and revised exercises, and offers a unique emphasis on applications. The author clearly explains how to both construct and evaluate approximations for accuracy and performance, which are key skills in a variety of fields. A wide range of higher-level methods and solutions, including new topics such as the roots of polynomials, sp

Status of School Safety and Security among Elementary Schools in the Fifth Class Municipality

Directory of Open Access Journals (Sweden)

Cresente E. Glariana

2015-12-01

Full Text Available This study attempted to determine the status of school safety and security in terms of the school sites, school playground, school canteen services, water safety, fire safety, campus security, building security, and sanitary facilities situation in eight (8 elementary schools in Libertad town. The descriptive survey was used to find out the status of school safety and security in the elementary schools of Libertad, Misamis Oriental. A checklist on the standards of facilities as implemented by the Department of Education was used to gather the data. Checklist was based from the 2010 Educational Facilities Manual. Evaluation based on the checklist showed that some of standards on 2010 Educational Facilities Manual were not observed. The schools have not complied with the requirements and specifications. The evaluation showed further that most of the schools did not comply within the standards set by the 2010 Educational Facilities Manual. School authorities may review the standards in the 2010 Educational Facilities Manual. The school should try to meet the standard to ensure safety and security of the pupils. Action plan may be prepared to be implemented in case of emergency.

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

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

European and International Standards on health and safety in welding

International Nuclear Information System (INIS)

Howe, A

2009-01-01

A number of European and International Standards on health and safety in welding have been published in recent years and work on several more is nearing completion. These standards have been prepared jointly by the International Standards Organization (ISO) and the European Committee for Standardization (CEN). The standards development work has mostly been led by CEN/TC 121/SC 9, with excellent technical input from experts within Europe; but work on the revision of published standards, which has recently gathered pace, is now being carried out by ISO/TC 44/SC 9, with greater international involvement. This paper gives an overview of the various standards that have been published, are being revised or are under development in this field of health and safety in welding, seeking to (i) increase international awareness of published standards, (ii) encourage wider participation in health and safety in welding standards work and (iii) obtain feedback and solicit comments on standards that are currently under development or revision. Such an initiative is particularly timely because work is currently in progress on the revision of one of the more important standards in this field, namely EN ISO 10882:2001 Health and safety in welding and allied processes- Sampling of airborne particles and gases in the operator's breathing zone - Part 1: Sampling of airborne particles.

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...

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...

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...

Effect of generic issues program on improving safety

International Nuclear Information System (INIS)

Fard, M. R.; Kauffman, J. V.

2010-01-01

The U.S. Nuclear Regulatory Commission (NRC) identifies (by its assessment of plant operation) certain issues involving public health and safety, the common defense and security, or the environment that could affect multiple entities under NRC jurisdiction. The Generic Issues Program (GIP) addresses the resolution of these Generic Issues (GIs). The resolution of these issues may involve new or revised rules, new or revised guidance, or revised interpretation of rules or guidance that affect nuclear power plant licensees, nuclear material certificate holders, or holders of other regulatory approvals. U.S. NRC provides information related to the past and ongoing GIP activities to the general public by the use of three main resources, namely NUREG-0933, 'Resolution of Generic Safety Issues, ' Generic Issues Management Control System (GIMCS), and GIP public web page. GIP information resources provide information such as historical information on resolved GIs, current status of the open GIs, policy documents, program procedures, GIP annual and quarterly reports and the process to contact GIP and propose a GI This paper provides an overview of the GIP and several examples of safety improvements resulting from the resolution of GIs. In addition, the paper provides a brief discussion of a few recent GIs to illustrate how the program functions to improve safety. (authors)

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

IAEA safety glossary. Terminology used in nuclear safety and radiation protection, multilingual 2007 edition, including the IAEA safety fundamentals [no. SF-1

International Nuclear Information System (INIS)

2008-10-01

The IAEA Safety Glossary defines and explains technical terms used in the IAEA Safety Standards and other safety related IAEA publications, and provides information on their usage.The publication is multilingual and covers the six official IAEA languages,, Arabic, Chinese, English, French, Russian and Spanish. It has been in use since April 2000. The 2007 Edition is a revised and updated version. The primary purpose of the publication is to harmonize terminology and usage in the IAEA Safety Standards. It is a source of information for users of the IAEA Safety Standards and other safety related IAEA publications and provides guidance for the drafters and reviewers of publications, including IAEA technical officers and consultants, and members of technical committees, advisory groups, working groups and bodies for the endorsement of safety standards

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

International Nuclear Information System (INIS)

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

2000-01-01

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

Peace Corps Aquaculture Training Manual. Training Manual T0057.

Science.gov (United States)

Peace Corps, Washington, DC. Information Collection and Exchange Div.

This Peace Corps training manual was developed from two existing manuals to provide a comprehensive training program in fish production for Peace Corps volunteers. The manual encompasses the essential elements of the University of Oklahoma program that has been training volunteers in aquaculture for 25 years. The 22 chapters of the manual are…

Design of the reactor coolant system and associated systems in nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2008-01-01

This Safety Guide was prepared under the IAEA programme for establishing safety standards for nuclear power plants. The basic requirements for the design of safety systems for nuclear power plants are established in the Safety Requirements publication, Safety Standards Series No. NS-R-1 on Safety of Nuclear Power Plants: Design, which it supplements. This Safety Guide describes how the requirements for the design of the reactor coolant system (RCS) and associated systems in nuclear power plants should be met. 1.2. This publication is a revision and combination of two previous Safety Guides, Safety Series No. 50-SG-D6 on Ultimate Heat Sink and Directly Associated Heat Transport Systems for Nuclear Power Plants (1981), and Safety Series No. 50-SG-D13 on Reactor Coolant and Associated Systems in Nuclear Power Plants (1986), which are superseded by this new Safety Guide. 1.3. The revision takes account of developments in the design of the RCS and associated systems in nuclear power plants since the earlier Safety Guides were published in 1981 and 1986, respectively. The other objectives of the revision are to ensure consistency with Ref., issued in 2000, and to update the technical content. In addition, an appendix on pressurized heavy water reactors (PHWRs) has been included

Manual on Safety Aspects of the Design and Equipment of Hot Laboratories

International Nuclear Information System (INIS)

1969-01-01

With the development of atomic energy application and research, hot laboratories are now being constructed in a number of countries. The present publication describes and discusses experience in several countries in designing equipment for these laboratories. The safe handling of highly radioactive substances is the main purpose of hot laboratory design and equipment. The manual aims at helping those persons, particularly in the developing countries, who plan to design and construct a new hot laboratory or modify an existing one. It does not deal in great detail with the engineering design of protective and handling equipment; these matters can be found in the comprehensive list of references. The manual itself covers only basic ideas and different approaches in the design of laboratory building, hot cells, shielded and glove boxes, fume cupboards, and handling and viewing equipment. Systems for transferring materials and main services are also discussed.

LANL Safety Conscious Work Environment (SCWE) Self-Assessment

Energy Technology Data Exchange (ETDEWEB)

Hargis, Barbara C. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2014-01-29

On December 21, 2012 Secretary of Energy Chu transmitted to the Defense Nuclear Facilities Safety Board (DNFSB) revised commitments on the implementation plan for Safety Culture at the Waste Treatment and Immobilization Plant. Action 2-5 was revised to require contractors and federal organizations to complete Safety Conscious Work Environment (SCWE) selfassessments and provide reports to the appropriate U.S. Department of Energy (DOE) - Headquarters Program Office by September 2013. Los Alamos National Laboratory (LANL) planned and conducted a Safety Conscious Work Environment (SCWE) Self-Assessment over the time period July through August, 2013 in accordance with the SCWE Self-Assessment Guidance provided by DOE. Significant field work was conducted over the 2-week period August 5-16, 2013. The purpose of the self-assessment was to evaluate whether programs and processes associated with a SCWE are in place and whether they are effective in supporting and promoting a SCWE.

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...

World of Work--The Interview and Working Relationships. Kit No. WW-706. Instructor's Manual. Revised.

Science.gov (United States)

Miles, Mamie Rose; Killingsworth, Linda

This instructor's manual contains activities for teaching students about how to obtain a Social Security card, how to fill out an employment application, how to dress and conduct themselves on job interviews, desirable traits for employees, and getting along with others on the job. It is designed for use during eight periods in classes in…

Surface Moisture Measurement System Operation and Maintenance Manual

International Nuclear Information System (INIS)

Ritter, G.A.; Pearce, K.L.; Stokes, T.L.

1995-12-01

This operations and maintenance manual addresses deployment, equipment and field hazards, operating instructions, calibration verification, removal, maintenance, and other pertinent information necessary to safely operate and store the Surface Moisture Measurement System (SMMS) and Liquid Observation Well Moisture Measurement System (LOWMMS). These systems were developed primarily in support of Tank Waste Remediation System (TWRS) Safety Programs for moisture measurement in organic and ferrocyanide watch list tanks

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)

HANSF 1.3 user's manual; TOPICAL

International Nuclear Information System (INIS)

PLYS, M.G.

1999-01-01

The HANSF analysis tool is an integrated model considering phenomena inside a multi-canister overpack (MCO) spent nuclear fuel container such as fuel oxidation, convective and radiative heat transfer, and the potential for fission product release. It may be used for all phases of spent fuel disposition including cold vacuum drying, transportation, and storage. This manual reflects HANSF version 1.3, a revised version of version 1.2a. HANSF 1.3 was written to add new models for axial nodalization, add new features for ease of usage, and correct errors. HANSF 1.3 is intended for use on personal computers such as IBM-compatible machines with Intel processors running under a DOS-type operating system. HANSF 1.3 is known to compile under Lahey TI and Digital Visual FORTRAN, Version 6.0, but this does not preclude operation in other environments

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

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.)

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

International Nuclear Information System (INIS)

2016-01-01

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

On the dimensioning of steel construction considering revision of German standards

International Nuclear Information System (INIS)

Lindhorst, L.; Schaudinn, L.; Milleder, J.

2005-01-01

Different procedures for dimensioning of structural steelwork are investigated in this paper. In the non-nuclear area, there has been made a change in the design concept for structural steelwork of surface constructions in Germany and the deterministic design concept of German DIN 18800 (03/81) [1] has been replaced by the semi-probabilistic design concept of DIN 18800 (11/90) [2]. Design codes established in nuclear safety standards for steelwork in German nuclear facilities are considered in the paper. Recent revisions of German nuclear safety standards and specifications are discussed with respect to regulations concerning design codes. The change in design concept for structural steelwork (non-nuclear) has not been adopted in recent revisions of nuclear safety standards and specifications for steelwork of components with importance to safety. The deterministic concept of DIN 18800 (03/81) [1] is compared with the semi-probabilistic concept of DIN 18800 (11/90) [2]. Differences between the standards [1] and [2] are investigated using an example of a steel construction. Results for dimensioning according to DIN 18800 (03/81) [1] are compared to those for dimensioning according to DIN 18800 (11/90) [2] putting the main emphasis on stress analysis and building structure interaction loads. (authors)

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

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

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.

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

Energy Technology Data Exchange (ETDEWEB)

Colley, D.L.

1993-10-01

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

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

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)

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

International Nuclear Information System (INIS)

Colley, D.L.

1993-01-01

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

Orientation to occupational safety compliance in DOE: Student manual, Book 1

International Nuclear Information System (INIS)

1993-01-01

The purpose of this document is to present Federal safety and health program requirements, provide an overview of DOE Safety and Health Programs, and to present information on the changes presently underway in the Department of Energy regarding safety and health. Public Law 91--596, Executive Order 12196,29 CFR 1960 and various related DOE Orders will be presented

Criticality Safety Basics for INL FMHs and CSOs

Energy Technology Data Exchange (ETDEWEB)

V. L. Putman

2012-04-01

Nuclear power is a valuable and efficient energy alternative in our energy-intensive society. However, material that can generate nuclear power has properties that require this material be handled with caution. If improperly handled, a criticality accident could result, which could severely harm workers. This document is a modular self-study guide about Criticality Safety Principles. This guide's purpose it to help you work safely in areas where fissionable nuclear materials may be present, avoiding the severe radiological and programmatic impacts of a criticality accident. It is designed to stress the fundamental physical concepts behind criticality controls and the importance of criticality safety when handling fissionable materials outside nuclear reactors. This study guide was developed for fissionable-material-handler and criticality-safety-officer candidates to use with related web-based course 00INL189, BEA Criticality Safety Principles, and to help prepare for the course exams. These individuals must understand basic information presented here. This guide may also be useful to other Idaho National Laboratory personnel who must know criticality safety basics to perform their assignments safely or to design critically safe equipment or operations. This guide also includes additional information that will not be included in 00INL189 tests. The additional information is in appendices and paragraphs with headings that begin with 'Did you know,' or with, 'Been there Done that'. Fissionable-material-handler and criticality-safety-officer candidates may review additional information at their own discretion. This guide is revised as needed to reflect program changes, user requests, and better information. Issued in 2006, Revision 0 established the basic text and integrated various programs from former contractors. Revision 1 incorporates operation and program changes implemented since 2006. It also incorporates suggestions, clarifications

Tritium radioluminescent devices, Health and Safety Manual

Energy Technology Data Exchange (ETDEWEB)

Traub, R.J.; Jensen, G.A.

1995-06-01

This document consolidates available information on the properties of tritium, including its environmental chemistry, its health physics, and safe practices in using tritium-activated RL lighting. It also summarizes relevant government regulations on RL lighting. Chapters are divided into a single-column part, which provides an overview of the topic for readers simply requiring guidance on the safety of tritium RL lighting, and a dual-column part for readers requiring more technical and detailed information.

Tritium radioluminescent devices, Health and Safety Manual

International Nuclear Information System (INIS)

Traub, R.J.; Jensen, G.A.

1995-06-01

This document consolidates available information on the properties of tritium, including its environmental chemistry, its health physics, and safe practices in using tritium-activated RL lighting. It also summarizes relevant government regulations on RL lighting. Chapters are divided into a single-column part, which provides an overview of the topic for readers simply requiring guidance on the safety of tritium RL lighting, and a dual-column part for readers requiring more technical and detailed information

Strong-back safety latch

International Nuclear Information System (INIS)

DeSantis, G.N.

1995-01-01

The calculation decides the integrity of the safety latch that will hold the strong-back to the pump during lifting. The safety latch will be welded to the strong-back and will latch to a 1.5-in. dia cantilever rod welded to the pump baseplate. The static and dynamic analysis shows that the safety latch will hold the strong-back to the pump if the friction clamps fail and the pump become free from the strong-back. Thus, the safety latch will meet the requirements of the Lifting and Rigging Manual for under the hook lifting for static loading; it can withstand shock loads from the strong-back falling 0.25 inch

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)

TASS code topical report. V.1 TASS code technical manual

International Nuclear Information System (INIS)

Sim, Suk K.; Chang, W. P.; Kim, K. D.; Kim, H. C.; Yoon, H. Y.

1997-02-01

TASS 1.0 code has been developed at KAERI for the initial and reload non-LOCA safety analysis for the operating PWRs as well as the PWRs under construction in Korea. TASS code will replace various vendor's non-LOCA safety analysis codes currently used for the Westinghouse and ABB-CE type PWRs in Korea. This can be achieved through TASS code input modifications specific to each reactor type. The TASS code can be run interactively through the keyboard operation. A simimodular configuration used in developing the TASS code enables the user easily implement new models. TASS code has been programmed using FORTRAN77 which makes it easy to install and port for different computer environments. The TASS code can be utilized for the steady state simulation as well as the non-LOCA transient simulations such as power excursions, reactor coolant pump trips, load rejections, loss of feedwater, steam line breaks, steam generator tube ruptures, rod withdrawal and drop, and anticipated transients without scram (ATWS). The malfunctions of the control systems, components, operator actions and the transients caused by the malfunctions can be easily simulated using the TASS code. This technical report describes the TASS 1.0 code models including reactor thermal hydraulic, reactor core and control models. This TASS code models including reactor thermal hydraulic, reactor core and control models. This TASS code technical manual has been prepared as a part of the TASS code manual which includes TASS code user's manual and TASS code validation report, and will be submitted to the regulatory body as a TASS code topical report for a licensing non-LOCA safety analysis for the Westinghouse and ABB-CE type PWRs operating and under construction in Korea. (author). 42 refs., 29 tabs., 32 figs

Long Term Resource Monitoring Program procedures: fish monitoring

Science.gov (United States)

Ratcliff, Eric N.; Glittinger, Eric J.; O'Hara, T. Matt; Ickes, Brian S.

2014-01-01

This manual constitutes the second revision of the U.S. Army Corps of Engineers’ Upper Mississippi River Restoration-Environmental Management Program (UMRR-EMP) Long Term Resource Monitoring Program (LTRMP) element Fish Procedures Manual. The original (1988) manual merged and expanded on ideas and recommendations related to Upper Mississippi River fish sampling presented in several early documents. The first revision to the manual was made in 1995 reflecting important protocol changes, such as the adoption of a stratified random sampling design. The 1995 procedures manual has been an important document through the years and has been cited in many reports and scientific manuscripts. The resulting data collected by the LTRMP fish component represent the largest dataset on fish within the Upper Mississippi River System (UMRS) with more than 44,000 collections of approximately 5.7 million fish. The goal of this revision of the procedures manual is to document changes in LTRMP fish sampling procedures since 1995. Refinements to sampling methods become necessary as monitoring programs mature. Possible refinements are identified through field experiences (e.g., sampling techniques and safety protocols), data analysis (e.g., planned and studied gear efficiencies and reallocations of effort), and technological advances (e.g., electronic data entry). Other changes may be required because of financial necessity (i.e., unplanned effort reductions). This version of the LTRMP fish monitoring manual describes the most current (2014) procedures of the LTRMP fish component.

Emergency Victim Care. A Training Manual for Emergency Medical Technicians. Module 5. CPR, Oxygen Therapy. Revised.

Science.gov (United States)

Ohio State Dept. of Education, Columbus. Div. of Vocational Education.

This student manual, the fifth in a set of 14 modules, is designed to train emergency medical technicians (EMTs) in Ohio. The module contains two sections covering the following course content; cardiopulmonary resuscitation (CPR) (including artificial ventilation, foreign body obstructions, adjunctive equipment and special techniques, artificial…

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

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

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

National Ignition Facility Project Site Safety Program

International Nuclear Information System (INIS)

Dun, C

2003-01-01

This Safety Program for the National Ignition Facility (NIF) presents safety protocols and requirements that management and workers shall follow to assure a safe and healthful work environment during activities performed on the NIF Project site. The NIF Project Site Safety Program (NPSSP) requires that activities at the NIF Project site be performed in accordance with the ''LLNL ES and H Manual'' and the augmented set of controls and processes described in this NIF Project Site Safety Program. Specifically, this document: (1) Defines the fundamental NIF site safety philosophy. (2) Defines the areas covered by this safety program (see Appendix B). (3) Identifies management roles and responsibilities. (4) Defines core safety management processes. (5) Identifies NIF site-specific safety requirements. This NPSSP sets forth the responsibilities, requirements, rules, policies, and regulations for workers involved in work activities performed on the NIF Project site. Workers are required to implement measures to create a universal awareness that promotes safe practice at the work site and will achieve NIF management objectives in preventing accidents and illnesses. ES and H requirements are consistent with the ''LLNL ES and H Manual''. This NPSSP and implementing procedures (e.g., Management Walkabout, special work procedures, etc.,) are a comprehensive safety program that applies to NIF workers on the NIF Project site. The NIF Project site includes the B581/B681 site and support areas shown in Appendix B

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.

Nuclear safety chains

International Nuclear Information System (INIS)

Robbins, M.C.; Eames, G.F.; Mayell, J.R.

1981-01-01

An original scheme has been developed for expressing the complex interrelationships associated with the engineered safeguards provided for a nuclear power station. This management tool, based upon network diagrams called Nuclear Safety Chains, looks at the function required of a particular item of safety plant, defines all of the vital supplies and support features necessary for successful operation, and expresses them in visual form, to facilitate analysis and optimisation for operations and maintenance staff. The safety chains are confined to manual schemes at present, although they are designed to be compatible with modern computer techniques. Their usefulness with any routine maintenance planning application on high technology plant is already being appreciated. (author)

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...

Integration of a browser based operator manual in the system environment of a process computer system; Integration eines browserbasierten Betriebshandbuchs in die Systemumgebung einer Prozessrechneranlage

Energy Technology Data Exchange (ETDEWEB)

Weber, Andreas [Westinghouse Electric Germany GmbH (Germany); Erfle, Robert [DOSCO GmbH, Heidelberg (Germany); Feinkohl, Dirk [E.ON Kernkraft GmbH (Germany). Kernkraftwerk Unterweser

2012-11-01

The integration of a browser based operator manual in the system environment of a process computer system is an optimization of the operating procedure in the control room and a safety enhancement due to faster and error-free access to the manual contents. Several requirements by the authorities have to be fulfilled: the operating manual has to be available as hard copy, the format has to be true to original, protection against manipulation has to be provided, the manual content of the browser-based version and the hard copy have to identical, and the display presentation has to be consistent with ergonomic principals. The integration of the on-line manual in the surveillance process computer system provides the operator with the relevant comments to the surveillance signal. The described integration of the on-line manual is an optimization of the operator's everyday job with respect to ergonomics and safety (human performance).

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

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

Probabilistic safety analysis applied to RBMK reactors

International Nuclear Information System (INIS)

Gerez Martin, L.; Fernandez Ramos, P.

1995-01-01

The project financed by the European Union ''Revision of RBMK Reactor Safety was divided into nine Topic Groups dealing with different aspects of safety. The area covered by Topic Group 9 was Probabilistic Safety Analysis. TG9 will have touched on some of the problems discussed by other groups, although in terms of the systematic quantification of the impact of design characteristics and RBMK reactor operating practices on the risk of core damage. On account of the reduced time scale and the resources available for the project, the analysis was made using a simplified method based on the results of PSAs conducted in Western countries and on the judgement of the group members. The simplifies method is based on the concepts of Qualification, Redundancy and Automatic Actuation of the systems considered. PSA experience shows that systems complying with the above-mentioned concepts have a failure probability of 1.0E-3 when redundancy is simple, ie two similar equipment items capable of carrying out the same function. In general terms, this value can be considered to be dominated by potential common cause failures. The value considered above changes according to factors that have a positive effect upon it, such as an additional redundancy with a different equipment item (eg a turbo pumps and a motor pump), individual trains with good separations, etc, or a negative effect, such as the absence of suitable periodical tests, the need for operators to perform manual operations, etc. Similarly, possible actions required by the operator during accident sequences are assigned failure probability values between 1 and 1.0E-4, according to the complexity of the action (including local actions to be performed outside the control room) and the time available

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

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.

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.

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.

Quantitative X ray analysis system. User's manual and guide to X ray fluorescence technique

International Nuclear Information System (INIS)

2009-01-01

This guide covers trimmed and re-arranged version 3.6 of the Quantitative X ray Analysis System (QXAS) software package that includes the most frequently used methods of quantitative analysis. QXAS is a comprehensive quantitative analysis package that has been developed by the IAEA through research and technical contracts. Additional development has also been carried out in the IAEA Laboratories in Seibersdorf where QXAS was extensively tested. New in this version of the manual are the descriptions of the Voigt-profile peak fitting, the backscatter fundamental parameters' and emission-transmission methods of chemical composition analysis, an expanded chapter on the X ray fluorescence physics, and completely revised and increased number of practical examples of utilization of the QXAS software package. The analytical data accompanying this manual were collected in the IAEA Seibersdorf Laboratories in the years 2006/2007