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Sample records for safety plan b360

  1. IR-360 nuclear power plant safety functions and component classification

    International Nuclear Information System (INIS)

    Yousefpour, F.; Shokri, F.; Soltani, H.

    2010-01-01

    The IR-360 nuclear power plant as a 2-loop PWR of 360 MWe power generation capacity is under design in MASNA Company. For design of the IR-360 structures, systems and components (SSCs), the codes and standards and their design requirements must be determined. It is a prerequisite to classify the IR-360 safety functions and safety grade of structures, systems and components correctly for selecting and adopting the suitable design codes and standards. This paper refers to the IAEA nuclear safety codes and standards as well as USNRC standard system to determine the IR-360 safety functions and to formulate the principles of the IR-360 component classification in accordance with the safety philosophy and feature of the IR-360. By implementation of defined classification procedures for the IR-360 SSCs, the appropriate design codes and standards are specified. The requirements of specific codes and standards are used in design process of IR-360 SSCs by design engineers of MASNA Company. In this paper, individual determination of the IR-360 safety functions and definition of the classification procedures and roles are presented. Implementation of this work which is described with example ensures the safety and reliability of the IR-360 nuclear power plant.

  2. IR-360 nuclear power plant safety functions and component classification

    Energy Technology Data Exchange (ETDEWEB)

    Yousefpour, F., E-mail: fyousefpour@snira.co [Management of Nuclear Power Plant Construction Company (MASNA) (Iran, Islamic Republic of); Shokri, F.; Soltani, H. [Management of Nuclear Power Plant Construction Company (MASNA) (Iran, Islamic Republic of)

    2010-10-15

    The IR-360 nuclear power plant as a 2-loop PWR of 360 MWe power generation capacity is under design in MASNA Company. For design of the IR-360 structures, systems and components (SSCs), the codes and standards and their design requirements must be determined. It is a prerequisite to classify the IR-360 safety functions and safety grade of structures, systems and components correctly for selecting and adopting the suitable design codes and standards. This paper refers to the IAEA nuclear safety codes and standards as well as USNRC standard system to determine the IR-360 safety functions and to formulate the principles of the IR-360 component classification in accordance with the safety philosophy and feature of the IR-360. By implementation of defined classification procedures for the IR-360 SSCs, the appropriate design codes and standards are specified. The requirements of specific codes and standards are used in design process of IR-360 SSCs by design engineers of MASNA Company. In this paper, individual determination of the IR-360 safety functions and definition of the classification procedures and roles are presented. Implementation of this work which is described with example ensures the safety and reliability of the IR-360 nuclear power plant.

  3. 33 CFR 96.360 - Interim Safety Management Certificate: what is it and when can it be used?

    Science.gov (United States)

    2010-07-01

    ...? § 96.360 Interim Safety Management Certificate: what is it and when can it be used? (a) A responsible... 33 Navigation and Navigable Waters 1 2010-07-01 2010-07-01 false Interim Safety Management Certificate: what is it and when can it be used? 96.360 Section 96.360 Navigation and Navigable Waters COAST...

  4. 29 CFR 1952.360 - Description of the plan as initially approved.

    Science.gov (United States)

    2010-07-01

    .... It adopts the definition of occupational safety and health issues expressed in § 1909.2(c)(1) of this... issues raised during the review process, including proposals to be submitted to the New Mexico... Section 1952.360 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH...

  5. 49 CFR 178.360-2 - Manufacture.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 2 2010-10-01 2010-10-01 false Manufacture. 178.360-2 Section 178.360-2 Transportation Other Regulations Relating to Transportation PIPELINE AND HAZARDOUS MATERIALS SAFETY... Specifications for Packagings for Class 7 (Radioactive) Materials § 178.360-2 Manufacture. The ends of the vessel...

  6. Implementing and measuring safety goals and safety culture. 3. Shifting to a Coaching Culture Through a 360-Degree Assessment Process

    International Nuclear Information System (INIS)

    Snow, Bruce A.; Maciuska, Frank

    2001-01-01

    Error-free operation is the ultimate objective of any safety culture. Ginna Training and Operations has embarked on an approach directed at further developing coaching skills, attitudes, and values. To accomplish this, a 360-deg assessment process designed to enhance coaching skills, attitudes, and values has been implemented. The process includes measuring participants based on a set of values and an individual self-development plan based on the feedback from the 360-deg assessment. The skills and experience of the people who make up that culture are irreplaceable. As nuclear organizations mature and generations retire, knowledge and skills must be transferred to the incoming generations without a loss in performance. The application of a 360- deg assessment process can shift the culture to include coaching in a strong command and control environment. It is a process of change management strengthened by experience while meeting the challenge to improve human performance by changing workplace attitudes. At Ginna, training programs and new processes were initiated to pursue the ultimate objective: error-free operation. The overall objective of the programs is to create a common knowledge base and the skill required to consistently incorporate ownership of 'coach and collaborate' responsibility into a strong existing 'command and control' culture. This involves the role of coach; the role of communications; and concept integration, which includes communications, coaching, and team dimensional training (TDT). The overall objective of the processes, TDT and shifting to a coaching culture through the application of a 360-deg assessment process, is to provide guidance for applying the skills learned in the programs. As depicted in Fig. 1, the TDT (a process that identifies 'strengths and challenges') can be greatly improved by applying good communications and coaching practices. As the training programs were implemented, the participants were observed and coached in

  7. Quality assurance program plan for 324 Building B-Cell safety cleanout project (BCCP)

    International Nuclear Information System (INIS)

    Tanke, J.M.

    1997-01-01

    This Quality Assurance Program Plan (QAPP) provides information on how the Quality Assurance Program is implemented for the 324 Building B-Cell Safety Cleanout Project (BCCP). This QAPP is responsive to the Westinghouse Hanford Company Quality Assurance Program and Implementation Plan, WHC-SP-1131, for 10 CFR 830.120, Nuclear Safety Management, Quality Assurance Requirements; and DOE Order 5700.6C, Quality Assurance. This QAPP supersedes PNNL PNL-MA-70 QAP Quality Assurance Plan No. WTC-050 Rev. 2, issue date May 3, 1996. This QAPP has been developed specifically for the BCCP. It applies to those items and tasks which affect the completion of activities identified in the work breakdown structure of the Project Management Plan (PMP). These activities include all aspects of decontaminating B-Cell and project related operations within the 324 Building as it relates to the specific activities of this project. General facility activities (i.e. 324 Building Operations) are covered in the Building 324 QAPP. In addition, this QAPP supports the related quality assurance activities addressed in CM-2-14, Hazardous Material Packaging and Shipping, and HSRCM-1, Hanford Site Radiological Control Manual, The 324 Building is currently transitioning from being a Pacific Northwest National Laboratory (PNNL) managed facility to a B and W Hanford Company (BWHC) managed facility. During this transition process existing, PNNL procedures and documents will be utilized until replaced by BWHC procedures and documents. These documents conform to the requirements found in PNL-MA-70, Quality Assurance Manual and PNL-MA-8 1, Hazardous Materials Shipping Manual. The Quality Assurance Program Index (QAPI) contained in Table 1 provides a matrix which shows how project activities relate to 10 CFR 83 0.120 and 5700.6C criteria. Quality Assurance program requirements will be addressed separate from the requirements specified in this document. Other Hanford Site organizations/companies may be

  8. 46 CFR 132.360 - Fire axes.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 4 2010-10-01 2010-10-01 false Fire axes. 132.360 Section 132.360 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) OFFSHORE SUPPLY VESSELS FIRE-PROTECTION EQUIPMENT Miscellaneous § 132.360 Fire axes. (a) Each vessel of less than 100 gross tons must carry one fire axe. (b) Each...

  9. 49 CFR 659.25 - Annual review of system safety program plan and system security plan.

    Science.gov (United States)

    2010-10-01

    ... system security plan. 659.25 Section 659.25 Transportation Other Regulations Relating to Transportation... and system security plan. (a) The oversight agency shall require the rail transit agency to conduct an annual review of its system safety program plan and system security plan. (b) In the event the rail...

  10. 46 CFR 129.360 - Semiconductor-rectifier systems.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 4 2010-10-01 2010-10-01 false Semiconductor-rectifier systems. 129.360 Section 129.360... INSTALLATIONS Power Sources and Distribution Systems § 129.360 Semiconductor-rectifier systems. (a) Each semiconductor-rectifier system must have an adequate heat-removal system to prevent overheating. (b) If a...

  11. 46 CFR 120.360 - Semiconductor rectifier systems.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 4 2010-10-01 2010-10-01 false Semiconductor rectifier systems. 120.360 Section 120.360... INSTALLATION Power Sources and Distribution Systems § 120.360 Semiconductor rectifier systems. (a) Each semiconductor rectifier system must have an adequate heat removal system that prevents overheating. (b) Where a...

  12. NIF conventional facilities construction health and safety plan

    International Nuclear Information System (INIS)

    Benjamin, D W

    1998-01-01

    The purpose of this Plan is to outline the minimum health and safety requirements to which all participating Lawrence Livermore National Laboratory (LLNL) and non-LLNL employees (excluding National Ignition Facility [NIF] specific contractors and subcontractors covered under the construction subcontract packages (e.g., CSP-9)-see Construction Safety Program for the National Ignition Facility [CSP] Section I.B. ''NIF Construction Contractors and Subcontractors'' for specifics) shall adhere to for preventing job-related injuries and illnesses during Conventional Facilities construction activities at the NIF Project. For the purpose of this Plan, the term ''LLNL and non-LLNL employees'' includes LLNL employees, LLNL Plant Operations staff and their contractors, supplemental labor, contract labor, labor-only contractors, vendors, DOE representatives, personnel matrixed/assigned from other National Laboratories, participating guests, and others such as visitors, students, consultants etc., performing on-site work or services in support of the NIF Project. Based upon an activity level determination explained in Section 1.2.18, in this document, these organizations or individuals may be required by site management to prepare their own NIF site-specific safety plan. LLNL employees will normally not be expected to prepare a site-specific safety plan. This Plan also outlines job-specific exposures and construction site safety activities with which LLNL and non-LLNL employees shall comply

  13. 46 CFR 174.360 - Calculations.

    Science.gov (United States)

    2010-10-01

    ... GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) SUBDIVISION AND STABILITY SPECIAL RULES PERTAINING TO SPECIFIC VESSEL TYPES Special Rules Pertaining to Dry Cargo Ships § 174.360 Calculations. Each ship to... for that ship by the International Convention for the Safety of Life at Sea, 1974, as amended, chapter...

  14. 78 FR 61251 - The National Public Transportation Safety Plan, the Public Transportation Agency Safety Plan, and...

    Science.gov (United States)

    2013-10-03

    ...-0030] RIN 2132-AB20; 2132-AB07 The National Public Transportation Safety Plan, the Public Transportation Agency Safety Plan, and the Public Transportation Safety Certification Training Program; Transit... Public Transportation Safety Program (National Safety Program) and the requirements of the new transit...

  15. Safety case plan 2008

    International Nuclear Information System (INIS)

    2008-07-01

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

  16. 48 CFR 970.5223-1 - Integration of environment, safety, and health into work planning and execution.

    Science.gov (United States)

    2010-10-01

    ..., safety, and health into work planning and execution. 970.5223-1 Section 970.5223-1 Federal Acquisition... Integration of environment, safety, and health into work planning and execution. As prescribed in 970.2303-3(b), insert the following clause: Integration of Environment, Safety, and Health Into Work Planning and...

  17. 29 CFR 1915.502 - Fire safety plan.

    Science.gov (United States)

    2010-07-01

    ... implement a written fire safety plan that covers all the actions that employers and employees must take to ensure employee safety in the event of a fire. (See Appendix A to this subpart for a Model Fire Safety... safety plan for their employees, and this plan must comply with the host employer's fire safety plan. ...

  18. 31 CFR 360.29 - Adjudication of claims.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 2 2010-07-01 2010-07-01 false Adjudication of claims. 360.29 Section 360.29 Money and Finance: Treasury Regulations Relating to Money and Finance (Continued) FISCAL... the ordinary course of business. (b) Claims filed 10 years after payment. Any claim filed 10 years or...

  19. Integrated operations plan for the MFTF-B Mirror Fusion Test Facility. Volume I. Organization plan

    International Nuclear Information System (INIS)

    1981-12-01

    This plan and the accompanying MFTF-B Integrated Operations Plan are submitted in response to UC/LLNL Purchase Order 3883801, dated July 1981. The organization plan also addresses the specific tasks and trade studies directed by the scope of work. The Integrated Operations Plan, which includes a reliability, quality assurance, and safety plan and an integrated logistics plan, comprises the burden of the report. In the first section of this volume, certain underlying assumptions and observations are discussed setting the requirements and limits for organization. Section B presents the recommended structure itself. Section C Device Availability vs Maintenance and Support Efforts and Section D Staffing Levels and Skills provide backup detail and justification. Section E is a trade study on maintenance and support by LLNL staff vs subcontract and Section F is a plan for transitioning from the construction phase into operation. A brief summary of schedules and estimated costs concludes the volume

  20. Maine highway safety plan

    Science.gov (United States)

    2010-01-01

    Each September 1, the MeBHS must provide NHTSA a comprehensive plan to reduce : traffic crashes and resulting deaths, injuries and property damage. The Highway Safety : Plan (HSP) serves as Maines application for available federal funds for these ...

  1. Criteria Document for B-plant's Surveillance and Maintenance Phase Safety Basis Document

    International Nuclear Information System (INIS)

    SCHWEHR, B.A.

    1999-01-01

    This document is required by the Project Hanford Managing Contractor (PHMC) procedure, HNF-PRO-705, Safety Basis Planning, Documentation, Review, and Approval. This document specifies the criteria that shall be in the B Plant surveillance and maintenance phase safety basis in order to obtain approval of the DOE-RL. This CD describes the criteria to be addressed in the S and M Phase safety basis for the deactivated Waste Fractionization Facility (B Plant) on the Hanford Site in Washington state. This criteria document describes: the document type and format that will be used for the S and M Phase safety basis, the requirements documents that will be invoked for the document development, the deactivated condition of the B Plant facility, and the scope of issues to be addressed in the S and M Phase safety basis document

  2. Fusion safety program plan

    International Nuclear Information System (INIS)

    Crocker, J.G.; Holland, D.F.; Herring, J.S.

    1980-09-01

    The program plan consists of research that has been divided into 13 different areas. These areas focus on the radioactive inventories that are expected in fusion reactors, the energy sources potentially available to release a portion of these inventories, and analysis and design techniques to assess and ensure that the safety risks associated with operation of magnetic fusion facilities are acceptably low. The document presents both long-term program requirements that must be fulfilled as part of the commercialization of fusion power and a five-year plan for each of the 13 different program areas. Also presented is a general discussion of magnetic fusion reactor safety, a method for establishing priorities in the program, and specific priority ratings for each task in the five-year plan

  3. NIF special equipment construction health and safety plan

    Energy Technology Data Exchange (ETDEWEB)

    Sawicki, R.H.

    1997-07-28

    The purpose of this plan is to identify how the construction and deployment activities of the National Ignition Facility (NIF) Special Equipment (SE) will be safely executed. This plan includes an identification of (1) the safety-related responsibilities of the SE people and their interaction with other organizations involved; (2) safety related requirements, policies, and documentation; (3) a list of the potential hazards unique to SE systems and the mechanisms that will be implemented to control them to acceptable levels; (4) a summary of Environmental Safety and Health (ES&H) training requirements; and (5) requirements of contractor safety plans that will be developed and used by all SE contractors participating in site activities. This plan is a subsidiary document to the NIF Construction Safety Program (CSP) and is intended to compliment the requirements stated therein with additional details specific to the safety needs of the SE construction-related activities. If a conflict arises between these two documents, the CSP will supersede. It is important to note that this plan does not list all of the potential hazards and their controls because the design and safety analysis process is still ongoing. Additional safety issues win be addressed in the Final Safety Analysis Report, Operational Safety Procedures (OSPs), and other plans and procedures as described in Section 3.0 of this plan.

  4. NIF special equipment construction health and safety plan

    International Nuclear Information System (INIS)

    Sawicki, R.H.

    1997-01-01

    The purpose of this plan is to identify how the construction and deployment activities of the National Ignition Facility (NIF) Special Equipment (SE) will be safely executed. This plan includes an identification of (1) the safety-related responsibilities of the SE people and their interaction with other organizations involved; (2) safety related requirements, policies, and documentation; (3) a list of the potential hazards unique to SE systems and the mechanisms that will be implemented to control them to acceptable levels; (4) a summary of Environmental Safety and Health (ES ampersand H) training requirements; and (5) requirements of contractor safety plans that will be developed and used by all SE contractors participating in site activities. This plan is a subsidiary document to the NIF Construction Safety Program (CSP) and is intended to compliment the requirements stated therein with additional details specific to the safety needs of the SE construction-related activities. If a conflict arises between these two documents, the CSP will supersede. It is important to note that this plan does not list all of the potential hazards and their controls because the design and safety analysis process is still ongoing. Additional safety issues win be addressed in the Final Safety Analysis Report, Operational Safety Procedures (OSPs), and other plans and procedures as described in Section 3.0 of this plan

  5. Environmental restoration contractor facility safety plan -- MO-561 100-D site remediation project

    International Nuclear Information System (INIS)

    Donahoe, R.L.

    1996-11-01

    This safety plan is applicable to Environmental Restoration Contractor personnel who are permanently assigned to MO-561 or regularly work in the facility. The MO-561 Facility is located in the 100-D Area at the Hanford Site in Richland, Washington. This plan will: (a) identify hazards potentially to be encountered by occupants of MO-561; (b) provide requirements and safeguards to ensure personnel safety and regulatory compliance; (c) provide information and actions necessary for proper emergency response

  6. Chemical Hygiene and Safety Plan

    Energy Technology Data Exchange (ETDEWEB)

    Berkner, K.

    1992-08-01

    The objective of this Chemical Hygiene and Safety Plan (CHSP) is to provide specific guidance to all LBL employees and contractors who use hazardous chemicals. This Plan, when implemented, fulfills the requirements of both the Federal OSHA Laboratory Standard (29 CFR 1910.1450) for laboratory workers, and the Federal OSHA Hazard Communication Standard (29 CFR 1910.1200) for non-laboratory operations (e.g., shops). It sets forth safety procedures and describes how LBL employees are informed about the potential chemical hazards in their work areas so they can avoid harmful exposures and safeguard their health. Generally, communication of this Plan will occur through training and the Plan will serve as a the framework and reference guide for that training.

  7. Tank 241-B-103 tank characterization plan

    International Nuclear Information System (INIS)

    Carpenter, B.C.

    1995-01-01

    The Defense Nuclear Facilities Safety Board (DNFSB) has advised the US Department of Energy (DOE) to concentrate the near-term sampling and analysis activities on identification and resolution of safety issues. The data quality objective (DQO) process was chosen as a tool to be used to identify sampling and analytical needs for the resolution of safety issues. As a result, a revision in the Federal Facility Agreement and Consent Order (Tri-Party Agreement or TPA) milestone M-44-00 has been made, which states that ''A Tank Characterization Plan (TCP) will also be developed for each double-shell tank (DST) and single-shell tank (SST) using the DQO process... Development of TCPs by the DQO process is intended to allow users (e.g., Hanford Facility user groups, regulators) to ensure their needs will be met and that resources are devoted to gaining only necessary information.'' This document satisfies that requirement for Tank 241-B-103 (B-103) sampling activities. Tank B-103 was placed on the Organic Watch List in January 1991 due to review of TRAC data that predicts a TOC content of 3.3 dry weight percent. The tank was classified as an assumed leaker of approximately 30,280 liters (8,000 gallons) in 1978 and declared inactive. Tank B-103 is passively ventilated with interim stabilization and intrusion prevention measures completed in 1985

  8. NPP Krsko Periodic Safety Review action plan

    International Nuclear Information System (INIS)

    Bilic Zabric, T.

    2006-01-01

    In the current, internationally accepted, safety philosophy Periodic Safety Reviews (PSRs) are comprehensive reviews aimed at the verification that an operating NPP remains safe when judged against current safety objectives and practices and that adequate arrangements are in place to maintain an acceptable level of safety. These reviews are complementary to the routine and special safety reviews. They are long time-scale reviews intended to deal with the cumulative effects of plant ageing, modifications, operating experience and technical developments, which are not so easily comprehended over the shorter time-scale routine of safety reviews. The review was completed in 2005 and the next period will see the implementation of the action plan including some plant upgrades. The action plan lists issues that should be implemented at NPP Krsko together with associated milestones. The milestones were assumed based on best estimate resource availability and their ends can be potentially floated. In some cases, multiple corrective measures may be postulated to provide resolution for a given safety issue. The Slovenian Nuclear Safety Administration by decree approved the first periodic safety review and the implementation plan of activities arising from it. The entire implementation plan must be carried out by 15 October 2010. Report on the second periodic safety review must be submitted by the NEK not later than 15 December 2013. (author)

  9. UMTRA Project environmental, health, and safety plan

    International Nuclear Information System (INIS)

    1989-02-01

    The basic health and safety requirements established in this plan are designed to provide guidelines to be applied at all Uranium Mill Tailings Remedial Action (UMTRA) Project sites. Specific restrictions are given where necessary. However, an attempt has been made to provide guidelines which are generic in nature, and will allow for evaluation of site-specific conditions. Health and safety personnel are expected to exercise professional judgment when interpreting these guidelines to ensure the health and safety of project personnel and the general population. This UMTRA Project Environmental, Health, and Safety (EH ampersand S) Plan specifies the basic Federal health and safety standards and special DOE requirements applicable to this program. In addition, responsibilities in carrying out this plan are delineated. Some guidance on program requirements and radiation control and monitoring is also included. An Environmental, Health, and Safety Plan shall be developed as part of the remedial action plan for each mill site and associated disposal site. Special conditions at the site which may present potential health hazards will be described, and special areas that should should be addressed by the Remedial Action Contractor (RAC) will be indicated. Site-specific EH ampersand S concerns will be addressed by special contract conditions in RAC subcontracts. 2 tabs

  10. 31 CFR 360.90 - Waiver of regulations.

    Science.gov (United States)

    2010-07-01

    ... STATES SAVINGS BONDS, SERIES I Miscellaneous Provisions § 360.90 Waiver of regulations. The Commissioner... unnecessary hardship: (a) If such action would not be inconsistent with law or equity; (b) If it does not...

  11. Seismic safety research program plan

    International Nuclear Information System (INIS)

    1985-06-01

    This plan describes the safety issues, regulatory needs, and the research necessary to address these needs. The plan also discusses the relationship between current and proposed research within the NRC and research sponsored by other government agencies, universities, industry groups, professional societies, and foreign sources

  12. Experimental investigations concerning the three particle reaction 19B(d,3α) at 360 keV

    International Nuclear Information System (INIS)

    Nocken, U.

    1976-01-01

    In this paper a complete energy angular correlation measurement of the three-particle reaction 10 B(d,3α) with an incident energy of Esub(d) = 360 keV is reported. By the measurement of coincidence events in two detectors complanar to the incident beam under 24 different angles, the 'Dalitz-plane' is covered in a wide region. An exact theory of three-particle reactions with compound nuclei in the final state does not exist, therefore three wellknown model theories are used for comparison. (orig./WL) [de

  13. Development of Comprehensive Nuclear Safety Regulation Plan for 2007-2011

    International Nuclear Information System (INIS)

    Choi, Young Sung; Kim, Woong Sik; Park, Dong Keuk; Kim, Ho Ki

    2006-01-01

    The Article 8-2 of Atomic Energy Act requires the government to establish Atomic Energy Promotion Plan every five years. It sets out national nuclear energy policies in a systematic and consistent way. The plan presents the goals and basic directions of national nuclear energy policies on the basis of current status and prospects. Both areas of utilization and safety management of nuclear energy are included and various projects and schedules are delineated based on the national policy directions. The safety management area in this plan deals with the overall safety and regulation policy. Its detail projects and schedule should be developed in separate plans by responsible ministries under the mediation of the MOST. As a regulatory authority, MOST is responsible for safety management area and its technical support organization, KINS has developed Comprehensive Nuclear Safety Regulation Plan as an implementation plan of safety area. This paper presents the development process and specific projects contained in the Comprehensive Nuclear Safety Regulation Plan which is under development now

  14. [Post-marketing drug safety-risk management plan(RMP)].

    Science.gov (United States)

    Ezaki, Asami; Hori, Akiko

    2013-03-01

    The Guidance for Risk Management Plan(RMP)was released by the Ministry of Health, Labour and Welfare in April 2012. The RMP consists of safety specifications, pharmacovigilance plans and risk minimization action plans. In this paper, we outline post-marketing drug safety operations in PMDA and the RMP, with examples of some anticancer drugs.

  15. OCRWM [Office of Civilian Radioactive Waste Management] Safety Plan

    International Nuclear Information System (INIS)

    1986-12-01

    The OCRWM Safety Plan sets forth management policies and general requirements for the safety of the public and of personnel associated with the Civilian Radioactive Waste Management Program (hereinafter called the ''Program''). It is applicable to all individuals and organizational elements of the Program, including all facilities and activities controlled by the Program pursuant to the Act, and to all phases of the Program. The plan defines the responsibilities assigned by the Director of the OCRWM to the various OCRWM line organizations, and to the contractors and the projects. It discusses the means by which safety policies and requirements will be communicated, and summarizes the applicable DOE Orders, and the procedures for reviewing, reporting, and evaluating safety problems. In addition, the OCRWM Safety Plan addresses DOE Orders applicable to occupational health and safety, worker protection, and public health and safety. OCRWM believes that it has an equally high level of commitment to both public safety and worker safety. The Plan also summarizes applicable NRC criteria and regulations that will be imposed through the formal licensing proceedings. While the Safety Plan sets forth OCRWM policy, it is not intended to be prescriptive in the details of implementation. Each OCRWM program element must develop and control its own set of detailed requirements for the protection of its workers and the public based on the principles set forth herein

  16. High-heat tank safety issue resolution program plan

    International Nuclear Information System (INIS)

    Wang, O.S.

    1993-12-01

    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 (SST) 241-C-106. This program plan also outlines the logic for selecting approaches and tasks to mitigate and resolve the high-heat safety issue. The identified safety issue for high-heat tank 241-C-106 involves the potential release of nuclear waste to the environment as the result of heat-induced structural damage to the tank's concrete, if forced cooling is interrupted for extended periods. Currently, forced ventilation with added water to promote thermal conductivity and evaporation cooling is used to cool the waste. At this time, the only viable solution identified to resolve this safety issue is the removal of heat generating waste in the tank. This solution is being aggressively pursued as the permanent solution to this safety issue and also to support the present waste retrieval plan. Tank 241-C-106 has been selected as the first SST for retrieval. The program plan has three parts. The first part establishes program objectives and defines safety issues, drivers, and resolution criteria and strategy. The second part evaluates the high-heat safety issue and its mitigation and remediation methods and alternatives according to resolution logic. The third part identifies major tasks and alternatives for mitigation and resolution of the safety issue. Selected tasks and best-estimate schedules are also summarized in the program plan

  17. Documented Safety Analysis for the B695 Segment

    Energy Technology Data Exchange (ETDEWEB)

    Laycak, D

    2008-09-11

    This Documented Safety Analysis (DSA) was prepared for the Lawrence Livermore National Laboratory (LLNL) Building 695 (B695) Segment of the Decontamination and Waste Treatment Facility (DWTF). The report provides comprehensive information on design and operations, including safety programs and safety structures, systems and components to address the potential process-related hazards, natural phenomena, and external hazards that can affect the public, facility workers, and the environment. Consideration is given to all modes of operation, including the potential for both equipment failure and human error. The facilities known collectively as the DWTF are used by LLNL's Radioactive and Hazardous Waste Management (RHWM) Division to store and treat regulated wastes generated at LLNL. RHWM generally processes low-level radioactive waste with no, or extremely low, concentrations of transuranics (e.g., much less than 100 nCi/g). Wastes processed often contain only depleted uranium and beta- and gamma-emitting nuclides, e.g., {sup 90}Sr, {sup 137}Cs, or {sup 3}H. The mission of the B695 Segment centers on container storage, lab-packing, repacking, overpacking, bulking, sampling, waste transfer, and waste treatment. The B695 Segment is used for storage of radioactive waste (including transuranic and low-level), hazardous, nonhazardous, mixed, and other waste. Storage of hazardous and mixed waste in B695 Segment facilities is in compliance with the Resource Conservation and Recovery Act (RCRA). LLNL is operated by the Lawrence Livermore National Security, LLC, for the Department of Energy (DOE). The B695 Segment is operated by the RHWM Division of LLNL. Many operations in the B695 Segment are performed under a Resource Conservation and Recovery Act (RCRA) operation plan, similar to commercial treatment operations with best demonstrated available technologies. The buildings of the B695 Segment were designed and built considering such operations, using proven building

  18. Documented Safety Analysis for the B695 Segment

    International Nuclear Information System (INIS)

    Laycak, D.

    2008-01-01

    This Documented Safety Analysis (DSA) was prepared for the Lawrence Livermore National Laboratory (LLNL) Building 695 (B695) Segment of the Decontamination and Waste Treatment Facility (DWTF). The report provides comprehensive information on design and operations, including safety programs and safety structures, systems and components to address the potential process-related hazards, natural phenomena, and external hazards that can affect the public, facility workers, and the environment. Consideration is given to all modes of operation, including the potential for both equipment failure and human error. The facilities known collectively as the DWTF are used by LLNL's Radioactive and Hazardous Waste Management (RHWM) Division to store and treat regulated wastes generated at LLNL. RHWM generally processes low-level radioactive waste with no, or extremely low, concentrations of transuranics (e.g., much less than 100 nCi/g). Wastes processed often contain only depleted uranium and beta- and gamma-emitting nuclides, e.g., 90 Sr, 137 Cs, or 3 H. The mission of the B695 Segment centers on container storage, lab-packing, repacking, overpacking, bulking, sampling, waste transfer, and waste treatment. The B695 Segment is used for storage of radioactive waste (including transuranic and low-level), hazardous, nonhazardous, mixed, and other waste. Storage of hazardous and mixed waste in B695 Segment facilities is in compliance with the Resource Conservation and Recovery Act (RCRA). LLNL is operated by the Lawrence Livermore National Security, LLC, for the Department of Energy (DOE). The B695 Segment is operated by the RHWM Division of LLNL. Many operations in the B695 Segment are performed under a Resource Conservation and Recovery Act (RCRA) operation plan, similar to commercial treatment operations with best demonstrated available technologies. The buildings of the B695 Segment were designed and built considering such operations, using proven building systems, and keeping

  19. EM Health and Safety Plan Guidelines

    Energy Technology Data Exchange (ETDEWEB)

    1994-12-01

    This document contains information about the Health and Safety Plan Guidelines. Topics discussed include: Regulatory framework; key personnel; hazard assessment; training requirements; personal protective equipment; extreme temperature disorders or conditions; medical surveillance; exposure monitoring/air sampling; site control; decontamination; emergency response/contingency plan; emergency action plan; confined space entry; and spill containment.

  20. Research on the Evaluation System for Rural Public Safety Planning

    Institute of Scientific and Technical Information of China (English)

    Ming; SUN; Jianxin; YAN

    2014-01-01

    The indicator evaluation system is introduced to the study of rural public safety planning in this article.By researching the current rural public safety planning and environmental carrying capacity,we select some carrying capacity indicators influencing the rural public safety,such as land,population,ecological environment,water resources,infrastructure,economy and society,to establish the environmental carrying capacity indicator system.We standardize the indicators,use gray correlation analysis method to determine the weight of indicators,and make DEA evaluation of the indicator system,to obtain the evaluation results as the basis for decision making in rural safety planning,and provide scientific and quantified technical support for rural public safety planning.

  1. Software quality assurance plans for safety-critical software

    International Nuclear Information System (INIS)

    Liddle, P.

    2006-01-01

    Application software is defined as safety-critical if a fault in the software could prevent the system components from performing their nuclear-safety functions. Therefore, for nuclear-safety systems, the AREVA TELEPERM R XS (TXS) system is classified 1E, as defined in the Inst. of Electrical and Electronics Engineers (IEEE) Std 603-1998. The application software is classified as Software Integrity Level (SIL)-4, as defined in IEEE Std 7-4.3.2-2003. The AREVA NP Inc. Software Program Manual (SPM) describes the measures taken to ensure that the TELEPERM XS application software attains a level of quality commensurate with its importance to safety. The manual also describes how TELEPERM XS correctly performs the required safety functions and conforms to established technical and documentation requirements, conventions, rules, and standards. The program manual covers the requirements definition, detailed design, integration, and test phases for the TELEPERM XS application software, and supporting software created by AREVA NP Inc. The SPM is required for all safety-related TELEPERM XS system applications. The program comprises several basic plans and practices: 1. A Software Quality-Assurance Plan (SQAP) that describes the processes necessary to ensure that the software attains a level of quality commensurate with its importance to safety function. 2. A Software Safety Plan (SSP) that identifies the process to reasonably ensure that safety-critical software performs as intended during all abnormal conditions and events, and does not introduce any new hazards that could jeopardize the health and safety of the public. 3. A Software Verification and Validation (V and V) Plan that describes the method of ensuring the software is in accordance with the requirements. 4. A Software Configuration Management Plan (SCMP) that describes the method of maintaining the software in an identifiable state at all times. 5. A Software Operations and Maintenance Plan (SO and MP) that

  2. High-temperature gas-cooled reactor safety-reliability program plan

    Energy Technology Data Exchange (ETDEWEB)

    1981-03-01

    The purpose of this document is to present a safety plan as part of an overall program plan for the design and development of the High Temperature Gas-Cooled Reactor (HTGR). This plan is intended to establish a logical framework for identifying the technology necessary to demonstrate that the requisite degree of public risk safety can be achieved economically. This plan provides a coherent system safety approach together with goals and success criterion as part of a unifying strategy for licensing a lead reactor plant in the near term. It is intended to provide guidance to program participants involved in producing a technology base for the HTGR that is fully responsive to safety consideration in the design, evaluation, licensing, public acceptance, and economic optimization of reactor systems.

  3. Safety and health five-year plan, Fiscal years 1995--1999

    International Nuclear Information System (INIS)

    1994-10-01

    This report describes efforts by the Department of Energy (DOE) to size and allocate funding to safety and health activities that protect workers and the public from harm. Although it is well recognized that virtually every aspect of an operation has health and safety implications, this effort is directed at identifying planned efforts specifically directed at health and safety. The initial effort, to compile information for the period covering FY 1994--1998, served two primary needs: (1) to document what was actually taking place in the DOE Complex, from a budget and resource utilization standpoint (how the complex was reacting to the calls for greater protection for workers and the public); and (2) to embark on an effort to utilize forward-looking management plans to allocate resources to meet safety and health needs (to begin to be proactive). It was recognized that it would take several years to achieve full acceptance and implementation of a single, DOE-wide approach toward planning for safety and health, and to develop plans that emphasized the benefits from both risk management and accident prevention strategies. This report, describing safety and health plans and budgets for FY 1995, reflects the increasing acceptance of risk-based strategies in the development of safety and health plans. More operations are using the prioritization methodology recommended for the safety and health planning process, and more operations have begun to review planned expenditures of resources to better assure that resources are allocated to the highest risk reduction activities

  4. Health and safety plan for operations performed for the Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    Trippet, W.A. II (IT Corp., (United States)); Reneau, M.; Morton, S.L. (EG and G Idaho, Inc., Idaho Falls, ID (United States))

    1992-04-01

    This document constitutes the generic health and safety plan for the Environmental Restoration Program (ERP). It addresses the health and safety requirements of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA); Occupational Safety and Health Administration (OSHA) 29 CFR 1910.120 standard; and EG G Idaho, Inc. This plan is a guide to individuals who must complete a health and safety plan for a task performed for the EPR. It contains a task specific addendum that, when completed, specifically addresses task specific health and safety issues. This health and safety plan reduces the time it takes to write a task specific health and safety plan by providing discussions of requirements, guidance on where specific information is located, and specific topics in the Addendum that must be discussed at a task level. This format encourages a complete task specific health and safety plan and a standard for all health and safety plans written for ERP.

  5. Health and safety plan for operations performed for the Environmental Restoration Program

    International Nuclear Information System (INIS)

    Trippet, W.A. II; Reneau, M.; Morton, S.L.

    1992-04-01

    This document constitutes the generic health and safety plan for the Environmental Restoration Program (ERP). It addresses the health and safety requirements of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA); Occupational Safety and Health Administration (OSHA) 29 CFR 1910.120 standard; and EG ampersand G Idaho, Inc. This plan is a guide to individuals who must complete a health and safety plan for a task performed for the EPR. It contains a task specific addendum that, when completed, specifically addresses task specific health and safety issues. This health and safety plan reduces the time it takes to write a task specific health and safety plan by providing discussions of requirements, guidance on where specific information is located, and specific topics in the Addendum that must be discussed at a task level. This format encourages a complete task specific health and safety plan and a standard for all health and safety plans written for ERP

  6. Nuclear safety research master plan

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Jae Joo; Yang, J. U.; Jun, Y. S. and others

    2001-06-01

    The SRMP (Safety Research Master Plan) is established to cope with the changes of nuclear industry environments. The tech. tree is developed according to the accident progress of the nuclear reactor. The 11 research fields are derived to cover the necessary technologies to ensure the safety of nuclear reactors. Based on the developed tech. tree, the following four main research fields are derived as the main safety research areas: 1. Integrated nuclear safety enhancement, 2. Thermal hydraulic experiment and assessment, 3. Severe accident management and experiment, and 4. The integrity of equipment and structure. The research frame and strategies are also recommended to enhance the efficiency of research activity, and to extend the applicability of research output.

  7. Task Group on Safety Margins Action Plan (SMAP). Safety Margins Action Plan - Final Report

    International Nuclear Information System (INIS)

    Hrehor, Miroslav; Gavrilas, Mirela; Belac, Josef; Sairanen, Risto; Bruna, Giovanni; Reocreux, Michel; Touboul, Francoise; Krzykacz-Hausmann, B.; Park, Jong Seuk; Prosek, Andrej; Hortal, Javier; Sandervaag, Odbjoern; Zimmerman, Martin

    2007-01-01

    The international nuclear community has expressed concern that some changes in existing plants could challenge safety margins while fulfilling all the regulatory requirements. In 1998, NEA published a report by the Committee on Nuclear Regulatory Activities on Future Nuclear Regulatory Challenges. The report recognized 'Safety margins during more exacting operating modes' as a technical issue with potential regulatory impact. Examples of plant changes that can cause such exacting operating modes include power up-rates, life extension or increased fuel burnup. In addition, the community recognized that the cumulative effects of simultaneous changes in a plant could be larger than the accumulation of the individual effects of each change. In response to these concerns, CSNI constituted the safety margins action plan (SMAP) task group with the following objectives: 'To agree on a framework for integrated assessments of the changes to the overall safety of the plant as a result of simultaneous changes in plant operation / condition; To develop a CSNI document which can be used by member countries to assess the effect of plant change on the overall safety of the plant; To share information and experience.' The two approaches to safety analysis, deterministic and probabilistic, use different methods and have been developed mostly independently of each other. This makes it difficult to assure consistency between them. As the trend to use information on risk (where the term risk means results of the PSA/PRA analysis) to support regulatory decisions is growing in many countries, it is necessary to develop a method of evaluating safety margin sufficiency that is applicable to both approaches and, whenever possible, integrated in a consistent way. Chapter 2 elaborates on the traditional view of safety margins and the means by which they are currently treated in deterministic analyses. This chapter also discusses the technical basis for safety limits as they are used today

  8. HAL/S-360 compiler test activity report

    Science.gov (United States)

    Helmers, C. T.

    1974-01-01

    The levels of testing employed in verifying the HAL/S-360 compiler were as follows: (1) typical applications program case testing; (2) functional testing of the compiler system and its generated code; and (3) machine oriented testing of compiler implementation on operational computers. Details of the initial test plan and subsequent adaptation are reported, along with complete test results for each phase which examined the production of object codes for every possible source statement.

  9. 47 CFR 3.60 - Reports.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 1 2010-10-01 2010-10-01 false Reports. 3.60 Section 3.60 Telecommunication... MARITIME AND MARITIME MOBILE-SATELLITE RADIO SERVICES Reporting Requirements § 3.60 Reports. (a) Initial... authority is required to submit to the FCC a report on additions, modifications or deletions to its list of...

  10. 49 CFR 1106.4 - The Safety Integration Plan process.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 8 2010-10-01 2010-10-01 false The Safety Integration Plan process. 1106.4 Section 1106.4 Transportation Other Regulations Relating to Transportation (Continued) SURFACE... CONSIDERATION OF SAFETY INTEGRATION PLANS IN CASES INVOLVING RAILROAD CONSOLIDATIONS, MERGERS, AND ACQUISITIONS...

  11. Russian Minatom nuclear safety research strategic plan. An international review

    International Nuclear Information System (INIS)

    Royen, J.

    1999-01-01

    An NEA study on safety research needs of Russian-designed reactors, carried out in 1996, strongly recommended that a strategic plan for safety research be developed with respect to Russian nuclear power plants. Such a plan was developed at the Russian International Nuclear Safety Centre (RINSC) of the Russian Ministry of Atomic Energy (Minatom). The Strategic Plan is designed to address high-priority safety-research needs, through a combination of domestic research, the application of appropriate foreign knowledge, and collaboration. It represents major progress toward developing a comprehensive and coherent safety-research programme for Russian nuclear power plants (NPPs). The NEA undertook its review of the Strategic Plan with the objective of providing independent verification on the scope, priority, and content of the research described in the Plan based upon the experience of the international group of experts. The principal conclusions of the review and the general comments of the NEA group are presented. (K.A.)

  12. Role of nuclear safety research and future plan

    International Nuclear Information System (INIS)

    Kim, W. S.; Lee, J. I.; Kang, S. C.; Park, Y. W.; Lee, J. H.; Kim, M. W.; Lee, C. J.; Park, Y. I.

    2000-01-01

    For promoting and improving nuclear safety research activities, this report gives an insight on the scope of safety research and its role in the safety management of nuclear installations, and suggests measures to adequately utilize the research results through taking an optimized role share among research organizations. Several measures such as cooperative planning of common research areas and proper role assignment, improvement of the interfaces among researchers, and reflection of end-users' opinion in the course of planning and conducting research to promote application of research results are identified. It is expected that the identified measures will contribute to enhancing the efficiency and effectiveness of nuclear safety research, if they are implemented after deliberating with the government and safety research organizations

  13. 14 CFR Appendix B of Part 415 - Safety Review Document Outline

    Science.gov (United States)

    2010-01-01

    ... Performance Graphs 2.0Launch Operator Organization (§ 415.111) 2.1Launch Operator Organization (§ 415.111 and... Plan 4.3.1Flight Safety Personnel 4.3.2Flight Safety Rules 4.3.3Flight Safety System Summary and... Instrumentation Plan 6.2Configuration Management and Control Plan 6.3Frequency Management Plan 6.4Flight...

  14. 12 CFR 308.303 - Filing of safety and soundness compliance plan.

    Science.gov (United States)

    2010-01-01

    ... time within which those steps will be taken. (c) Review of safety and soundness compliance plans... PRACTICE RULES OF PRACTICE AND PROCEDURE Submission and Review of Safety and Soundness Compliance Plans and... compliance plan. (a) Schedule for filing compliance plan—(1) In general. A bank shall file a written safety...

  15. Supporting Fernald Site Closure with Integrated Health and Safety Plans as Documented Safety Analyses

    International Nuclear Information System (INIS)

    Kohler, S.; Brown, T.; Fisk, P.; Krach, F.; Klein, B.

    2004-01-01

    At the Fernald Closure Project (FCP) near Cincinnati, Ohio, environmental restoration activities are supported by Documented Safety Analyses (DSAs) that combine the required project-specific Health and Safety Plans, Safety Basis Requirements (SBRs), and Process Requirements (PRs) into single Integrated Health and Safety Plans (I-HASPs). These integrated DSAs employ Integrated Safety Management methodology in support of simplified restoration and remediation activities that, so far, have resulted in the decontamination and demolition (D and D) of over 200 structures, including eight major nuclear production plants. There is one of twelve nuclear facilities still remaining (Silos containing uranium ore residues) with its own safety basis documentation. This paper presents the status of the FCP's safety basis documentation program, illustrating that all of the former nuclear facilities and activities have now replaced. Basis of Interim Operations (BIOs) with I-HASPs as their safety basis during the closure process

  16. Certification plan for safety and PRA codes

    International Nuclear Information System (INIS)

    Toffer, H.; Crowe, R.D.; Ades, M.J.

    1990-05-01

    A certification plan for computer codes used in Safety Analyses and Probabilistic Risk Assessment (PRA) for the operation of the Savannah River Site (SRS) reactors has been prepared. An action matrix, checklists, and a time schedule have been included in the plan. These items identify what is required to achieve certification of the codes. A list of Safety Analysis and Probabilistic Risk Assessment (SA ampersand PRA) computer codes covered by the certification plan has been assembled. A description of each of the codes was provided in Reference 4. The action matrix for the configuration control plan identifies code specific requirements that need to be met to achieve the certification plan's objectives. The checklist covers the specific procedures that are required to support the configuration control effort and supplement the software life cycle procedures based on QAP 20-1 (Reference 7). A qualification checklist for users establishes the minimum prerequisites and training for achieving levels of proficiency in using configuration controlled codes for critical parameter calculations

  17. UMTRA project office federal employee occupational safety and health program plan

    International Nuclear Information System (INIS)

    1994-06-01

    This document establishes the Federal Employee Occupational Safety and Health (FEOSH) Program for the US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project Office. This program will ensure compliance with applicable requirements of DOE Order 3790.1B and DOE Albuquerque Operations Office (AL) Order 3790.lA. FEOSH Program responsibilities delegated by the DOE-AL to the UMTRA Project Office by AL Order 3790.1A also are assigned. The UMTRA Project Office has developed the UMTRA Project Environmental, Safety, and Health (ES ampersand H) Plan (DOE, 1992), which establishes the basic programmatic ES ampersand H requirements for all participants on the UMTRA Project. The ES ampersand H plan is designed primarily to cover remedial action activities at UMTRA sites and defines the ES ampersand H responsibilities of both the UMTRA Project Office and its contractors. The UMTRA FEOSH Program described herein is a subset of the overall UMTRA ES ampersand H program and covers only federal employees working on the UMTRA Project

  18. Spent Nuclear Fuel Project Safety Management Plan

    International Nuclear Information System (INIS)

    Garvin, L.J.

    1996-02-01

    The Spent Nuclear Fuel Project Safety Management Plan describes the new nuclear facility regulatory requirements basis for the Spemt Nuclear Fuel (SNF) Project and establishes the plan to achieve compliance with this basis at the new SNF Project facilities

  19. Sanitation health risk and safety planning in urban residential ...

    African Journals Online (AJOL)

    The aim of this review paper was to determine the best sanitation health risk and safety planning approach for sustainable management of urban environment. This was achieved by reviewing the concept of sanitation safety planning as a tool. The review adopted exploratory research approach and used secondary data ...

  20. The Norwegian Plan of Action for nuclear safety issues

    International Nuclear Information System (INIS)

    1997-07-01

    The Plan of Action underlies Norwegian activities in the field of international co-operation to enhance nuclear safety and prevent radioactive contamination from activities in Eastern Europe and the former Soviet Union. Geographically the highest priority has been given to support for safety measures in north-west Russia. This information brochure outlines the main content of the Plan of Action for nuclear safety issues and lists a number of associated measures and projects

  1. The Norwegian Plan of Action for nuclear safety issues

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-07-01

    The Plan of Action underlies Norwegian activities in the field of international co-operation to enhance nuclear safety and prevent radioactive contamination from activities in Eastern Europe and the former Soviet Union. Geographically the highest priority has been given to support for safety measures in north-west Russia. This information brochure outlines the main content of the Plan of Action for nuclear safety issues and lists a number of associated measures and projects.

  2. 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

  3. 360° tunable microwave phase shifter based on silicon-on-insulator dual-microring resonator

    DEFF Research Database (Denmark)

    Pu, Minhao; Xue, Weiqi; Liu, Liu

    2010-01-01

    We demonstrate tunable microwave phase shifters based on electrically tunable silicon-on-insulator dual-microring resonators. A quasi-linear phase shift of 360° with ~2dB radio frequency power variation at a microwave frequency of 40GHz is obtained......We demonstrate tunable microwave phase shifters based on electrically tunable silicon-on-insulator dual-microring resonators. A quasi-linear phase shift of 360° with ~2dB radio frequency power variation at a microwave frequency of 40GHz is obtained...

  4. 78 FR 51754 - Request To Modify License by Replacing Security Plan With New Radiation Safety Plan; U.S...

    Science.gov (United States)

    2013-08-21

    ... Replacing Security Plan With New Radiation Safety Plan; U.S. Department of the Army, Jefferson Proving... security plan with a new radiation safety plan. DATES: Submit comments by September 20, 2013. Requests for.... The proposed change is to modify License Condition No. 12 D which refers to the security plan of...

  5. Safety research plan, JFY 2013 edition

    International Nuclear Information System (INIS)

    2013-09-01

    As for the regulatory issues the governments or JNES considered necessary, JNES had updated every year 'safety research plan' in respective research areas necessary for solving the regulatory issues (safety research needs) and was conducting safety research to obtain the results, etc. 'Safety research plan, JFY 2013 Edition' was compiled aiming at promotion of appropriate reflection and flexible application of research achievements for tacking the regulatory issues taking account of importance and urgency dependent on trend of nuclear safety regulations as well as collective management of safety research and safety survey. 5 new research projects were established with 4 unified research projects and 6 terminated research projects. Finally modified safety research areas, subjects and research projects, JFY 2013 Edition were as follows: design review of nuclear power plant (7 subjects and each subject having several research projects totaled 19), control management of nuclear power plant (one subject having 4 research projects), nuclear fuel cycle (2 subjects and each subject having several research projects totaled 4), nuclear fuel cycle backend (2 subjects and each subject having several research projects totaled 5), nuclear emergency preparedness and response (3 subjects and each subject having several research projects totaled 7) and bases of nuclear safety technology (3 subjects and each subject having several research projects totaled 6). Safety reviews consisted of 6 projects in 3 areas extracting the regulatory issues. As for urgent research projects on the basis of the disaster at Fukushima Daiichi NPP accident, 7 research projects in 4 urgent subjects were as follows: examination for new safety regulation (4 research projects generalized in the above research projects), development of newly necessary evaluation methods (one research project generalized in the above research project), evaluation of the validity for the work for convergence at Fukushima

  6. Safety plan for the cooperative telerobotic retrieval system equipment development area

    Energy Technology Data Exchange (ETDEWEB)

    Haney, T.J.; Jessmore, J.J.

    1995-07-01

    This plan establishes guidelines to minimize safety risks for the cooperative telerobotic retrieval project at the North Boulevard Annex (NBA). This plan has the dual purpose of minimizing safety risks to workers and visitors and of securing sensitive equipment from inadvertent damage by nonqualified personnel. This goal will be accomplished through physical control of work zones and through assigned responsibilities for project personnel. The scope of this plan is limited to establishing the working zone boundaries and entry requirements, and assigning responsibilities for project personnel. This plan does not supersede current safety organization responsibilities for the Landfill Stabilization Focus Area Transuranic (LSFA TRU) Arid outlined in the Environment, Safety, Health, and Quality Plan for the Buried Waste Integrated Demonstration Program; Tenant Manual; Idaho Falls Building Emergency Control Plan;; applicable Company Procedures; the attached Interface Agreement (Appendix A).

  7. Safety plan for the cooperative telerobotic retrieval system equipment development area

    International Nuclear Information System (INIS)

    Haney, T.J.; Jessmore, J.J.

    1995-07-01

    This plan establishes guidelines to minimize safety risks for the cooperative telerobotic retrieval project at the North Boulevard Annex (NBA). This plan has the dual purpose of minimizing safety risks to workers and visitors and of securing sensitive equipment from inadvertent damage by nonqualified personnel. This goal will be accomplished through physical control of work zones and through assigned responsibilities for project personnel. The scope of this plan is limited to establishing the working zone boundaries and entry requirements, and assigning responsibilities for project personnel. This plan does not supersede current safety organization responsibilities for the Landfill Stabilization Focus Area Transuranic (LSFA TRU) Arid outlined in the Environment, Safety, Health, and Quality Plan for the Buried Waste Integrated Demonstration Program; Tenant Manual; Idaho Falls Building Emergency Control Plan;; applicable Company Procedures; the attached Interface Agreement (Appendix A)

  8. 42 CFR 137.360 - Does the Secretary approve project planning and design documents prepared by the Self-Governance...

    Science.gov (United States)

    2010-10-01

    ... design documents prepared by the Self-Governance Tribe? 137.360 Section 137.360 Public Health PUBLIC... HUMAN SERVICES TRIBAL SELF-GOVERNANCE Construction Roles of the Secretary in Establishing and... documents prepared by the Self-Governance Tribe? The Secretary shall have at least one opportunity to...

  9. 49 CFR 244.11 - Contents of a Safety Integration Plan.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 4 2010-10-01 2010-10-01 false Contents of a Safety Integration Plan. 244.11 Section 244.11 Transportation Other Regulations Relating to Transportation (Continued) FEDERAL RAILROAD ADMINISTRATION, DEPARTMENT OF TRANSPORTATION REGULATIONS ON SAFETY INTEGRATION PLANS GOVERNING RAILROAD...

  10. Hospital 360°.

    Science.gov (United States)

    Giraldo Valencia, Juan Carlos; Delgado, Liliana Claudia

    2015-01-01

    There are forces that are greater than the individual performance of each hospital institution and of the health system structural of each country. The world is changing and to face up to the future in the best possible way, we need to understand how contexts and emerging trends link up and how they affect the hospital sector. The Columbian Association of Hospitals and Clinics, ACHC, has thus come up with the Hospital 360° concept which uses hospitals capable of anticipating changing contexts by means of the transition between present and future and takes on board the experience of global, socio-economic, demographic, political, environmental and technological fields as its model. Hospital 360° is an invitation to reinvent processes and institution themselves allowing them to adapt and incorporate a high degree of functional flexibility. Hospital 360° purses goals of efficiency, effectiveness and relevance, but also of impact and sustainability, and is coherent with the internal needs of hospital institutions and society for long-term benefits.

  11. 19 CFR 360.102 - Online registration.

    Science.gov (United States)

    2010-04-01

    ... 19 Customs Duties 3 2010-04-01 2010-04-01 false Online registration. 360.102 Section 360.102... ANALYSIS SYSTEM § 360.102 Online registration. (a) In general. (1) Any importer, importing company, customs.... boxes will not be accepted. A user identification number will be issued within two business days...

  12. Sign up to Safety: developing a safety improvement plan.

    Science.gov (United States)

    Dight, Carol; Peters, Hayley

    2015-04-01

    The Sign up to Safety (SutS) programme was launched in June 2014 by health secretary Jeremy Hunt. It focuses on listening to patients, carers and staff, learning from what they say when things go wrong, and then taking action to improve patient safety. The programme aims to make the NHS the safest healthcare system in the world by creating a culture devoted to continuous learning and improvement (NHS England 2014). Musgrove Park Hospital, part of Taunton and Somerset NHS Foundation Trust, was one of 12 NHS organisations that signed up to the SutS programme, making public its commitment to the national pledges to be 'open and transparent' and to develop a safety improvement plan. This paper describes the development of the strategy.

  13. IAEA Sets Up Team to Drive Nuclear Safety Action Plan

    International Nuclear Information System (INIS)

    2011-01-01

    Full text: The International Atomic Energy Agency is setting up a Nuclear Safety Action Team to oversee prompt implementation of the IAEA Action Plan on Nuclear Safety and ensure proper coordination among all stakeholders. The 12-point Action Plan, drawn up in the wake of the Fukushima Daiichi accident, was approved by the Agency's Board of Governors on 13 September and endorsed by all 151 Member States at its General Conference last week. The team will work within the Agency's Department of Nuclear Safety and Security, headed by Deputy Director General Denis Flory, and will coordinate closely with the Director General's Office for Policy. ''The Action Plan requires immediate follow-up,'' Director General Yukiya Amano said. ''This compact, dedicated team will assist Deputy Director General Flory in implementing the measures agreed in the Action Plan.'' Gustavo Caruso, Head of the Regulatory Activities Section in the IAEA's Division of Installation Safety, has been designated as the team's Special Coordinator for the implementation of the Action Plan. The IAEA has already started implementing its responsibilities under the Action Plan, including development of an IAEA methodology for stress tests for nuclear power plants. The methodology will be ready in October. (IAEA)

  14. 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

  15. 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.

  16. 40 CFR 98.360 - Definition of the source category.

    Science.gov (United States)

    2010-07-01

    ... this rule. (b) A manure management system (MMS) is a system that stabilizes and/or stores livestock... (CONTINUED) MANDATORY GREENHOUSE GAS REPORTING Manure Management § 98.360 Definition of the source category. (a) This source category consists of livestock facilities with manure management systems that emit 25...

  17. Validation and verification plan for safety and PRA codes

    International Nuclear Information System (INIS)

    Ades, M.J.; Crowe, R.D.; Toffer, H.

    1991-04-01

    This report discusses a verification and validation (V ampersand V) plan for computer codes used for safety analysis and probabilistic risk assessment calculations. The present plan fulfills the commitments by Westinghouse Savannah River Company (WSRC) to the Department of Energy Savannah River Office (DOE-SRO) to bring the essential safety analysis and probabilistic risk assessment codes in compliance with verification and validation requirements

  18. Hawaii State Plan for Occupational Safety and Health. Final rule.

    Science.gov (United States)

    2012-09-21

    This document announces the Occupational Safety and Health Administration's (OSHA) decision to modify the Hawaii State Plan's ``final approval'' determination under Section 18(e) of the Occupational Safety and Health Act (the Act) and to transition to ``initial approval'' status. OSHA is reinstating concurrent federal enforcement authority over occupational safety and health issues in the private sector, which have been solely covered by the Hawaii State Plan since 1984.

  19. Cesium legacy safety project management work plan

    International Nuclear Information System (INIS)

    Durham, J.S.

    1998-01-01

    This Management Work Plan (MWP) describes the process flow, quality assurance controls, and the Environment, Safety, and Health requirements of the Cesium Legacy Safety Project. This MWP provides an overview of the project goals and methods for repackaging the non-conforming Type W overpacks and packaging the CsCl powder and pellets. This MWP is not intended to apply to other activities associated with the CsCl Legacy Safety Program (i.e., clean out of South Cell)

  20. Environment, Safety, Health and Waste Management Plan

    International Nuclear Information System (INIS)

    1988-01-01

    The mission of the Feed Materials Production Center (FMPC) is the production of high qaulity uranium metal for use by the US Department of Energy (DOE) in Defense Programs. In order to accomplish this mission and to maintain the FMPC as a viable facility in the DOE production complex, the facility must be brought into full compliance with all federal and state regulations and industry standards for environmental protection and worker safety. Where past practices have resulted in environmental insult, a comprehensive program of remediation must be implemented. The purpose of this combined Environment, Safety, Health and Waste Management Plan is to provide a road map for achieving needed improvements. The plan is structured to provide a comprehensive projection from the current fiscal year (FY) through FY 1994 of the programs, projects and funding required to achieve compliance. To do this, the plan is subdivided into chapters which discuss the applicable regulations;project schedules and funding requirements;details of the various programs for environment, safety, health and waste management;details of the ongoing National Environmental Policy Act (NEPA);the quality assurance program and the environmental monitoring program. 14 refs., 30 figs., 29 tabs

  1. 77 FR 42462 - Hawaii State Plan for Occupational Safety and Health; Proposed Modification of 18(e) Plan Approval

    Science.gov (United States)

    2012-07-19

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration 29 CFR Part 1952 [Docket ID. OSHA 2012-0029] RIN 1218-AC78 Hawaii State Plan for Occupational Safety and Health; Proposed Modification of 18(e) Plan Approval AGENCY: Occupational Safety and Health Administration (OSHA), Department of...

  2. 12 CFR 30.4 - Filing of safety and soundness compliance plan.

    Science.gov (United States)

    2010-01-01

    ... steps the bank will take to correct the deficiency and the time within which those steps will be taken. (c) Review of safety and soundness compliance plans. Within 30 days after receiving a safety and... AND SOUNDNESS STANDARDS § 30.4 Filing of safety and soundness compliance plan. (a) Schedule for filing...

  3. Simplifying documentation while approaching site closure: integrated health and safety plans as documented safety analysis

    International Nuclear Information System (INIS)

    Brown, Tulanda

    2003-01-01

    At the Fernald Closure Project (FCP) near Cincinnati, Ohio, environmental restoration activities are supported by Documented Safety Analyses (DSAs) that combine the required project-specific Health and Safety Plans, Safety Basis Requirements (SBRs), and Process Requirements (PRs) into single Integrated Health and Safety Plans (I-HASPs). By isolating any remediation activities that deal with Enriched Restricted Materials, the SBRs and PRs assure that the hazard categories of former nuclear facilities undergoing remediation remain less than Nuclear. These integrated DSAs employ Integrated Safety Management methodology in support of simplified restoration and remediation activities that, so far, have resulted in the decontamination and demolition (D and D) of over 150 structures, including six major nuclear production plants. This paper presents the FCP method for maintaining safety basis documentation, using the D and D I-HASP as an example

  4. Yearly plan of safety research on environmental radioactivity for 1996 - 2000

    International Nuclear Information System (INIS)

    1996-01-01

    'Yearly Plan of Safety Research on Environmental Radioactivity' proposed from the special meeting for safety research of environmental radioactivity on December 14, 1995 was investigated by Nuclear Safety Commission. And the safety research of environmental radioactivity in Japan was decided to be pursued according to the plan. The contents of this plan consisted of the purpose and the contents of research as well as the research period and the facilities to be done for each theme. The following themes were included; 1) study on environment·radiation dose and study on radiation exposure reduction. 2) study on biological effects of radiation. 3) study on internal exposure by specified nuclides. 4) study on medical measures for acute radiation exposure. 5) study on assessment of nuclear safety. 6) investigation on radioactivities released from various nuclear facilities in Japan to demonstrate their safety. (M.N.)

  5. Committee on the safety of nuclear installations - Operating plan (2006 - 2009)

    International Nuclear Information System (INIS)

    2007-01-01

    In 2004, NEA issued its Strategic Plan covering the period 2005-2009, addressing the NEA activities associated with nuclear safety and regulation. Committee on the Safety of Nuclear Installations (CSNI) and Committee on Nuclear Regulatory Activities (CNRA), which have the primary responsibility for activities in this area, have developed and issued a joint strategic plan covering this same time period. As requested in the Joint Strategic Plan, each committee is to prepare an operating plan which describes in more detail the committee's organisation, planned activities, priorities and operating procedures to be used to implement the Joint Strategic Plan. In effect, the Joint Strategic Plan defines what type of work CSNI should do, whereas the Operating Plan describes the overall work scope and how to accomplish it to meet the joint CSNI/CNRA Strategic Plan objectives and mission. The present Operating Plan follows and takes into account the outcome of a CSNI assessment group, which has evaluated the CSNI activities. The assessment group expressed appreciation for the CSNI role and activity, while making recommendations with regards to scope of work and way to operate in order to further improve efficiency. The main objectives of CSNI are to: - Keep all member countries involved in and abreast of developments in safety technology. - Review operating experience with the objective to identify safety issues that need to be addressed by new research. - Review the state-of-knowledge on selected topics of nuclear safety technology and safety assessment. - Promote training and research projects that serve to maintain competence in nuclear safety matters. - Promote research as needed to reach consensus on nuclear safety issues of common interest. - Consider the safety implications of scientific and technical developments. To accomplish these objectives, CSNI is organised into six permanent working groups (as described in Section II), each covering a different set of

  6. 76 FR 17808 - Final Vehicle Safety Rulemaking and Research Priority Plan 2011-2013

    Science.gov (United States)

    2011-03-31

    ... [Docket No. NHTSA-2009-0108] Final Vehicle Safety Rulemaking and Research Priority Plan 2011- 2013 AGENCY... availability. SUMMARY: This document announces the availability of the Final NHTSA Vehicle Safety and Fuel.... This Priority Plan is an update to the Final Vehicle Safety Rulemaking and Research Priority Plan 2009...

  7. Hotelzon's B2B content marketing plan

    OpenAIRE

    Nguyen, Trang

    2015-01-01

    This thesis follows a research-based structure. The objective of this research was to help the case company Hotelzon develop a practical business-to-business (B2B) content marketing plan to engage new customers. The research topic came up when the case company named Hotelzon started expanding its business to many other countries. Therefore, attracting new prospects has become a critical issue to B2B corporates in this online world and constantly changing business environment. The first pa...

  8. Implementing 10 CFR 830 at the FEMP Silos: Nuclear Health and Safety Plans as Documented Safety Analysis

    International Nuclear Information System (INIS)

    Fisk, Patricia; Rutherford, Lavon

    2003-01-01

    The objective of the Silos Project at the Fernald Closure Project (FCP) is to safely remediate high-grade uranium ore residues (Silos 1 and 2) and metal oxide residues (Silo 3). The evolution of Documented Safety Analyses (DSAs) for these facilities has reflected the changes in remediation processes. The final stage in silos DSAs is an interpretation of 10 CFR 830 Safe Harbor Requirements that combines a Health and Safety Plan with nuclear safety requirements. This paper will address the development of a Nuclear Health and Safety Plan, or N-HASP

  9. 46 CFR 183.360 - Semiconductor rectifier systems.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Semiconductor rectifier systems. 183.360 Section 183.360... TONS) ELECTRICAL INSTALLATION Power Sources and Distribution Systems § 183.360 Semiconductor rectifier systems. (a) Each semiconductor rectifier system must have an adequate heat removal system that prevents...

  10. HAL/S-360-user's manual

    Science.gov (United States)

    Kole, R. E.; Helmers, P. H.; Hotz, R. L.

    1974-01-01

    This is a reference document to be used in the process of getting HAL/S programs compiled and debugged on the IBM 360 computer. Topics from the operating system communication to interpretation of debugging aids are discussed. Features of HAL programming system that have specific system/360 dependencies are presented.

  11. Overview of IAEA Action Plan on Nuclear Safety

    International Nuclear Information System (INIS)

    Monti, Stefano

    2012-01-01

    The IAEA Action Plan represents a work programme to strengthen and improve nuclear safety world wide. The plan identifies actions for Member States and the IAEA. Success depends upon: • Cooperation between IAEA, Member States, and other stakeholders; • Availability of appropriate financial resources (MS voluntary contributions)

  12. The evolving role and care management approaches of safety-net Medicaid managed care plans.

    Science.gov (United States)

    Gusmano, Michael K; Sparer, Michael S; Brown, Lawrence D; Rowe, Catherine; Gray, Bradford

    2002-12-01

    This article provides new empirical data about the viability and the care management activities of Medicaid managed-care plans sponsored by provider organizations that serve Medicaid and other low-income populations. Using survey and case study methods, we studied these "safety-net" health plans in 1998 and 2000. Although the number of safety-net plans declined over this period, the surviving plans were larger and enjoying greater financial success than the plans we surveyed in 1998. We also found that, based on a partnership with providers, safety-net plans are moving toward more sophisticated efforts to manage the care of their enrollees. Our study suggests that, with supportive state policies, safety-net plans are capable of remaining viable. Contracting with safety-net plans may not be an efficient mechanism for enabling Medicaid recipients to "enter the mainstream of American health care," but it may provide states with an effective way to manage and coordinate the care of Medicaid recipients, while helping to maintain the health care safety-net for the uninsured.

  13. 12 CFR 360.7 - Post-insolvency interest.

    Science.gov (United States)

    2010-01-01

    ... becomes proven. (4) Post-insolvency interest shall be determined using a simple interest method of... 12 Banks and Banking 4 2010-01-01 2010-01-01 false Post-insolvency interest. 360.7 Section 360.7... RESOLUTION AND RECEIVERSHIP RULES § 360.7 Post-insolvency interest. (a) Purpose and scope. This section...

  14. 12 CFR 360.1 - Least-cost resolution.

    Science.gov (United States)

    2010-01-01

    ... 12 Banks and Banking 4 2010-01-01 2010-01-01 false Least-cost resolution. 360.1 Section 360.1 Banks and Banking FEDERAL DEPOSIT INSURANCE CORPORATION REGULATIONS AND STATEMENTS OF GENERAL POLICY RESOLUTION AND RECEIVERSHIP RULES § 360.1 Least-cost resolution. (a) General rule. Except as provided in...

  15. Reactor safety research program. A description of current and planned reactor safety research sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research

    International Nuclear Information System (INIS)

    1975-06-01

    The reactor safety research program, sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, is described in terms of its program objectives, current status, and future plans. Elements of safety research work applicable to water reactors, fast reactors, and gas cooled reactors are presented together with brief descriptions of current and planned test facilities. (U.S.)

  16. A case study of IMRT planning (Plan B) subsequent to a previously treated IMRT plan (Plan A)

    International Nuclear Information System (INIS)

    2Department of Radiation Oncology, Fraser Valley Centre, BC Cancer Agency, Surrey, British Columbia (Canada))" data-affiliation=" (Department of Medical Physics and 2Department of Radiation Oncology, Fraser Valley Centre, BC Cancer Agency, Surrey, British Columbia (Canada))" >Cao, F; 2Department of Radiation Oncology, Fraser Valley Centre, BC Cancer Agency, Surrey, British Columbia (Canada))" data-affiliation=" (Department of Medical Physics and 2Department of Radiation Oncology, Fraser Valley Centre, BC Cancer Agency, Surrey, British Columbia (Canada))" >Leong, C; 2Department of Radiation Oncology, Fraser Valley Centre, BC Cancer Agency, Surrey, British Columbia (Canada))" data-affiliation=" (Department of Medical Physics and 2Department of Radiation Oncology, Fraser Valley Centre, BC Cancer Agency, Surrey, British Columbia (Canada))" >Schroeder, J; 2Department of Radiation Oncology, Fraser Valley Centre, BC Cancer Agency, Surrey, British Columbia (Canada))" data-affiliation=" (Department of Medical Physics and 2Department of Radiation Oncology, Fraser Valley Centre, BC Cancer Agency, Surrey, British Columbia (Canada))" >Lee, B

    2014-01-01

    Background and purpose: Treatment of the contralateral neck after previous ipsilateral intensity modulated radiation therapy (IMRT) for head and neck cancer is a challenging problem. We have developed a technique that limits the cumulative dose to the spinal cord and brainstem while maximizing coverage of a planning target volume (PTV) in the contralateral neck. Our case involves a patient with right tonsil carcinoma who was given ipsilateral IMRT with 70Gy in 35 fractions (Plan A). A left neck recurrence was detected 14 months later. The patient underwent a neck dissection followed by postoperative left neck radiation to a dose of 66 Gy in 33 fractions (Plan B). Materials and Methods: The spinal cord-brainstem margin (SCBM) was defined as the spinal cord and brainstem with a 1.0 cm margin. Plan A was recalculated on the postoperative CT scan but the fluence outside of SCBM was deleted. A further modification of Plan A resulted in a base plan that was summed with Plan B to evaluate the cumulative dose received by the spinal cord and brainstem. Plan B alone was used to evaluate for coverage of the contralateral neck PTV. Results: The maximum cumulative doses to the spinal cord with 0.5cm margin and brainstem with 0.5cm margin were 51.96 Gy and 45.60 Gy respectively. For Plan B, 100% of the prescribed dose covered 95% of PTVb1. Conclusion: The use of a modified ipsilateral IMRT plan as a base plan is an effective way to limit the cumulative dose to the spinal cord and brainstem while enabling coverage of a PTV in the contralateral neck.

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

    International Nuclear Information System (INIS)

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

    2000-05-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2000-05-01

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

  19. [Implementation of a safety and health planning system in a teaching hospital].

    Science.gov (United States)

    Mariani, F; Bravi, C; Dolcetti, L; Moretto, A; Palermo, A; Ronchin, M; Tonelli, F; Carrer, P

    2007-01-01

    University Hospital "L. Sacco" had started in 2006 a two-year project in order to set up a "Health and Safety Management System (HSMS)" referring to the technical guideline OHSAS 18001:1999 and the UNI and INAIL "Guidelines for a health and safety management system at workplace". So far, the following operations had been implemented: Setting up of a specific Commission within the Risk Management Committee; Identification and appointment of Departmental Representatives of HSMS; Carrying out of a training course addressed to Workers Representatives for Safety and Departmental Representatives of HSMS; Development of an Integrated Informative System for Prevention and Safety; Auditors qualification; Inspection of the Occupational Health Unit and the Prevention and Safety Service: reporting of critical situations and monitoring solutions adopted. Short term objectives are: Self-evaluation through check-lists of each department; Sharing of the Improvement Plan among the departments of the hospital; Planning of Health and Safety training activities in the framework of the Hospital Training Plan; Safety audit.

  20. A plan for safety and integrity of research reactor components

    International Nuclear Information System (INIS)

    Moatty, Mona S. Abdel; Khattab, M.S.

    2013-01-01

    Highlights: ► A plan for in-service inspection of research reactor components is put. ► Section XI of the ASME Code requirements is applied. ► Components subjected to inspection and their classes are defined. ► Flaw evaluation and its acceptance–rejection criteria are reviewed. ► A plan of repair or replacement is prepared. -- Abstract: Safety and integrity of a research reactor that has been operated over 40 years requires frequent and thorough inspection of all the safety-related components of the facility. The need of increasing the safety is the need of improving the reliability of its systems. Diligent and extensive planning of in-service inspection (ISI) of all reactor components has been imposed for satisfying the most stringent safety requirements. The Safeguards Officer's responsibilities of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code ASME Code have been applied. These represent the most extensive and time-consuming part of ISI program, and identify the components subjected to inspection and testing, methods of component classification, inspection and testing techniques, acceptance/rejection criteria, and the responsibilities. The paper focuses on ISI planning requirements for welded systems such as vessels, piping, valve bodies, pump casings, and control rod-housing parts. The weld in integral attachments for piping, pumps, and valves are considered too. These are taken in consideration of safety class (1, 2, 3, etc.), reactor age, and weld type. The parts involve in the frequency of inspection, the examination requirements for each inspection, the examination method are included. Moreover the flaw evaluation, the plan of repair or replacement, and the qualification of nondestructive examination personnel are considered

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

    Energy Technology Data Exchange (ETDEWEB)

    Kilmer, J.

    1997-08-01

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

  2. Safety Standards Plan for Middlesex County Vocational & Technical High Schools.

    Science.gov (United States)

    Sommer, Cy

    This vocational education safety standards plan outlines rules and regulations adopted by the Board of Education of Middlesex County Vocational and Technical High Schools. The first of eleven chapters presents demographics and a safety organization table for Middlesex County Vocational and Technical Schools. In chapter 2, six safety program…

  3. 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

  4. 49 CFR 1106.3 - Actions for which Safety Integration Plan is required.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 8 2010-10-01 2010-10-01 false Actions for which Safety Integration Plan is required. 1106.3 Section 1106.3 Transportation Other Regulations Relating to Transportation (Continued... TRANSPORTATION BOARD CONSIDERATION OF SAFETY INTEGRATION PLANS IN CASES INVOLVING RAILROAD CONSOLIDATIONS...

  5. 20 CFR 405.360 - Official record.

    Science.gov (United States)

    2010-04-01

    ... in making the decision under review and any additional evidence or written statements that the... 20 Employees' Benefits 2 2010-04-01 2010-04-01 false Official record. 405.360 Section 405.360 Employees' Benefits SOCIAL SECURITY ADMINISTRATION ADMINISTRATIVE REVIEW PROCESS FOR ADJUDICATING INITIAL...

  6. The advanced neutron source safety approach and plans

    International Nuclear Information System (INIS)

    Harrington, R.M.

    1989-01-01

    The Advanced Neutron Source (ANS) is a user facility for all areas of neutron research proposed for construction at the Oak Ridge National Laboratory. The neutron source is planned to be a 350-MW research reactor. The reactor, currently in conceptual design, will belong to the United States Department of Energy (USDOE). The safety approach and planned elements of the safety program for the ANS are described. The safety approach is to incorporate USDOE requirements [which, by reference, include appropriate requirements from the United States Nuclear Regulatory Commission (USNRC) and other national and state regulatory agencies] into the design, and to utilize probabilistic risk assessment (PRA) techniques during design to achieve extremely low probability of severe core damage. The PRA has already begun and will continue throughout the design and construction of the reactor. Computer analyses will be conducted for a complete spectrum of accidental events, from anticipated events to very infrequent occurrences. 8 refs., 2 tabs

  7. The Advanced Neutron Source safety approach and plans

    International Nuclear Information System (INIS)

    Harrington, R.M.

    1990-01-01

    The Advanced Neutron Source (ANS) is a user facility proposed for construction at the Oak Ridge National Laboratory for all areas of neutron research. The neutron source is planned to be a 350-MW research reactor. The reactor, currently in conceptual design, will belong to the United States Department of Energy (USDOE). The safety approach and planned elements of the safety program for the ANS are described. The safety approach is to incorporate USDOE requirements (which, by reference, include appropriate requirements from the United States Nuclear Regulatory Commission (USNRC) and other national and state regulatory agencies) into the design, and to utilize probabilistic risk assessment (PRA) techniques during design to achieve extremely low probability of severe core damage. The PRA has already begun and will continue throughout the design and construction of the reactor. Computer analyses will be conducted for a complete spectrum of accidental events, from anticipated events to very infrequent occurrences

  8. Russian MINATOM nuclear safety research strategic plan. An international review

    International Nuclear Information System (INIS)

    1999-03-01

    The 'Safety Research Strategic Plan for Russian Nuclear Power Plants' was published in draft form at the Russian International Nuclear Safety Centre (RINSC) by a working group of fifteen senior Russian experts. The Plan consists of 12 chapters, each addressing a specific technical area and containing a number of proposed research programmes and projects to advance the state-of-knowledge in that area. In part because a strong Recommendation to undertake such a Plan was made by the 1998 OECD/NEA study, the OECD Nuclear Energy Agency was asked by the Director of RINSC and the Director of USINSC to organize an international review of the Plan when the English-language version became available in October, 1998. This report represents the results of that review. (R.P.)

  9. Safety assessment plans for authorization and inspection of radiation sources

    International Nuclear Information System (INIS)

    2002-05-01

    The objective of this TECDOC is to enhance the efficacy, quality and efficiency of the whole regulatory process. It provides advice on good practice administrative procedures for the regulatory process for preparation of applications, granting of authorizations, inspection, and enforcement. It also provides information on the development and use of standard safety assessment plans for authorization and inspection. The plans are intended to be used in conjunction with more detailed advice related to specific practices. In this sense, this TECDOC provides advice on a systematic approach to evaluations of protection and safety while other IAEA Safety Guides assist the user to distinguish between the acceptable and the unacceptable. This TECDOC covers administrative advice to facilitate the regulatory process governing authorization and inspection. It also covers the use of standard assessment and inspection plans and provides simplified plans for the more common, well established uses of radiation sources in medicine and industry, i.e. sources for irradiation facilities, industrial radiography, well logging, industrial gauging, unsealed sources in industry, X ray diagnosis, nuclear medicine, teletherapy and brachytherapy

  10. Safety assessment plans for authorization and inspection of radiation sources

    International Nuclear Information System (INIS)

    1999-09-01

    The objective of this TECDOC is to enhance the efficacy, quality and efficiency of the whole regulatory process. It provides advice on good practice administrative procedures for the regulatory process for preparation of applications, granting of authorizations, inspection, and enforcement. It also provides information on the development and use of standard safety assessment plans for authorization and inspection. The plans are intended to be used in conjunction with more detailed advice related to specific practices. In this sense, this TECDOC provides advice on a systematic approach to evaluations of protection and safety while other IAEA Safety Guides assist the user to distinguish between the acceptable and the unacceptable. This TECDOC covers administrative advice to facilitate the regulatory process governing authorization and inspection. It also covers the use of standard assessment and inspection plans and provides simplified plans for the more common, well established uses of radiation sources in medicine and industry, i.e. sources for irradiation facilities, industrial radiography, well logging, industrial gauging, unsealed sources in industry, X ray diagnosis, nuclear medicine, teletherapy and brachytherapy

  11. 37 CFR 360.4 - Compliance with statutory dates.

    Science.gov (United States)

    2010-07-01

    ... dates. 360.4 Section 360.4 Patents, Trademarks, and Copyrights COPYRIGHT ROYALTY BOARD, LIBRARY OF CONGRESS SUBMISSION OF ROYALTY CLAIMS FILING OF CLAIMS TO ROYALTY FEES COLLECTED UNDER COMPULSORY LICENSE Cable Claims § 360.4 Compliance with statutory dates. (a) Claims filed with the Copyright Royalty Board...

  12. 37 CFR 360.24 - Compliance with statutory dates.

    Science.gov (United States)

    2010-07-01

    ... dates. 360.24 Section 360.24 Patents, Trademarks, and Copyrights COPYRIGHT ROYALTY BOARD, LIBRARY OF CONGRESS SUBMISSION OF ROYALTY CLAIMS FILING OF CLAIMS TO ROYALTY FEES COLLECTED UNDER COMPULSORY LICENSE Digital Audio Recording Devices and Media Royalty Claims § 360.24 Compliance with statutory dates. (a...

  13. 37 CFR 360.13 - Compliance with statutory dates.

    Science.gov (United States)

    2010-07-01

    ... dates. 360.13 Section 360.13 Patents, Trademarks, and Copyrights COPYRIGHT ROYALTY BOARD, LIBRARY OF CONGRESS SUBMISSION OF ROYALTY CLAIMS FILING OF CLAIMS TO ROYALTY FEES COLLECTED UNDER COMPULSORY LICENSE Satellite Claims § 360.13 Compliance with statutory dates. (a) Claims filed with the Copyright Royalty Board...

  14. Planning and evaluation of plant under safety aspects

    International Nuclear Information System (INIS)

    Strnad, H.

    1985-01-01

    Plant denotes a technical product characterized as being structured, complex, comprising the use of energy, and that of measuring, automatic control and monitoring systems to keep track of present, control and monitor processes. Particular attention is paid to methods of developing plant concepts, measures to exclude or detect risks, integration of safety engineering into the course of planning, safety concept and ergonomics in plant design. (DG) [de

  15. 44 CFR 360.4 - Administrative procedures.

    Science.gov (United States)

    2010-10-01

    ... of training as well as costs of delivery and student travel and per diem are to be estimated. Special.... 360.4 Section 360.4 Emergency Management and Assistance FEDERAL EMERGENCY MANAGEMENT AGENCY...) Issuance of a request for application: Each State emergency management agency will receive a Request for...

  16. 46 CFR 185.360 - Use of auto pilot.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Use of auto pilot. 185.360 Section 185.360 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) SMALL PASSENGER VESSELS (UNDER 100 GROSS TONS) OPERATIONS Miscellaneous Operating Requirements § 185.360 Use of auto pilot. Whenever an automatic pilot is...

  17. Site Safety Plan for Lawrence Livermore National Laboratory CERCLA investigations

    Energy Technology Data Exchange (ETDEWEB)

    Bainer, R.; Duarte, J.

    1993-07-01

    The safety policy of LLNL is to take every reasonable precaution in the performance of work to protect the environment and the health and safety of employees and the public, and to prevent property damage. With respect to hazardous agents, this protection is provided by limiting human exposures, releases to the environment, and contamination of property to levels that are as low as reasonably achievable (ALARA). It is the intent of this Plan to supply the broad outline for completing environmental investigations within ALARA guidelines. It may not be possible to determine actual working conditions in advance of the work; therefore, planning must allow the opportunity to provide a range of protection based upon actual working conditions. Requirements will be the least restrictive possible for a given set of circumstances, such that work can be completed in an efficient and timely fashion. Due to the relatively large size of the LLNL Site and the different types of activities underway, site-specific Operational Safety Procedures (OSPs) will be prepared to supplement activities not covered by this Plan. These site-specific OSPs provide the detailed information for each specific activity and act as an addendum to this Plan, which provides the general plan for LLNL Main Site operation.

  18. 31 CFR 360.1 - Official agencies.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 2 2010-07-01 2010-07-01 false Official agencies. 360.1 Section 360.1 Money and Finance: Treasury Regulations Relating to Money and Finance (Continued) FISCAL SERVICE... Bank of Kansas City, 925 Grand Boulevard, Kansas City, MO 64106 Dallas, San Francisco, Kansas City, St...

  19. Void -spelprototyp för Xbox360 / Void -game prototype for Xbox360

    OpenAIRE

    Lindberg, Joakim; Gullbrandson, Fredrik; Nilsson, Bo Martin

    2008-01-01

    Detta examensarbete består utav av två delar, en produktionsdel och denna slutreflektion. Produktionsdelen varade i 15 veckor och gick ut på att utveckla en spelprototyp. Spelprototypen är ämnad för spelkonsolen Xbox360, som är den nya generationens tv-spel. För att kunna utveckla till denna konsol måste man använda sig av XNA, som är ett utvecklingsverktyg ämnat specifikt för Xbox360 och ett måste om man vill kunna utveckla till denna konsol som icke licensierad spelutvecklare. Denna rapport...

  20. MO-B-BRB-00: Optimizing the Treatment Planning Process

    International Nuclear Information System (INIS)

    2015-01-01

    The radiotherapy treatment planning process has evolved over the years with innovations in treatment planning, treatment delivery and imaging systems. Treatment modality and simulation technologies are also rapidly improving and affecting the planning process. For example, Image-guided-radiation-therapy has been widely adopted for patient setup, leading to margin reduction and isocenter repositioning after simulation. Stereotactic Body radiation therapy (SBRT) and Radiosurgery (SRS) have gradually become the standard of care for many treatment sites, which demand a higher throughput for the treatment plans even if the number of treatments per day remains the same. Finally, simulation, planning and treatment are traditionally sequential events. However, with emerging adaptive radiotherapy, they are becoming more tightly intertwined, leading to iterative processes. Enhanced efficiency of planning is therefore becoming more critical and poses serious challenge to the treatment planning process; Lean Six Sigma approaches are being utilized increasingly to balance the competing needs for speed and quality. In this symposium we will discuss the treatment planning process and illustrate effective techniques for managing workflow. Topics will include: Planning techniques: (a) beam placement, (b) dose optimization, (c) plan evaluation (d) export to RVS. Planning workflow: (a) import images, (b) Image fusion, (c) contouring, (d) plan approval (e) plan check (f) chart check, (g) sequential and iterative process Influence of upstream and downstream operations: (a) simulation, (b) immobilization, (c) motion management, (d) QA, (e) IGRT, (f) Treatment delivery, (g) SBRT/SRS (h) adaptive planning Reduction of delay between planning steps with Lean systems due to (a) communication, (b) limited resource, (b) contour, (c) plan approval, (d) treatment. Optimizing planning processes: (a) contour validation (b) consistent planning protocol, (c) protocol/template sharing, (d) semi

  1. MO-B-BRB-00: Optimizing the Treatment Planning Process

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2015-06-15

    The radiotherapy treatment planning process has evolved over the years with innovations in treatment planning, treatment delivery and imaging systems. Treatment modality and simulation technologies are also rapidly improving and affecting the planning process. For example, Image-guided-radiation-therapy has been widely adopted for patient setup, leading to margin reduction and isocenter repositioning after simulation. Stereotactic Body radiation therapy (SBRT) and Radiosurgery (SRS) have gradually become the standard of care for many treatment sites, which demand a higher throughput for the treatment plans even if the number of treatments per day remains the same. Finally, simulation, planning and treatment are traditionally sequential events. However, with emerging adaptive radiotherapy, they are becoming more tightly intertwined, leading to iterative processes. Enhanced efficiency of planning is therefore becoming more critical and poses serious challenge to the treatment planning process; Lean Six Sigma approaches are being utilized increasingly to balance the competing needs for speed and quality. In this symposium we will discuss the treatment planning process and illustrate effective techniques for managing workflow. Topics will include: Planning techniques: (a) beam placement, (b) dose optimization, (c) plan evaluation (d) export to RVS. Planning workflow: (a) import images, (b) Image fusion, (c) contouring, (d) plan approval (e) plan check (f) chart check, (g) sequential and iterative process Influence of upstream and downstream operations: (a) simulation, (b) immobilization, (c) motion management, (d) QA, (e) IGRT, (f) Treatment delivery, (g) SBRT/SRS (h) adaptive planning Reduction of delay between planning steps with Lean systems due to (a) communication, (b) limited resource, (b) contour, (c) plan approval, (d) treatment. Optimizing planning processes: (a) contour validation (b) consistent planning protocol, (c) protocol/template sharing, (d) semi

  2. 46 CFR 122.360 - Use of auto pilot.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 4 2010-10-01 2010-10-01 false Use of auto pilot. 122.360 Section 122.360 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) SMALL PASSENGER VESSELS CARRYING MORE THAN 150... Requirements § 122.360 Use of auto pilot. Whenever an automatic pilot is used the master shall ensure that: (a...

  3. Stress Tests Worldwide - IAEA Nuclear Safety Action Plan

    International Nuclear Information System (INIS)

    Lyons, J.E.

    2012-01-01

    The IAEA nuclear safety action plan relies on 11 important issues. 1) Safety assessments in light of the Fukushima accident: the IAEA secretariat will develop a methodology for stress tests against specific extreme natural hazards and will provide assistance for their implementation; 2) Strengthen existing IAEA peer reviews; 3) Emergency preparedness and response; 4) National Regulatory bodies in terms of independence and adequacy of human and financial resources; 5) The development of safety culture and scientific and technical capacity in Operating Organizations; 6) The upgrading of IAEA safety standards in a more efficient way; 7) A better implementation of relevant conventions concerning nuclear safety and nuclear accidents; 8) To provide a broad assistance on safety standard for countries embarking on a nuclear power program; 9) To facilitate the use of available information, expertise and techniques concerning radiation protection; 10) To enhance the transparency of nuclear industry; and 11) To promote the cooperation between member states in nuclear safety. (A.C.)

  4. Status of safety issues at licensed power plants: TMI action plan requirements, unresolved safety issues, generic safety issues

    International Nuclear Information System (INIS)

    1991-12-01

    As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, a program was established whereby an annual NUREG report would be published on the status of licensee implementation and NRC verification of safety issues in major NRC requirements areas. This information was compiled and reported in three NUREG volumes. Volume 1, published in March 1991, addressed the status of of Three Mile Island (TMI) Action Plan Requirements. Volume 2, published in May 1991, addressed the status of unresolved safety issues (USIs). Volume 3, published in June 1991, addressed the implementation and verification status of generic safety issues (GSIs). This annual NUREG report combines these volumes into a single report and provides updated information as of September 30, 1991. The data contained in these NUREG reports are a product of the NRC's Safety Issues Management System (SIMS) database, which is maintained by the Project Management Staff in the Office of Nuclear Reactor Regulation and by NRC regional personnel. This report is to provide a comprehensive description of the implementation and verification status of TMI Action Plan Requirements, safety issues designated as USIs, and GSIs that have been resolved and involve implementation of an action or actions by licensees. This report makes the information available to other interested parties, including the public. An additional purpose of this NUREG report is to serve as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues up until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees

  5. 77 FR 58488 - Hawaii State Plan for Occupational Safety and Health

    Science.gov (United States)

    2012-09-21

    ... DEPARTMENT OF LABOR Occupational Safety and Health Administration 29 CFR Part 1952 [Docket ID. OSHA 2012-0029] RIN 1218-AC78 Hawaii State Plan for Occupational Safety and Health AGENCY: Occupational... announces the Occupational Safety and Health Administration's (OSHA) decision to modify the Hawaii State...

  6. Work plan, health and safety plan, and site characterization for the Rust Spoil Area (D-106)

    International Nuclear Information System (INIS)

    Bohrman, D.E.; Uziel, M.S.; Landguth, D.C.; Hawthorne, S.W.

    1990-06-01

    As part of the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) of the Department of Energy's Y-12 Plant located in Oak Ridge, Tennessee, this work plan has been developed for the Rust Spoil Area (a solid waste disposal area). The work plan was developed by the Measurement Applications and Development Group (MAD) of the Health and Safety Research Division (HASRD) at Oak Ridge National Laboratory (ORNL) and will be implemented jointly by ORNL/MAD and the Y-12 Environmental Surveillance Section. This plan consists of four major sections: (1) a project description giving the scope and objectives of the investigation at the Rust Spoil Area; (2) field and sampling procedures describing sample documentation, soil sampling techniques, sample packaging and preservation, equipment decontamination, and disposal of investigation generated wastes; (3) sample analysis procedures detailing necessary analytical laboratory procedures to ensure the quality of chemical results from sample receipt through analysis and data reporting; and (4) a health and safety plan which describes general site hazards and particular hazards associated with specific tasks, assigns responsibilities, establishes personnel protection standards and mandatory safety procedures, and provides emergency information for contingencies that may arise during the course of field operations

  7. A report on developing a checklist to assess company plans focused on improving safety awareness, safe behaviour and safety culture: final report

    NARCIS (Netherlands)

    Steijger, N.; Starren, H.; Keus, M.; Gort, J.; Vervoort, M.

    2003-01-01

    This report describes the process of developing a checklist to asses company plans focused on improving safety awareness, safe behaviour and safety culture. These plans are part of a programme initiated by the Ministry of Social Affairs and Employment aiming at improving the safety performance of

  8. Safety issue resolution strategy plan for inactive miscellaneous underground storage tanks

    International Nuclear Information System (INIS)

    Wang, O.S.; Powers, T.B.

    1994-09-01

    The purpose of this strategy plan is to identify, confirm, and resolve safely issues associated with inactive miscellaneous underground storage tanks (MUSTs) using a risk-based priority approach. Assumptions and processes to assess potential risks and operational concerns are documented in this report. Safety issue priorities are ranked based on a number of considerations including risk ranking and cost effectiveness. This plan specifies work scope and recommends schedules for activities related to resolving safety issues, such as collecting historical data, searching for authorization documents, performing Unreviewed Safety Question (USQ) screening and evaluation, identifying safety issues, imposing operational controls and monitoring, characterizing waste contents, mitigating and resolving safety issues, and fulfilling other remediation requirements consistent with the overall Tank Waste Remediation System strategy. Recommendations for characterization and remediation are also recommended according to the order of importance and practical programmatic consideration

  9. Deliberate and Crisis Action Planning and Execution Segments Increment 2B (DCAPES Inc 2B)

    Science.gov (United States)

    2016-03-01

    2016 Major Automated Information System Annual Report Deliberate and Crisis Action Planning and Execution Segments Increment 2B (DCAPES Inc 2B...Information Program Name Deliberate and Crisis Action Planning and Execution Segments Increment 2B (DCAPES Inc 2B) DoD Component Air Force Responsible Office...been established. DCAPES Inc 2B 2016 MAR UNCLASSIFIED 4 Program Description Deliberate and Crisis Action Planning and Execution Segments (DCAPES) is

  10. Facility effluent monitoring plan for the B plant

    International Nuclear Information System (INIS)

    Lesser, J.E.

    1994-09-01

    A facility effluent monitoring plan is required by the U.S. Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438-1. This facility effluent monitoring plant assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated every three years

  11. K basins interim remedial action health and safety plan

    Energy Technology Data Exchange (ETDEWEB)

    DAY, P.T.

    1999-09-14

    The K Basins Interim Remedial Action Health and Safety Plan addresses the requirements of the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA), as they apply to the CERCLA work that will take place at the K East and K West Basins. The provisions of this plan become effective on the date the US Environmental Protection Agency issues the Record of Decision for the K Basins Interim Remedial Action, currently planned in late August 1999.

  12. Plan for safety case of spent fuel repository at Olkiluoto

    International Nuclear Information System (INIS)

    Vieno, T.; Ikonen, A.T.K.

    2005-02-01

    Posiva aims to present the Safety Case supporting the construction license application of the spent fuel repository at Olkiluoto by 2012. An outline and preliminary assessments will be presented in 2009. Interim reporting and an update of the Safety Case plan will be presented in 2006, as required by the authorities. The KBS-3 disposal concept aims at long-term isolation and containment of spent fuel assemblies in durable copper-iron canisters emplaced in a repository to be constructed at a depth between 400 and 600 metres in crystalline bedrock. By 2012, studies on the KBS-3 disposal concept and site investigations at Olkiluoto will have been continued over about thirty years. The construction of an underground rock characterisation facility (called ONKALO) was started in June 2004. The investigations are carried out in close cooperation with the Swedish SKB developing and assessing the same disposal concept at candidate sites, resembling Olkiluoto, at the other side of the Baltic Sea. A safety case is the synthesis of evidence, analyses and arguments that quantify and substantiate the safety, and the level of expert confidence in the safety, of a planned repository. Posiva's Safety Case will be organised in a portfolio including ten main reports, which will be periodically updated according the overall schedule presented in the plan. The Site report describing the present state and past evolution of the Olkiluoto site, as well as the disturbances caused by the construction of ONKALO and the first stage of the repository, forms the geoscientific basis of the Safety Case. The engineering basis is provided by the reports on the Characteristics of spent fuel, Canister design, and Repository design. The Process report containing descriptions and analyses of features, events and processes potentially affecting the disposal system, and the report on the Evolution of site and repository form the scientific basis of the Safety Case. The latter report will describe and

  13. 360-Degree Feedback Implementation Plan: Dean Position, Graduate School of Business and Public Policy, Naval Postgraduate School

    National Research Council Canada - National Science Library

    Morrison, Devin

    2002-01-01

    360-degree feedback is a personal development and appraisal tool designed to quantify the competencies and skills of fellow employees by tapping the collective experience of their superiors, subordinates, and peers...

  14. Virtual displays for 360-degree video

    Science.gov (United States)

    Gilbert, Stephen; Boonsuk, Wutthigrai; Kelly, Jonathan W.

    2012-03-01

    In this paper we describe a novel approach for comparing users' spatial cognition when using different depictions of 360- degree video on a traditional 2D display. By using virtual cameras within a game engine and texture mapping of these camera feeds to an arbitrary shape, we were able to offer users a 360-degree interface composed of four 90-degree views, two 180-degree views, or one 360-degree view of the same interactive environment. An example experiment is described using these interfaces. This technique for creating alternative displays of wide-angle video facilitates the exploration of how compressed or fish-eye distortions affect spatial perception of the environment and can benefit the creation of interfaces for surveillance and remote system teleoperation.

  15. School Climate: An Essential Component of a Comprehensive School Safety Plan

    Science.gov (United States)

    Stark, Heidi

    2017-01-01

    The intentional assessment and management of school climate is an essential component of a comprehensive school safety plan. The value of this preventive aspect of school safety is often diminished as schools invest resources in physical security measures as a narrowly focused effort to increase school safety (Addington, 2009). This dissertation…

  16. 31 CFR 360.48 - Restrictions on reissue; denominational exchange.

    Science.gov (United States)

    2010-07-01

    ...; denominational exchange. 360.48 Section 360.48 Money and Finance: Treasury Regulations Relating to Money and... GOVERNING DEFINITIVE UNITED STATES SAVINGS BONDS, SERIES I Reissue and Denominational Exchange § 360.48 Restrictions on reissue; denominational exchange. Reissue is not permitted solely to change denominations. ...

  17. Breckinridge Project, initial effort. Report VII, Volume 4. Safety and health plan

    Energy Technology Data Exchange (ETDEWEB)

    None

    1982-01-01

    The Safety and Health Plan recognizes the potential hazards associated with the Project and has been developed specifically to respond to these risks in a positive manner. Prevention, the primary objective of the Plan, starts with building safety controls into the process design and continues through engineering, construction, start-up, and operation of the Project facilities and equipment. Compliance with applicable federal, state, and local health and safety laws, regulations, and codes throughout all Project phases is required and assured. The Plan requires that each major Project phase be thoroughly reviewed and analyzed to determine that those provisions required to assure the safety and health of all employees and the public, and to prevent property and equipment losses, have been provided. The Plan requires followup on those items or situations where corrective action needs were identified to assure that the action was taken and is effective. Emphasis is placed on loss prevention. Exhibit 1 provides a breakdown of Ashland Synthetic Fuels, Inc.'s (ASFI's) Loss Prevention Program. The Plan recognizes that the varied nature of the work is such as to require the services of skilled, trained, and responsible personnel who are aware of the hazards and know that the work can be done safely, if done correctly. Good operating practice is likewise safe operating practice. Training is provided to familiarize personnel with good operational practice, the general sequence of activities, reporting requirements, and above all, the concept that each step in the operating procedures must be successfully concluded before the following step can be safely initiated. The Plan provides for periodic review and evaluation of all safety and loss prevention activities at the plant and departmental levels.

  18. 19 CFR 360.108 - Loss of electronic licensing privileges.

    Science.gov (United States)

    2010-04-01

    ... 19 Customs Duties 3 2010-04-01 2010-04-01 false Loss of electronic licensing privileges. 360.108 Section 360.108 Customs Duties INTERNATIONAL TRADE ADMINISTRATION, DEPARTMENT OF COMMERCE STEEL IMPORT MONITORING AND ANALYSIS SYSTEM § 360.108 Loss of electronic licensing privileges. Should Commerce determine...

  19. UMTRA Project: Environment, Safety, and Health Plan

    International Nuclear Information System (INIS)

    1995-02-01

    The US Department of Energy has prepared this UMTRA Project Environment, Safety, and Health (ES and H) Plan to establish the policy, implementing requirements, and guidance for the UMTRA Project. The requirements and guidance identified in this plan are designed to provide technical direction to UMTRA Project contractors to assist in the development and implementation of their ES and H plans and programs for UMTRA Project work activities. Specific requirements set forth in this UMTRA Project ES and H Plan are intended to provide uniformity to the UMTRA Project's ES and H programs for processing sites, disposal sites, and vicinity properties. In all cases, this UMTRA Project ES and H Plan is intended to be consistent with applicable standards and regulations and to provide guidance that is generic in nature and will allow for contractors' evaluation of site or contract-specific ES and H conditions. This plan specifies the basic ES and H requirements applicable to UMTRA Project ES and H programs and delineates responsibilities for carrying out this plan. DOE and contractor ES and H personnel are expected to exercise professional judgment and apply a graded approach when interpreting these guidelines, based on the risk of operations

  20. System Safety Program Plan for Project W-314, tank farm restoration and safe operations

    International Nuclear Information System (INIS)

    Boos, K.A.

    1996-01-01

    This System Safety Program Plan (SSPP) outlines the safety analysis strategy for project W-314, ''Tank Farm Restoration and Safe Operations.'' Project W-314 will provide capital improvements to Hanford's existing Tank Farm facilities, with particular emphasis on infrastructure systems supporting safe operation of the double-shell activities related to the project's conceptual Design Phase, but is planned to be updated and maintained as a ''living document'' throughout the life of the project to reflect the current safety analysis planning for the Tank Farm Restoration and Safe Operations upgrades. This approved W-314 SSPP provides the basis for preparation/approval of all safety analysis documentation needed to support the project

  1. 37 CFR 360.22 - Form and content of claims.

    Science.gov (United States)

    2010-07-01

    .... 360.22 Section 360.22 Patents, Trademarks, and Copyrights COPYRIGHT ROYALTY BOARD, LIBRARY OF CONGRESS SUBMISSION OF ROYALTY CLAIMS FILING OF CLAIMS TO ROYALTY FEES COLLECTED UNDER COMPULSORY LICENSE Digital Audio Recording Devices and Media Royalty Claims § 360.22 Form and content of claims. (a) Forms. (1...

  2. 10 CFR Appendix A to Subpart B of... - General Statement of Safety Basis Policy

    Science.gov (United States)

    2010-01-01

    ... at all levels. Performing work in accordance with the safety basis for a nuclear facility is the..., safety, and health into work planning and execution (48 CFR 970.5223-1, Integration of Environment, Safety and Health into Work Planning and Execution) and the DEAR clause on laws, regulations, and DOE...

  3. Our Journey to Summon and 360: The KAUST experience

    KAUST Repository

    Ramli, Rindra M.

    2017-09-12

    Depicts the journey undertaken by KAUST (King Abdullah University of Science and Technology), an international graduate research university located on the shores of the Red Sea, in implementing Summon as its new webscale discovery layer. We will also describe the implementation of 360 suite of products namely: 360 Core & 360 LINK, 360 Marc. The presentation will cover the early days of library’s foray into discovery layers and the difficulties faced by the library that gave the impetus to embark on the project to evaluate, assess and recommend for a new and robust discovery layer. On top of that, the presenters would elaborate the project timeline (which also include the implementation phase for Summon and 360 Core), the challenges faced by the project team and lessons learnt.

  4. 37 CFR 360.25 - Copies of claims.

    Science.gov (United States)

    2010-07-01

    ... Section 360.25 Patents, Trademarks, and Copyrights COPYRIGHT ROYALTY BOARD, LIBRARY OF CONGRESS SUBMISSION OF ROYALTY CLAIMS FILING OF CLAIMS TO ROYALTY FEES COLLECTED UNDER COMPULSORY LICENSE Digital Audio Recording Devices and Media Royalty Claims § 360.25 Copies of claims. A claimant shall, for each claim...

  5. The evolving role and care management approaches of safety-net medicaid managed care plans

    OpenAIRE

    Gusmano, Michael K.; Sparer, Michael S.; Brown, Lawrence D.; Rowe, Catherine; Gray, Bradford

    2002-01-01

    This article provides new empirical data about the viability and the care management activities of Medicaid managed-care plans sponsored by provider organizations that serve Medicaid and other low-income populations. Using survey and case study methods we studied these “safety-net” health plans in 1998 and 2000. Although the number of safety-net plans declined over this period, the surviving plans were larger and enjoying greater financial success than the plans we surveyed in 1998. We also f...

  6. Technical Safety Requirements for the B695 Segment

    Energy Technology Data Exchange (ETDEWEB)

    Laycak, D

    2008-09-11

    This document contains Technical Safety Requirements (TSRs) for the Radioactive and Hazardous Waste Management (RHWM) Division's B695 Segment of the Decontamination and Waste Treatment Facility (DWTF) at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the B695 Segment. The TSRs are derived from the Documented Safety Analysis (DSA) for the B695 Segment (LLNL 2007). The analysis presented there determined that the B695 Segment is a low-chemical hazard, Hazard Category 3, nonreactor nuclear facility. The TSRs consist primarily of inventory limits as well as controls to preserve the underlying assumptions in the hazard analyses. Furthermore, appropriate commitments to safety programs are presented in the administrative controls section of the TSRs. The B695 Segment (B695 and the west portion of B696) is a waste treatment and storage facility located in the northeast quadrant of the LLNL main site. The approximate area and boundary of the B695 Segment are shown in the B695 Segment DSA. Activities typically conducted in the B695 Segment include container storage, lab-packing, repacking, overpacking, bulking, sampling, waste transfer, and waste treatment. B695 is used to store and treat radioactive, mixed, and hazardous waste, and it also contains equipment used in conjunction with waste processing operations to treat various liquid and solid wastes. The portion of the building called Building 696 Solid Waste Processing Area (SWPA), also referred to as B696S in this report, is used primarily to manage solid radioactive, mixed, and hazardous waste. Operations specific to the SWPA include sorting and segregating waste, lab-packing, sampling, and crushing empty drums that previously contained waste. Furthermore, a Waste Packaging Unit will be permitted to treat hazardous and mixed waste. RHWM generally processes LLW with no, or extremely low, concentrations of transuranics (i.e., much less than 100 n

  7. Technical Safety Requirements for the B695 Segment

    International Nuclear Information System (INIS)

    Laycak, D.

    2008-01-01

    This document contains Technical Safety Requirements (TSRs) for the Radioactive and Hazardous Waste Management (RHWM) Division's B695 Segment of the Decontamination and Waste Treatment Facility (DWTF) at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the B695 Segment. The TSRs are derived from the Documented Safety Analysis (DSA) for the B695 Segment (LLNL 2007). The analysis presented there determined that the B695 Segment is a low-chemical hazard, Hazard Category 3, nonreactor nuclear facility. The TSRs consist primarily of inventory limits as well as controls to preserve the underlying assumptions in the hazard analyses. Furthermore, appropriate commitments to safety programs are presented in the administrative controls section of the TSRs. The B695 Segment (B695 and the west portion of B696) is a waste treatment and storage facility located in the northeast quadrant of the LLNL main site. The approximate area and boundary of the B695 Segment are shown in the B695 Segment DSA. Activities typically conducted in the B695 Segment include container storage, lab-packing, repacking, overpacking, bulking, sampling, waste transfer, and waste treatment. B695 is used to store and treat radioactive, mixed, and hazardous waste, and it also contains equipment used in conjunction with waste processing operations to treat various liquid and solid wastes. The portion of the building called Building 696 Solid Waste Processing Area (SWPA), also referred to as B696S in this report, is used primarily to manage solid radioactive, mixed, and hazardous waste. Operations specific to the SWPA include sorting and segregating waste, lab-packing, sampling, and crushing empty drums that previously contained waste. Furthermore, a Waste Packaging Unit will be permitted to treat hazardous and mixed waste. RHWM generally processes LLW with no, or extremely low, concentrations of transuranics (i.e., much less than 100 n

  8. Safety research basic plan of JNC

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    Japan Nuclear Cycle Development Institute (JNC) formally succeeded to Power Reactor and Nuclear Fuel Development Corporation (PNC) on October, 1 1998. This report describes the basic plan for major program of JNC which consists of two parts: management philosophy of the new institute and the latest revised medium term program. In the first part, the primary mission of JNC is to perform its R and D concentrating on fast breeder reactor and its fuel cycle, and treatment and disposal of high-level radioactive wastes, while at the same time giving special consideration to safety. In the second, individual programs in the new basic plan are discussed in detail. The outline and schedule of each program are also attached in the table form. (H. Itami)

  9. 24 CFR 1006.360 - Conflict of interest.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 4 2010-04-01 2010-04-01 false Conflict of interest. 1006.360... DEVELOPMENT NATIVE HAWAIIAN HOUSING BLOCK GRANT PROGRAM Program Requirements § 1006.360 Conflict of interest. In the procurement of property and services by the DHHL and contractors, the conflict of interest...

  10. Therapeutic risk management of the suicidal patient: safety planning.

    Science.gov (United States)

    Matarazzo, Bridget B; Homaifar, Beeta Y; Wortzel, Hal S

    2014-05-01

    This column is the fourth in a series describing a model for therapeutic risk management of the suicidal patient. Previous columns presented an overview of the therapeutic risk management model, provided recommendations for how to augment risk assessment using structured assessments, and discussed the importance of risk stratification in terms of both severity and temporality. This final column in the series discusses the safety planning intervention as a critical component of therapeutic risk management of suicide risk. We first present concerns related to the relatively common practice of using no-suicide contracts to manage risk. We then present the safety planning intervention as an alternative approach and provide recommendations for how to use this innovative strategy to therapeutically mitigate risk in the suicidal patient.

  11. Sodium Fast Reactor Safety and Licensing Research Plan

    International Nuclear Information System (INIS)

    Denman, Matthew; Lachance, Jeff; Sofu, Tanju; Wigeland, Roald; Flanagan, George; Bari, Robert

    2013-01-01

    Conclusions: The Sodium Fast Reactor Safety and Licensing Research Plan reports conclude a multi-year expert elicitation process. All information included in the studies are publicly available and the reports are UUR. These reports are intended to guide SFR researchers in the safety and licensing arena to important and outstanding issues Two (and a half) projects have been funded based on the recommendations in this report: • Modernization of SAS4A; • Incorporation of Contain/LMR with MELCOR; • (Data recovery at INL and PNNL)

  12. 31 CFR 360.61 - Payment after death.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 2 2010-07-01 2010-07-01 false Payment after death. 360.61 Section 360.61 Money and Finance: Treasury Regulations Relating to Money and Finance (Continued) FISCAL... after death. After the death of the ward, and at any time prior to the representative's discharge, the...

  13. 360 DEGREE PHOTOGRAPHY TO DOCUMENT and TRAIN and ORIENT PERSONNEL FOR DECONTAMINATION and DECOMMISSIONING

    International Nuclear Information System (INIS)

    LEBARON, G.J.

    2001-01-01

    360 o photo technology is being used to document conditions, especially hazardous conditions, at US. Department of Energy (DOE) facilities that are being closed. Traditional efforts to document the condition of rooms and cells, especially those difficult to enter due to the hazards present, using engineering drawings, documents, ''traditional flat'' photographs or videos, don't provide perspective. These miss items or quickly pan across areas of interest with little opportunity to study details. Therefore, it becomes necessary to make multiple entries into these hazardous areas resulting in work activities taking longer and increasing exposure and the risk of accidents. High-resolution digital cameras, in conjunction with software techniques, make possible 360 o photos that allow a person to look all around, up and down, and zoom in or out. The software provides the opportunity to attach other information to a 360 o photo such as sound files providing audio information; flat photos providing additional detail or information about what is behind a panel or around a comer; and text information which can be used to show radiological conditions or identify other hazards present but not readily visible. The software also allows other 360 o photos to be attached to create a virtual tour where the user can move from area to area or room to room. The user is able to stop, study and zoom in on areas of interest. A virtual tour of a building or room can be used for facility documentation, work planning and orientation, and training. Documentation is developed during facility closure so people involved in follow-on activities can gain a perspective of the area, focus on points of interest and discuss what they would do or how they would respond to and manage conditions. Decontamination and Decommissioning (D and D) planners and workers can make use of the tour to plan work and decide ahead of time, while looking at the areas of interest, what and how tasks will be performed

  14. Health and safety plan for the Environmental Restoration Program at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Clark, C. Jr.; Burman, S.N.; Cipriano, D.J. Jr.; Uziel, M.S.; Kleinhans, K.R.; Tiner, P.F.

    1994-08-01

    This Programmatic Health and Safety plan (PHASP) is prepared for the U.S. Department of Energy (DOE) Oak Ridge National Laboratory (ORNL) Environmental Restoration (ER) Program. This plan follows the format recommended by the U.S. Environmental Protection Agency (EPA) for remedial investigations and feasibility studies and that recommended by the EM40 Health and Safety Plan (HASP) Guidelines (DOE February 1994). This plan complies with the Occupational Safety and Health Administration (OSHA) requirements found in 29 CFR 1910.120 and EM-40 guidelines for any activities dealing with hazardous waste operations and emergency response efforts and with OSHA requirements found in 29 CFR 1926.65. The policies and procedures in this plan apply to all Environmental Restoration sites and activities including employees of Energy Systems, subcontractors, and prime contractors performing work for the DOE ORNL ER Program. The provisions of this plan are to be carried out whenever activities are initiated that could be a threat to human health or the environment. This plan implements a policy and establishes criteria for the development of procedures for day-to-day operations to prevent or minimize any adverse impact to the environment and personnel safety and health and to meet standards that define acceptable management of hazardous and radioactive materials and wastes. The plan is written to utilize past experience and best management practices to minimize hazards to human health and safety and to the environment from event such as fires, explosions, falls, mechanical hazards, or any unplanned release of hazardous or radioactive materials to air, soil, or surface water

  15. Health and safety plan for the Environmental Restoration Program at Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Clark, C. Jr.; Burman, S.N.; Cipriano, D.J. Jr.; Uziel, M.S.; Kleinhans, K.R.; Tiner, P.F.

    1994-08-01

    This Programmatic Health and Safety plan (PHASP) is prepared for the U.S. Department of Energy (DOE) Oak Ridge National Laboratory (ORNL) Environmental Restoration (ER) Program. This plan follows the format recommended by the U.S. Environmental Protection Agency (EPA) for remedial investigations and feasibility studies and that recommended by the EM40 Health and Safety Plan (HASP) Guidelines (DOE February 1994). This plan complies with the Occupational Safety and Health Administration (OSHA) requirements found in 29 CFR 1910.120 and EM-40 guidelines for any activities dealing with hazardous waste operations and emergency response efforts and with OSHA requirements found in 29 CFR 1926.65. The policies and procedures in this plan apply to all Environmental Restoration sites and activities including employees of Energy Systems, subcontractors, and prime contractors performing work for the DOE ORNL ER Program. The provisions of this plan are to be carried out whenever activities are initiated that could be a threat to human health or the environment. This plan implements a policy and establishes criteria for the development of procedures for day-to-day operations to prevent or minimize any adverse impact to the environment and personnel safety and health and to meet standards that define acceptable management of hazardous and radioactive materials and wastes. The plan is written to utilize past experience and best management practices to minimize hazards to human health and safety and to the environment from event such as fires, explosions, falls, mechanical hazards, or any unplanned release of hazardous or radioactive materials to air, soil, or surface water.

  16. Improving School Improvement: Development and Validation of the CSIS-360, a 360-Degree Feedback Assessment for School Improvement Specialists

    Science.gov (United States)

    McDougall, Christie M.

    2013-01-01

    The purpose of the mixed methods study was to develop and validate the CSIS-360, a 360-degree feedback assessment to measure competencies of school improvement specialists from multiple perspectives. The study consisted of eight practicing school improvement specialists from a variety of settings. The specialists nominated 23 constituents to…

  17. Status of safety issues at licensed power plants: TMI Action Plan requirements; unresolved safety issues; generic safety issues; other multiplant action issues

    International Nuclear Information System (INIS)

    1993-12-01

    As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, the NRC established a program for publishing an annual report on the status of licensee implementation and NRC verification of safety issues in major NRC requirements areas. This information was initially compiled and reported in three NUREG-series volumes. Volume 1, published in March 1991, addressed the status of Three Mile Island (TMI) Action Plan Requirements. Volume 2, published in May 1991, addressed the status of unresolved safety issues (USIs). Volume 3, published in June 1991, addressed the implementation and verification status of generic safety issues (GSIs). The first annual supplement, which combined these volumes into a single report and presented updated information as of September 30, 1991, was published in December 1991. The second annual supplement, which provided updated information as of September 30, 1992, was published in December 1992. Supplement 2 also provided the status of licensee implementation and NRC verification of other multiplant action (MPA) issues not related to TMI Action Plan requirements, USIs, or GSIs. This third annual NUREG report, Supplement 3, presents updated information as of September 30, 1993. This report gives a comprehensive description of the implementation and verification status of TMI Action Plan requirements, safety issues designated as USIs, GSIs, and other MPAs that have been resolved and involve implementation of an action or actions by licensees. This report makes the information available to other interested parties, including the public. Additionally, this report serves as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees

  18. Implementation plan for the Defense Nuclear Facilities Safety Board Recommendation 90-7

    International Nuclear Information System (INIS)

    Borsheim, G.L.; Cash, R.J.; Dukelow, G.T.

    1992-12-01

    This document revises the original plan submitted in March 1991 for implementing the recommendations made by the Defense Nuclear Facilities Safety Board in their Recommendation 90-7 to the US Department of Energy. Recommendation 90-7 addresses safety issues of concern for 24 single-shell, high-level radioactive waste tanks containing ferrocyanide compounds at the Hanford Site. The waste in these tanks is a potential safety concern because, under certain conditions involving elevated temperatures and low concentrations of nonparticipating diluents, ferrocyanide compounds in the presence of oxidizing materials can undergo a runaway (propagating) chemical reaction. This document describes those activities underway by the Hanford Site contractor responsible for waste tank safety that address each of the six parts of Defense Nuclear Facilities Safety Board Recommendation 90-7. This document also identifies the progress made on these activities since the beginning of the ferrocyanide safety program in September 1990. Revised schedules for planned activities are also included

  19. Tank waste remediation system nuclear criticality safety inspection and assessment plan

    International Nuclear Information System (INIS)

    VAIL, T.S.

    1999-01-01

    This plan provides a management approved procedure for inspections and assessments of sufficient depth to validate that the Tank Waste Remediation System (TWRS) facility complies with the requirements of the Project Hanford criticality safety program, NHF-PRO-334, ''Criticality Safety General, Requirements''

  20. The safety analysis of realization of the stabilization of beams B1/B2 supports project

    International Nuclear Information System (INIS)

    Aleshin, A.M.; Batij, V.G.; Glukhen'kij, V.N.; Kozoriz, V.I.; Klyuchnikov, A.A.; Kochnev, N.A.; Pavlovskij, L.I.; Rubezhanskij, Yu.I.; Sidorenko, N.V.; Stoyanov, A.I.; Shcherbin, V.N.

    2000-01-01

    The results of the analysis of radiation safety executed at preparing for realization of the stabilization of beams B1/B2 support are given. The comparison of results of the preliminary analysis of safety with the data received during realization of works is carried out

  1. LMFBR safety experiment facility planning and analysis

    International Nuclear Information System (INIS)

    Stevenson, M.G.; Scott, J.H.

    1976-01-01

    In the past two years considerable effort has been placed on the planning and design of new facilities for the resolution of LMFBR safety issues. The paper reviews the key issues, the experiments needed to resolve them, and the design aspects of proposed new facilities. In addition, it presents a decision theory approach to selecting an optimal combination of modified and new facilities

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

    International Nuclear Information System (INIS)

    Johanson, Gunnar; Holmberg, J.

    1994-01-01

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

  3. A Template Analysis of Intimate Partner Violence Survivors' Experiences of Animal Maltreatment: Implications for Safety Planning and Intervention.

    Science.gov (United States)

    Collins, Elizabeth A; Cody, Anna M; McDonald, Shelby Elaine; Nicotera, Nicole; Ascione, Frank R; Williams, James Herbert

    2018-03-01

    This study explores the intersection of intimate partner violence (IPV) and animal cruelty in an ethnically diverse sample of 103 pet-owning IPV survivors recruited from community-based domestic violence programs. Template analysis revealed five themes: (a) Animal Maltreatment by Partner as a Tactic of Coercive Power and Control, (b) Animal Maltreatment by Partner as Discipline or Punishment of Pet, (c) Animal Maltreatment by Children, (d) Emotional and Psychological Impact of Animal Maltreatment Exposure, and (e) Pets as an Obstacle to Effective Safety Planning. Results demonstrate the potential impact of animal maltreatment exposure on women and child IPV survivors' health and safety.

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

    International Nuclear Information System (INIS)

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

    1994-09-01

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

  5. Implementing national nuclear safety plan at the preliminary stage of nuclear power project development

    International Nuclear Information System (INIS)

    Xue Yabin; Cui Shaozhang; Pan Fengguo; Zhang Lizhen; Shi Yonggang

    2014-01-01

    This study discusses the importance of nuclear power project design and engineering methods at the preliminary stage of its development on nuclear power plant's operational safety from the professional view. Specifically, we share our understanding of national nuclear safety plan's requirement on new reactor accident probability, technology, site selection, as well as building and improving nuclear safety culture and strengthening public participation, with a focus on plan's implications on preliminary stage of nuclear power project development. Last, we introduce China Huaneng Group's work on nuclear power project preliminary development and the experience accumulated during the process. By analyzing the siting philosophy of nuclear power plant and the necessity of building nuclear safety culture at the preliminary stage of nuclear power project development, this study explicates how to fully implement the nuclear safety plan's requirements at the preliminary stage of nuclear power project development. (authors)

  6. 37 CFR 360.23 - Content of notices regarding independent administrators.

    Science.gov (United States)

    2010-07-01

    ... independent administrators. 360.23 Section 360.23 Patents, Trademarks, and Copyrights COPYRIGHT ROYALTY BOARD, LIBRARY OF CONGRESS SUBMISSION OF ROYALTY CLAIMS FILING OF CLAIMS TO ROYALTY FEES COLLECTED UNDER COMPULSORY LICENSE Digital Audio Recording Devices and Media Royalty Claims § 360.23 Content of notices...

  7. 20 CFR 416.360 - Cancellation of a request to withdraw.

    Science.gov (United States)

    2010-04-01

    ....360 Section 416.360 Employees' Benefits SOCIAL SECURITY ADMINISTRATION SUPPLEMENTAL SECURITY INCOME FOR THE AGED, BLIND, AND DISABLED Filing of Applications Withdrawal of Application § 416.360... received after we have approved the withdrawal, the cancellation request is filed no later than 60 days...

  8. Evaluation of immunogenicity and safety of Genevac B: A new recombinant hepatitis b vaccine in comparison with Engerix B and Shanvac B in healthy adults

    Directory of Open Access Journals (Sweden)

    Vijayakumar V

    2004-01-01

    Full Text Available PURPOSE: Genevac B, a new indigenous recombinant hepatitis B vaccine was evaluated for its immunogenicity and safety in comparison with Engerix B (Smithkline Beecham Biologicals, Belgium and Shanvac B (Shantha Biotechnics, India in healthy adult volunteers. METHODS: While 240 study subjects were included in the Genevac B group, 80 each were the subjects for Engerix B and Shanvac B. A three dose regimen of 0,1,2 months was adopted with 20 gm dosage uniformly in all the three groups. Vaccinees were assessed during prevaccination, followup and post vaccination periods for clinical, haematological, biochemical and immunological parameters for safety and immunogenicity. RESULTS: Successful follow-up in all parameters for four months could be achieved in 92.5% (222/240 for Genevac B study subjects and the same was 85% (68/80 and 80% (64/80 for Engerix B and Shanvac B respectively. While 100% seroconversion was observed in all the three groups, the rate of seroprotectivity was 99.5% by Genevac B, 98.5% by Engerix B and 98.4% for Shanvac B. However the difference was not statistically significant (p>0.05. The GMT values of anti HBs after one month of completion of the vaccination were 735.50, 718.23 and 662.20 mIU/mL respectively. No systemic reaction was either seen or reported by the volunteers during the vaccination process of Genevac B and other two vaccines. Clinical, haematological and biochemical safety parameters remained within normal limits throughout the study period. CONCLUSION: The study confirms that Genevac B, the new recombinant Hepatitis B vaccine has the acceptable international standards of safety and immunogenicity.

  9. 360° Operative Videos: A Randomised Cross-Over Study Evaluating Attentiveness and Information Retention.

    Science.gov (United States)

    Harrington, Cuan M; Kavanagh, Dara O; Wright Ballester, Gemma; Wright Ballester, Athena; Dicker, Patrick; Traynor, Oscar; Hill, Arnold; Tierney, Sean

    2017-11-06

    Although two-dimensional (2D) and three-dimensional videos have traditionally provided foundations for reviewing operative procedures, the recent 360º format may provide new dimensions to surgical education. This study sought to describe the production of a high quality 360º video for an index-operation (augmented with educational material), while evaluating for variances in attentiveness, information retention, and appraisal compared to 2D. A 6-camera synchronised array (GoPro Omni, [California, United States]) was suspended inverted and recorded an elective laparoscopic cholecystectomy in 2016. A single-blinded randomised cross-over study was performed to evaluate this video in 360º vs 2D formats. Group A experienced the 360º video using Samsung (Suwon, South-Korea) GearVR virtual-reality headsets, followed by the 2D experience on a 75-inch television. Group B were reversed. Each video was probed at designated time points for engagement levels and task-unrelated images or thoughts. Alternating question banks were administered following each video experience. Feedback was obtained via a short survey at study completion. The New Academic and Education Building (NAEB) in Dublin, Royal College of Surgeons in Ireland, July 2017. Preclinical undergraduate students from a medical university in Ireland. Forty students participated with a mean age of 23.2 ± 4.5 years and equal sex involvement. The 360º video demonstrated significantly higher engagement (p video as their learning platform of choice. Mean appraisal levels for the 360º platform were positive with mean responses of >8/10 for the platform for learning, immersion, and entertainment. This study describes the successful development and evaluation of a 360º operative video. This new video format demonstrated significant engagement and attentiveness benefits compared to traditional 2D formats. This requires further evaluation in the field of technology enhanced learning. Copyright © 2017 Association of

  10. Work Plans 2011 – Norwegian Scientific Committee for Food Safety

    OpenAIRE

    Norwegian Scientific Committee for Food Safety

    2011-01-01

    The annual work plan for 2011 summaries activities for the Scientific Steering Committee and the 9 panels of the Norwegian Scientific Committee for Food Safety (VKM). VKM carries out independent risk assessments for the Norwegian Food Safety Authority across the Authority’s field of responsibility as well as environmental risk assessments of genetically modified organisms for the Directorate for Nature Management.

  11. Developing 360 degree feedback system for KINS

    Energy Technology Data Exchange (ETDEWEB)

    Han, In Soo; Cheon, B. M.; Kim, T. H.; Ryu, J. H. [Chungman National Univ., Daejeon (Korea, Republic of)

    2003-12-15

    This project aims to investigate the feasibility of a 360 degree feedback systems for KINS and to design guiding rules and structures in implementing that systems. Literature survey, environmental analysis and questionnaire survey were made to ensure that 360 degree feedback is the right tool to improve performance in KINS. That review leads to conclusion that more readiness and careful feasibility review are needed before implementation of 360 degree feedback in KINS. Further the project suggests some guiding rules that can be helpful for successful implementation of that system in KINS. Those include : start with development, experiment with one department, tie it to a clear organization's goal, train everyone involve, make sure to try that system in an atmosphere of trust.

  12. Developing 360 degree feedback system for KINS

    International Nuclear Information System (INIS)

    Han, In Soo; Cheon, B. M.; Kim, T. H.; Ryu, J. H.

    2003-12-01

    This project aims to investigate the feasibility of a 360 degree feedback systems for KINS and to design guiding rules and structures in implementing that systems. Literature survey, environmental analysis and questionnaire survey were made to ensure that 360 degree feedback is the right tool to improve performance in KINS. That review leads to conclusion that more readiness and careful feasibility review are needed before implementation of 360 degree feedback in KINS. Further the project suggests some guiding rules that can be helpful for successful implementation of that system in KINS. Those include : start with development, experiment with one department, tie it to a clear organization's goal, train everyone involve, make sure to try that system in an atmosphere of trust

  13. 48 CFR 952.223-71 - Integration of environment, safety, and health into work planning and execution.

    Science.gov (United States)

    2010-10-01

    ..., safety, and health into work planning and execution. 952.223-71 Section 952.223-71 Federal Acquisition... Provisions and Clauses 952.223-71 Integration of environment, safety, and health into work planning and... safety and health standards applicable to the work conditions of contractor and subcontractor employees...

  14. 31 CFR 360.22 - Payment or reissue pursuant to divorce.

    Science.gov (United States)

    2010-07-01

    ... divorce. 360.22 Section 360.22 Money and Finance: Treasury Regulations Relating to Money and Finance... divorce. (a) Divorce. (1) The Department of the Treasury will recognize a divorce decree that ratifies or.... (2) The evidence required under § 360.23 must be submitted in every case. When the divorce decree...

  15. 42 CFR 495.360 - Software and ownership rights.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 5 2010-10-01 2010-10-01 false Software and ownership rights. 495.360 Section 495.360 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) STANDARDS AND CERTIFICATION STANDARDS FOR THE ELECTRONIC HEALTH RECORD TECHNOLOGY INCENTIVE...

  16. RISMC Advanced Safety Analysis Project Plan – FY 2015 - FY 2019

    Energy Technology Data Exchange (ETDEWEB)

    Szilard, Ronaldo H. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Smith, Curtis L. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Youngblood, Robert [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-09-01

    In this report, a project plan is developed, focused on industry applications, using Risk-Informed Safety Margin Characterization (RISMC) tools and methods applied to realistic, relevant, and current interest issues to the operating nuclear fleet. RISMC focuses on modernization of nuclear power safety analysis (tools, methods and data); implementing state-of-the-art modeling techniques (which include, for example, enabling incorporation of more detailed physics as they become available); taking advantage of modern computing hardware; and combining probabilistic and mechanistic analyses to enable a risk informed safety analysis process. The modernized tools will maintain the current high level of safety in our nuclear power plant fleet, while providing an improved understanding of safety margins and the critical parameters that affect them. Thus, the set of tools will provide information to inform decisions on plant modifications, refurbishments, and surveillance programs, while improving economics. This set of tools will also benefit the design of new reactors, enhancing safety per unit cost of a nuclear plant. The proposed plan will focus on application of the RISMC toolkit, in particular, solving realistic problems of important current issues to the nuclear industry, in collaboration with plant owners and operators to demonstrate the usefulness of these tools in decision making.

  17. 76 FR 55056 - Toy Safety Standard: Strategic Outreach and Education Plan

    Science.gov (United States)

    2011-09-06

    ... to test and certify to the toy safety standard. We plan to use traditional and social media to... testing and certification requirements for children's toys and toy chests and their compliance with ASTM... manufacturers of children's toys must ensure that covered toys are tested for compliance with the toy safety...

  18. 12 CFR 263.303 - Filing of safety and soundness compliance plan.

    Science.gov (United States)

    2010-01-01

    ... member bank will take to correct the deficiency and the time within which those steps will be taken. (c... FEDERAL RESERVE SYSTEM RULES OF PRACTICE FOR HEARINGS Submission and Review of Safety and Soundness... safety and soundness compliance plan. (a) Schedule for filing compliance plan—(1) In general. A State...

  19. Selenide isotope generator for the Galileo Mission: safety test plan

    International Nuclear Information System (INIS)

    1979-01-01

    The intent of this safety test plan is to outline particular kinds of safety tests designed to produce information which would be useful in the safety analysis process. The program deals primarily with the response of the RTG to accident environments; accordingly two criteria were established: (1) safety tests should be performed for environments which are the most critical in terms of risk contribution; and (2) tests should be formulated to determine failure conditions for critical heat source components rather than observe heat source response in reference accident environments. To satisfy criterion 1. results of a recent safety study were used to rank various accidents in terms of expected source terms. Six kinds of tests were then proposed which would provide information meeting the second criterion

  20. A tailored online safety and health intervention for women experiencing intimate partner violence: the iCAN Plan 4 Safety randomized controlled trial protocol

    Directory of Open Access Journals (Sweden)

    Marilyn Ford-Gilboe

    2017-03-01

    Full Text Available Abstract Background Intimate partner violence (IPV threatens the safety and health of women worldwide. Safety planning is a widely recommended, evidence-based intervention for women experiencing IPV, yet fewer than 1 in 5 Canadian women access safety planning through domestic violence services. Rural, Indigenous, racialized, and immigrant women, those who prioritize their privacy, and/or women who have partners other than men, face unique safety risks and access barriers. Online IPV interventions tailored to the unique features of women’s lives, and to maximize choice and control, have potential to reduce access barriers, and improve fit and inclusiveness, maximizing effectiveness of these interventions for diverse groups. Methods/Design In this double blind randomized controlled trial, 450 Canadian women who have experienced IPV in the previous 6 months will be randomized to either a tailored, interactive online safety and health intervention (iCAN Plan 4 Safety or general online safety information (usual care. iCAN engages women in activities designed to increase their awareness of safety risks, reflect on their plans for their relationships and priorities, and create a personalize action plan of strategies and resources for addressing their safety and health concerns. Self-reported outcome measures will be collected at baseline and 3, 6, and 12 months post-baseline. Primary outcomes are depressive symptoms (Center for Epidemiological Studies Depression Scale, Revised and PTSD Symptoms (PTSD Checklist, Civilian Version. Secondary outcomes include helpful safety actions, safety planning self-efficacy, mastery, and decisional conflict. In-depth qualitative interviews with approximately 60 women who have completed the trial and website utilization data will be used to explore women’s engagement with the intervention and processes of change. Discussion This trial will contribute timely evidence about the effectiveness of online safety and

  1. MO-B-BRB-01: Optimize Treatment Planning Process in Clinical Environment

    International Nuclear Information System (INIS)

    Feng, W.

    2015-01-01

    The radiotherapy treatment planning process has evolved over the years with innovations in treatment planning, treatment delivery and imaging systems. Treatment modality and simulation technologies are also rapidly improving and affecting the planning process. For example, Image-guided-radiation-therapy has been widely adopted for patient setup, leading to margin reduction and isocenter repositioning after simulation. Stereotactic Body radiation therapy (SBRT) and Radiosurgery (SRS) have gradually become the standard of care for many treatment sites, which demand a higher throughput for the treatment plans even if the number of treatments per day remains the same. Finally, simulation, planning and treatment are traditionally sequential events. However, with emerging adaptive radiotherapy, they are becoming more tightly intertwined, leading to iterative processes. Enhanced efficiency of planning is therefore becoming more critical and poses serious challenge to the treatment planning process; Lean Six Sigma approaches are being utilized increasingly to balance the competing needs for speed and quality. In this symposium we will discuss the treatment planning process and illustrate effective techniques for managing workflow. Topics will include: Planning techniques: (a) beam placement, (b) dose optimization, (c) plan evaluation (d) export to RVS. Planning workflow: (a) import images, (b) Image fusion, (c) contouring, (d) plan approval (e) plan check (f) chart check, (g) sequential and iterative process Influence of upstream and downstream operations: (a) simulation, (b) immobilization, (c) motion management, (d) QA, (e) IGRT, (f) Treatment delivery, (g) SBRT/SRS (h) adaptive planning Reduction of delay between planning steps with Lean systems due to (a) communication, (b) limited resource, (b) contour, (c) plan approval, (d) treatment. Optimizing planning processes: (a) contour validation (b) consistent planning protocol, (c) protocol/template sharing, (d) semi

  2. MO-B-BRB-01: Optimize Treatment Planning Process in Clinical Environment

    Energy Technology Data Exchange (ETDEWEB)

    Feng, W. [New York Presbyterian Hospital (United States)

    2015-06-15

    The radiotherapy treatment planning process has evolved over the years with innovations in treatment planning, treatment delivery and imaging systems. Treatment modality and simulation technologies are also rapidly improving and affecting the planning process. For example, Image-guided-radiation-therapy has been widely adopted for patient setup, leading to margin reduction and isocenter repositioning after simulation. Stereotactic Body radiation therapy (SBRT) and Radiosurgery (SRS) have gradually become the standard of care for many treatment sites, which demand a higher throughput for the treatment plans even if the number of treatments per day remains the same. Finally, simulation, planning and treatment are traditionally sequential events. However, with emerging adaptive radiotherapy, they are becoming more tightly intertwined, leading to iterative processes. Enhanced efficiency of planning is therefore becoming more critical and poses serious challenge to the treatment planning process; Lean Six Sigma approaches are being utilized increasingly to balance the competing needs for speed and quality. In this symposium we will discuss the treatment planning process and illustrate effective techniques for managing workflow. Topics will include: Planning techniques: (a) beam placement, (b) dose optimization, (c) plan evaluation (d) export to RVS. Planning workflow: (a) import images, (b) Image fusion, (c) contouring, (d) plan approval (e) plan check (f) chart check, (g) sequential and iterative process Influence of upstream and downstream operations: (a) simulation, (b) immobilization, (c) motion management, (d) QA, (e) IGRT, (f) Treatment delivery, (g) SBRT/SRS (h) adaptive planning Reduction of delay between planning steps with Lean systems due to (a) communication, (b) limited resource, (b) contour, (c) plan approval, (d) treatment. Optimizing planning processes: (a) contour validation (b) consistent planning protocol, (c) protocol/template sharing, (d) semi

  3. Safety evaluation report on Tennessee Valley Authority: Watts Bar Nuclear Performance Plan

    International Nuclear Information System (INIS)

    1990-01-01

    This safety evaluation report on the information submitted by the Tennessee Valley Authority in its Nuclear Performance Plan for the Watts Bar Nuclear Plant and in supporting documents has been prepared by the US Nuclear Regulatory Commission staff. The plan addresses the plant-specific corrective actions as part of the recovery program for licensing of Unit 1. The staff will be monitoring and inspecting the implementation of the programs. The plan does not address all licensing matters that will be required for fuel load and operation of Unit 1. Those remaining licensing matters have been addressed in previous safety evaluations or will be addressed in accordance with routing NRC licensing practices. 97 refs

  4. 12 CFR Appendix C to Part 360 - Deposit File Structure

    Science.gov (United States)

    2010-01-01

    .... • STATE = State government. • COMM = Commercial. • CORP = Corporate. • BANK = Bank Owned. • DUE TO = Other... 12 Banks and Banking 4 2010-01-01 2010-01-01 false Deposit File Structure C Appendix C to Part 360... RESOLUTION AND RECEIVERSHIP RULES Pt. 360, App. C Appendix C to Part 360—Deposit File Structure This is the...

  5. Is it necessary to plan with safety margins for actively scanned proton therapy?

    Science.gov (United States)

    Albertini, F.; Hug, E. B.; Lomax, A. J.

    2011-07-01

    In radiation therapy, a plan is robust if the calculated and the delivered dose are in agreement, even in the case of different uncertainties. The current practice is to use safety margins, expanding the clinical target volume sufficiently enough to account for treatment uncertainties. This, however, might not be ideal for proton therapy and in particular when using intensity modulated proton therapy (IMPT) plans as degradation in the dose conformity could also be found in the middle of the target resulting from misalignments of highly in-field dose gradients. Single field uniform dose (SFUD) and IMPT plans have been calculated for different anatomical sites and the need for margins has been assessed by analyzing plan robustness to set-up and range uncertainties. We found that the use of safety margins is a good way to improve plan robustness for SFUD and IMPT plans with low in-field dose gradients but not necessarily for highly modulated IMPT plans for which only a marginal improvement in plan robustness could be detected through the definition of a planning target volume.

  6. A Template Analysis of Intimate Partner Violence Survivors’ Experiences of Animal Maltreatment: Implications for Safety Planning and Intervention

    Science.gov (United States)

    Collins, Elizabeth A.; Cody, Anna M.; McDonald, Shelby Elaine; Nicotera, Nicole; Ascione, Frank R.; Williams, James Herbert

    2018-01-01

    This study explores the intersection of intimate partner violence (IPV) and animal cruelty in an ethnically diverse sample of 103 pet-owning IPV survivors recruited from community-based domestic violence programs. Template analysis revealed five themes: (a) Animal Maltreatment by Partner as a Tactic of Coercive Power and Control, (b) Animal Maltreatment by Partner as Discipline or Punishment of Pet, (c) Animal Maltreatment by Children, (d) Emotional and Psychological Impact of Animal Maltreatment Exposure, and (e) Pets as an Obstacle to Effective Safety Planning. Results demonstrate the potential impact of animal maltreatment exposure on women and child IPV survivors’ health and safety. PMID:29332521

  7. Status of safety issues at licensed power plants: TMI Action Plan requirements, unresolved safety issues, generic safety issues, other multiplant action issues

    International Nuclear Information System (INIS)

    1992-12-01

    This report is to provide a comprehensive description of the implementation and verification status of Three Mile Island (TMI) Action Plan requirements, safety issues designated as Unresolved Safety Issues (USIs), Generic Safety Issues(GSIs), and other Multiplant Actions (MPAs) that have been resolved and involve implementation of an action or actions by licensees. This report makes the information available to other interested parties, including the public. An additional purpose of this NUREG report is to serve as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues up until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees

  8. 12 CFR 570.3 - Filing of safety and soundness compliance plan.

    Science.gov (United States)

    2010-01-01

    ... compliance plan shall include a description of the steps the savings association will take to correct the deficiency and the time within which those steps will be taken. (c) Review of safety and soundness compliance... plan. (a) Schedule for filing compliance plan—(1) In general. A savings association shall file a...

  9. Planning and Preparing for Emergency Response to Transport Accidents Involving Radioactive Material. Safety Guide

    International Nuclear Information System (INIS)

    2009-01-01

    This Safety Guide provides guidance on various aspects of emergency planning and preparedness for dealing effectively and safely with transport accidents involving radioactive material, including the assignment of responsibilities. It reflects the requirements specified in Safety Standards Series No. TS-R-1, Regulations for the Safe Transport of Radioactive Material, and those of Safety Series No. 115, International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. Contents: 1. Introduction; 2. Framework for planning and preparing for response to accidents in the transport of radioactive material; 3. Responsibilities for planning and preparing for response to accidents in the transport of radioactive material; 4. Planning for response to accidents in the transport of radioactive material; 5. Preparing for response to accidents in the transport of radioactive material; Appendix I: Features of the transport regulations influencing emergency response to transport accidents; Appendix II: Preliminary emergency response reference matrix; Appendix III: Guide to suitable instrumentation; Appendix IV: Overview of emergency management for a transport accident involving radioactive material; Appendix V: Examples of response to transport accidents; Appendix VI: Example equipment kit for a radiation protection team; Annex I: Example of guidance on emergency response to carriers; Annex II: Emergency response guide.

  10. 31 CFR 360.55 - Individuals authorized to certify.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 2 2010-07-01 2010-07-01 false Individuals authorized to certify. 360.55 Section 360.55 Money and Finance: Treasury Regulations Relating to Money and Finance (Continued... imprint of either the corporate seal of the institution or of the issuing or paying agent's stamp. The...

  11. Maintenance Implementation Plan for B Plant

    International Nuclear Information System (INIS)

    Tritt, S.E.

    1993-04-01

    The objective of the Maintenance Implementation Plan (MIP) is to describe how the B Plant will implement the requirements established by US Department of Energy (DOE) Order 4330.4A, Maintenance Management Program, Chapter II, ''Nuclear Facilities'' (DOE 1990). The plan provides a blueprint for a disciplined approach to implementation and compliance. Each element of the order is prioritized, categorized, and then placed into one of three phases for implementation

  12. Angra-1 probabilistic safety study-phase B

    International Nuclear Information System (INIS)

    Fernandes Filho, T.L.; Gibelli, S.M.O.

    1988-05-01

    This study represents the Phase B of the Angra-1 Probabilistic Safety Study and is the the final report prepared for the IAEA under Research Contract No. 3423/R2/RB. The three main items covered in this report are the establishment of interim safety goals, analysis of Angra-1 operational experience and development of emergency procedures to address severe accidents. For establishment of interim safety goals a methodology for calculating consequences and risks associated to the Angra-1 operation was developed based on the available data and codes. The proposed safety goals refer to the individual risk of early fatality for people living in the vicinity of the plant, colective risk of cancer fatalities for people living near the plant, the propobability of core melt occurrence and the probability of dominant accident sequences. (author) [pt

  13. 360-degree suture trabeculotomy ab interno to treat open-angle glaucoma: 2-year outcomes

    Science.gov (United States)

    Sato, Tomoki; Kawaji, Takahiro; Hirata, Akira; Mizoguchi, Takanori

    2018-01-01

    Purpose The purpose of this study was to evaluate the efficacy of 360-degree suture trabeculotomy (360S-LOT) ab interno for treating open-angle glaucoma (OAG). Risk factors of surgical failure were examined. Patients and methods 360S-LOT ab interno alone was performed for patients with uncontrolled OAG, and combined 360S-LOT ab interno/phacoemulsification was performed for patients with controlled OAG with a visually significant cataract between March 2014 and September 2015 at a single center. The patients were prospectively followed for 2 years. The main outcome measures included 2-year intraocular pressure (IOP), number of anti-glaucoma medications used, postoperative complications, and predictive factors of surgical failure. Kaplan–Meier analysis was performed, with surgical success (with or without medication use) defined as postoperative IOP ≤15 mmHg and IOP reduction ≥20% (criterion A) or IOP ≤12 mmHg and IOP reduction ≥30% (criterion B). Predictive factors were evaluated using Cox proportional hazard ratios. Results A total of 64 eyes of 64 patients were included, and 50 (78%) eyes of 64 eyes underwent a phacoemulsification combination procedure. Surgery significantly reduced IOP from 18.4 ± 2.9 mmHg before surgery to 13.4 ± 3.0 mmHg after surgery (P interno procedure is a favorable option for treating eyes with mild or moderate OAG. PMID:29844656

  14. Status of safety issues at licensed power plants: TMI Action Plan requirements, unresolved safety issues, generic safety issues, other multiplant action issues. Supplement 4

    International Nuclear Information System (INIS)

    1994-12-01

    As part of ongoing US Nuclear Regulatory Commission (NRC) efforts to ensure the quality and accountability of safety issue information, the NRC established a program for publishing an annual report on the status of licensee implementation and NRC verification of safety issues in major NRC requirements areas. This information was initially compiled and reported in three NUREG-series volumes. Volume 1, published in March 1991, addressed the status of Three Mile Island (TMI) Action Plan Requirements. Volume 2, published in May 1991, addressed the status of unresolved safety issues (USIs). Volume 3, published in June 1991, addressed the implementation and verification status of generic safety issues (GSIs). The first annual supplement, which combined these volumes into a single report and presented updated information as of September 30, 1991, was published in December 1991. The second annual supplement, which provided updated information as of September 30, 1992, was published in December 1992. Supplement 2 also provided the status of licensee implementation and NRC verification of other multiplant action (MPA) issues not related to TMI Action Plan requirements, USIs, or GSIs. Supplement 3 gives status as of September 30, 1993. This annual report, Supplement 4, presents updated information as of September 30, 1994. This report gives a comprehensive description of the implementation and verification status of TMI Action Plan requirements, safety issues designated as USIs, GSIs, and other MPAs that have been resolved and involve implementation of an action or actions by licensees. This report makes the information available to other interested parties, including the public. Additionally, this report serves as a follow-on to NUREG-0933, ''A Prioritization of Generic Safety Issues,'' which tracks safety issues until requirements are approved for imposition at licensed plants or until the NRC issues a request for action by licensees

  15. TIC360. Concepto, Conclusiones y Líneas Abiertas.

    OpenAIRE

    Prado, Andrés

    2015-01-01

    TIC360. Concepto, conclusiones y líneas abiertas derivadas de las jornadas de la sectorial TIC de CRUE celebradas en el campus de Toledo de la UCLM. En estas jornadas se trazó una visión 360º de las TIC en la Universidad, contando con todos los agentes implicados

  16. 20 CFR 410.360 - Determination of dependency; widow.

    Science.gov (United States)

    2010-04-01

    ... 20 Employees' Benefits 2 2010-04-01 2010-04-01 false Determination of dependency; widow. 410.360... OF 1969, TITLE IV-BLACK LUNG BENEFITS (1969- ) Relationship and Dependency § 410.360 Determination of dependency; widow. (a) General. An individual who is the miner's widow (see § 410.320) will be determined to...

  17. Urban planning, traffic planning and traffic safety of pedestrians and cyclists : report presented to the 1979 Road Research Symposium on Safety of Pedestrians and Cyclists, OECD Headquarters, Paris, 14-16 May 1979. Session III: Physical Countermeasures; Subsession III.1: Urban planning and traffic planning.

    NARCIS (Netherlands)

    Wegman, F.C.M.

    1979-01-01

    The traffic safety of pedestrians and cyclists can be improved by means of urban planning and traffic planning, as one of the possibilities. This paper discusses the framework of these measures and activities and also the effects on the field of traffic planning. Chapter I show that it is not

  18. 360° FILM BRINGS BOMBED CHURCH TO LIFE

    Directory of Open Access Journals (Sweden)

    K. Kwiatek

    2012-09-01

    Full Text Available This paper explores how a computer-generated reconstruction of a church can be adapted to create a panoramic film that is presented in a panoramic viewer and also on a wrap-around projection system. It focuses on the fundamental principles of creating 360º films, not only in 3D modelling software, but also presents how to record 360º video using panoramic cameras inside the heritage site. These issues are explored in a case study of Charles Church in Plymouth, UK that was bombed in 1941 and has never been rebuilt. The generation of a 3D model of the bombed church started from the creation of five spherical panoramas and through the use of Autodesk ImageModeler software. The processed files were imported and merged together in Autodesk 3ds Max where a visualisation of the ruin was produced. A number of historical images were found and this collection enabled the process of a virtual reconstruction of the site. The aspect of merging two still or two video panoramas (one from 3D modelling software, the other one recorded on the site from the same locations or with the same trajectories is also discussed. The prototype of 360º non-linear film tells a narrative of a wartime wedding that occurred in this church. The film was presented on two 360º screens where members of the audience could make decisions on whether to continue the ceremony or whether to run away when the bombing of the church starts. 3D modelling software made this possible to render a number of different alternati ves (360º images and 360º video. Immersive environments empower the visitor to imagine the building before it was destroyed.

  19. 360° Film Brings Bombed Church to Life

    Science.gov (United States)

    Kwiatek, K.

    2011-09-01

    This paper explores how a computer-generated reconstruction of a church can be adapted to create a panoramic film that is presented in a panoramic viewer and also on a wrap-around projection system. It focuses on the fundamental principles of creating 360º films, not only in 3D modelling software, but also presents how to record 360º video using panoramic cameras inside the heritage site. These issues are explored in a case study of Charles Church in Plymouth, UK that was bombed in 1941 and has never been rebuilt. The generation of a 3D model of the bombed church started from the creation of five spherical panoramas and through the use of Autodesk ImageModeler software. The processed files were imported and merged together in Autodesk 3ds Max where a visualisation of the ruin was produced. A number of historical images were found and this collection enabled the process of a virtual reconstruction of the site. The aspect of merging two still or two video panoramas (one from 3D modelling software, the other one recorded on the site) from the same locations or with the same trajectories is also discussed. The prototype of 360º non-linear film tells a narrative of a wartime wedding that occurred in this church. The film was presented on two 360º screens where members of the audience could make decisions on whether to continue the ceremony or whether to run away when the bombing of the church starts. 3D modelling software made this possible to render a number of different alternati ves (360º images and 360º video). Immersive environments empower the visitor to imagine the building before it was destroyed.

  20. Sizewell 'B' PWR pre-construction safety report

    International Nuclear Information System (INIS)

    1982-04-01

    The Pre-Construction Safety Report (PCSR) for a PWR power station to be constructed as Sizewell 'B' is presented in 13 volumes containing 16 chapters. The PCSR has been submitted to the Nuclear Installations Inspectorate in support of the Central Electricity Generating Board's application for consent to the extension at Sizewell. It describes the design and provides the safety case for the proposed station, which comprises a 4-loop pressurized water reactor with associated generating plant and supporting auxiliary equipment. A general description of the station and its site is given. The strategy for ensuring nuclear safety is set out and the general design aspects of systems and plant outlined. The plant and systems, including their safety design bases and the fault analyses carried out for the design are described. Finally the way in which the plant will be decommissioned at the end of its useful life is outlined. (U.K.)

  1. Oak Ridge National Laboratory Environmenal, Safety, and Health Management Plan

    International Nuclear Information System (INIS)

    1991-12-01

    The 1990 Tiger Team Appraisal of Oak Ridge National Laboratory (ORNL) revealed that neither Martin Marietta Energy Systems, Inc. (Energy Systems) nor ORNL had a strategic plan for Environmental, Safety, and Health (ES ampersand H) activities. There were no detailed plans describing ORNL's mission, objectives, and strategies for ES ampersand H activities. A number of plans do exist that cover various aspects of ES ampersand H. Their scope ranges from multiyear program plans to annual audit schedules to compliance plans to action plans from specific audits. However, there is not a single document that identifies the plans and the objectives they are to address. This document describes the strategic plan for ORNL and provides the linkage among existing plans. It gives a brief description of the organization and management of ES ampersand H activities at ORNL. The plan identifies the general strategies to be taken by ORNL, using the overall guidance from Energy Systems in its corporate ES ampersand H Strategic Plan. It also identifies more detailed plans for implementation of these strategies, where appropriate

  2. Waste convention regulatory impact on planning safety assessment for LILW disposal in Croatia

    International Nuclear Information System (INIS)

    Valcic, I.; Subasic, D.; Lokner, V.

    2000-01-01

    Preparations for establishment of a LILW repository in Croatia have reached a point where a preliminary safety assessment for the prospective facility is being planned. The planning is not based upon the national regulatory framework, which does not require such an assessment at this early stage, but upon the interagency BSS and the IAEA RADWASS programme recommendations because the national regulations are being revised with express purpose to conform to the most recent international standards and good practices. The Waste Convention, which Croatia has ratified in the meantime, supports this approach in principle, but does not appear to have more tangible regulatory relevance for the safety assessment planning. Its actual requirements regarding safety analyses for a repository fall short of the specific assessment concepts practiced in this decade, and could have well been met by the old Croatian regulations from the mid-eighties. (author)

  3. D Modelling with the Samsung Gear 360

    Science.gov (United States)

    Barazzetti, L.; Previtali, M.; Roncoroni, F.

    2017-02-01

    The Samsung Gear 360 is a consumer grade spherical camera able to capture photos and videos. The aim of this work is to test the metric accuracy and the level of detail achievable with the Samsung Gear 360 coupled with digital modelling techniques based on photogrammetry/computer vision algorithms. Results demonstrate that the direct use of the projection generated inside the mobile phone or with Gear 360 Action Direction (the desktop software for post-processing) have a relatively low metric accuracy. As results were in contrast with the accuracy achieved by using the original fisheye images (front and rear facing images) in photogrammetric reconstructions, an alternative solution to generate the equirectangular projections was developed. A calibration aimed at understanding the intrinsic parameters of the two lenses camera, as well as their relative orientation, allowed one to generate new equirectangular projections from which a significant improvement of geometric accuracy has been achieved.

  4. Development of Broadband Nuclear Safety Data Network (B-NSDN)

    International Nuclear Information System (INIS)

    Son, Gwang Seop; Kim, Dong Hoon; Park, Gi Yong

    2011-01-01

    Recently as introducing digital safety system in nuclear power plant, more data transmission capacity is required. Bandwidth of existing communication network is about a few Mbps. Thus data transmission quantity in recently digital safety system is beyond existing communication network's capacity. In this paper, new protocol that is suitable for safety system communication network is designed. FPGA based communication system is implemented. As result of test, effective bandwidth of B-NSDN is about 20Mbps

  5. Annual plan of research on safety techniques against low level radioactive wastes, FY1994-FY1999

    International Nuclear Information System (INIS)

    1994-01-01

    The safety research on the disposal of low level radioactive waste has been promoted based on the annual plan decided by the committee on radiative waste safety regulation of the Nuclear Safety Commission. Hereafter, the disposal of low level radioactive waste in ocean is never selected. As to the subjects of the safety research which should be carried out for five years from 1994, the necessity, the contents of research, the organs that carry out the research and so on were deliberated, and the results are made into the annual plan, therefore, it is reported. The way of thinking on the safety research, the contents for which efforts should be exerted as the safety research, and the matters to which attention should be paid are shown. As for the annual plan of safety research, the necessity and the outline of the safety research on the disposal in strata, the concrete subjects and their contents, and the necessity and the outline of the safety research on the reuse, the concrete subjects and their contents are reported. The radioactive waste is those produced by the operation of nuclear reactor facilities, those containing TRU nuclides and RI waste. (K.I.)

  6. National nuclear power plant safety research 2011-2014. SAFIR2014 framework plan

    International Nuclear Information System (INIS)

    2010-01-01

    A country utilising nuclear energy is presumed to possess a sufficient infrastructure to cover the education and research in this field, besides the operating organisations of the plants and a regulatory body. The starting point of public nuclear safety research programmes is that they provide the necessary conditions for retaining the knowledge needed for ensuring the continuance of safe and economic use of nuclear power, for development of new know-how and for participation in international cooperation. In fact, the Finnish organisations engaged in research in this sector have been an important resource which the various ministries, the Radiation and Nuclear Safety Authority (STUK) and the power companies have had at their disposal. Ministry of employment and the economy appointed a group to write the Framework Plan of the new programme. This report contains a proposal for the general outline of the programme, entitled as SAFIR2014 (SAfety of Nuclear Power Plants - Finnish National Research Programme). The plan has been made for the period 2011-2014, but it is based on safety challenges identified for a longer time span as well. Olkiluoto 3, the new nuclear power plant unit under construction and new decisions-in-principle have also been taken into account in the plan. The safety challenges set by the existing plants and the new projects, as well as the ensuing research needs do, however, converge to a great extent. The research programme is strongly based on the Chapter 7a of the Finnish Nuclear Energy Act. The construction of new power plant units will increase the need for experts in the field in Finland. At the same time, the retirement of the existing experts is continuing. These factors together will call for more education and training, in which active research activities play a key role. This situation also makes long-term safety research face a great challenge. The Framework Plan aims to define the important research needs related to the safety

  7. 49 CFR 659.27 - Internal safety and security reviews.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 7 2010-10-01 2010-10-01 false Internal safety and security reviews. 659.27... State Oversight Agency § 659.27 Internal safety and security reviews. (a) The oversight agency shall... safety and security reviews in its system safety program plan. (b) The internal safety and security...

  8. Radiation safety analysis and action plans for NSRRC top-up operation

    International Nuclear Information System (INIS)

    Wang, J.-P.; Sheu, R.-J.; Liu, Joseph C.; Chen, C.-R.; Chang, F.-D.; Kao, S.-P.

    2006-01-01

    This paper summarizes the radiation safety analysis and action plans for the upcoming top-up operation at the National Synchrotron Radiation Research Center (NSRRC). Electron beam loss scenarios and consequence of beam lifetime and injection efficiency have been studied. Dose assessment was conducted based on measurement and Monte Carlo simulation results. Radiation safety action plans such as upgrading the shielding of the injection section, enlarging the exclusion zones of the straight section beamlines, installing new interlock system for top-up operation and most importantly improving the injection efficiency have been scheduled. The goal is to keep present dose limit of 2 mSv/y and make top-up operation feasible at normal user's run of year 2006

  9. System safety program plan for the Isotope Brayton Ground Demonstration System (phase I)

    International Nuclear Information System (INIS)

    1976-01-01

    The safety engineering effort to be undertaken in achieving an acceptable level of safety in the Brayton Isotope Power System (BIPS) development program is discussed. The safety organizational relationships, the methods to be used, the tasks to be completed, and the documentation to be published are described. The plan will be updated periodically as the need arises

  10. Hacking 360 Link: A hybrid approach

    Directory of Open Access Journals (Sweden)

    John Durno

    2012-10-01

    Full Text Available When the University of Victoria Libraries switched from a locally-hosted link resolver (SFX to a vendor-hosted link resolver (360Link, new strategies were required to effectively integrate the vendor-hosted link resolver with the Libraries' other systems and services. Custom javascript is used to add links to the 360Link page; these links then point at local PHP code running on UVic servers, which can then redirect to appropriate local service or display a form directly. An open source PHP OpenURL parser class is announced. Consideration is given to the importance of maintaining open protocols and standards in the transition to vendor-hosted services.

  11. Integrated Environment and Safety and Health Management System (ISMS) Implementation Project Plan

    Energy Technology Data Exchange (ETDEWEB)

    MITCHELL, R.L.

    2000-01-10

    The Integrated Environment, Safety and Health Management System (ISMS) Implementation Project Plan serves as the project document to guide the Fluor Hanford, Inc (FHI) and Major Subcontractor (MSC) participants through the steps necessary to complete the integration of environment, safety, and health into management and work practices at all levels.

  12. Integrated Environment and Safety and Health Management System (ISMS) Implementation Project Plan

    International Nuclear Information System (INIS)

    MITCHELL, R.L.

    2000-01-01

    The Integrated Environment, Safety and Health Management System (ISMS) Implementation Project Plan serves as the project document to guide the Fluor Hanford, Inc (FHI) and Major Subcontractor (MSC) participants through the steps necessary to complete the integration of environment, safety, and health into management and work practices at all levels

  13. Minnesota urban partnership agreement national evaluation : safety data test plan.

    Science.gov (United States)

    2009-11-17

    This report provides the safety data test plan for the Minnesota Urban Partnership Agreement (UPA) under the United States Department of Transportation (U.S. DOT) UPA Program. The Minnesota UPA projects focus on reducing congestion by employing strat...

  14. Sexual Safety Planning as an HIV Prevention Strategy for Survivors of Domestic Violence.

    Science.gov (United States)

    Foster, Jill; Núñez, Ana; Spencer, Susan; Wolf, Judith; Robertson-James, Candace

    2016-06-01

    Victims of domestic violence (DV) are not only subject to physical and emotional abuse but may also be at increased risk for less recognized dangers from infection with human immunodeficiency virus (HIV) and other sexually transmitted pathogens. Because of the close link between DV and sexual risk, women need to be educated about the consequences of acquiring a life-threatening sexually transmitted infection, risk reduction measures, and how to access appropriate HIV services for diagnosis and treatment. It is therefore critical for DV workers to receive sufficient training about the link between DV and HIV risk so that sexual safety planning can be incorporated into activities with their clients in the same way as physical safety plans. In this article, we discuss how the Many Hands Working Together project provides interactive training for workers in DV and DV-affiliated agencies to increase their knowledge about HIV and teach sexual safety planning skills to achieve HIV risk reduction.

  15. COPD360social Online Community: A Social Media Review.

    Science.gov (United States)

    Stellefson, Michael; Paige, Samantha R; Alber, Julia M; Stewart, Margaret

    2018-06-01

    People living with chronic obstructive pulmonary disease (COPD) commonly report feelings of loneliness and social isolation due to lack of support from family, friends, and health care providers. COPD360social is an interactive and disease-specific online community and social network dedicated to connecting people living with COPD to evidence-based resources. Through free access to collaborative forums, members can explore, engage, and discuss an array of disease-related topics, such as symptom management. This social media review provides an overview of COPD360social, specifically its features that practitioners can leverage to facilitate patient-provider communication, knowledge translation, and community building. The potential of COPD360social for chronic disease self-management is maximized through community recognition programming and interactive friend-finding tools that encourage members to share their own stories through blogs and multimedia (e.g., images, videos). The platform also fosters collaborative knowledge dissemination and helping relationships among patients, family members, friends, and health care providers. Successful implementation of COPD360social has dramatically expanded patient education and self-management support resources for people affected by COPD. Practitioners should refer patients and their families to online social networks such as COPD360social to increase knowledge and awareness of evidence-based chronic disease management practices.

  16. Health and safety plan for characterization sampling of ETR and MTR facilities

    International Nuclear Information System (INIS)

    Baxter, D.E.

    1994-10-01

    This health and safety plan establishes the procedures and requirements that will be used to minimize health and safety risks to persons performing Engineering Test Reactor and Materials Test Reactor characterization sampling activities, as required by the Occupational Safety and Health Administration standard, 29 CFR 1910.120. It contains information about the hazards involved in performing the tasks, and the specific actions and equipment that will be used to protect persons working at the site

  17. Autodesk Infraworks 360 and Autodesk Infraworks 360 LT essentials

    CERN Document Server

    Chappell, Eric

    2015-01-01

    Get up to speed and get to work quickly with the official InfraWorks handbook Autodesk InfraWorks and InfraWorks 360 Essentials, 2nd Edition is your comprehensive, hands-on guide to this popular civil engineering software. This unique guide features concise, straightforward explanations and real world exercises to bring you up to speed on InfraWorks' core features and functions, giving you the skills you need to quickly become productive. Following a workflow-based approach that mirrors how projects progress in the real world, this book walks you through the process of designing a residential

  18. 78 FR 979 - Petition for Positive Train Control Safety Plan Approval and System Certification of the...

    Science.gov (United States)

    2013-01-07

    ...] Petition for Positive Train Control Safety Plan Approval and System Certification of the Electronic Train... the Federal Railroad Administration (FRA) for Positive Train Control (PTC) Safety Plan (PTCSP) approval and system certification of the Electronic Train Management System (ETMS) as required by 49 U.S.C...

  19. Jefferson Proving Ground, South of the Firing Line Health and Safety Plan, Volume 4

    National Research Council Canada - National Science Library

    1992-01-01

    .... The purpose of this Site Health and Safety Plan (SHSP) is to assign SECD personnel health and safety responsibilities, to prescribe mandatory operating procedures, and to establish personal-protective-equipment (PPE...

  20. Annual plan of research on safety techniques against low level radioactive wastes, 1984-1988

    International Nuclear Information System (INIS)

    1984-01-01

    The establishment of the countermeasures for treating and disposing radioactive wastes has become an important subject for promoting the utilization of atomic energy. Especially as to low level radioactive wastes, the cumulative quantity has reached about 460,000 in terms of 200 l drums as of the end of March, 1983, and accompanying the development of the utilization of atomic energy, its rapid increase is expected. So far, as for the disposal of low level radioactive wastes, the research and development and the preparation of safety criteria and safety evaluation techniques have been carried out, following the basic policy of the Atomic Energy Commission to execute land disposal and ocean disposal in combination, first to make the test disposal after preliminary safety evaluation, and to shift to the full scale disposal based on the results. The annual plan was decided on July 22, 1983, and the first revision was carried out this time, therefore, it is reported here. The basic policy of establishing this annual plan, and the annual plan for safety technique research are described. (Kako, I.)

  1. 360-degree videos: a new visualization technique for astrophysical simulations

    Science.gov (United States)

    Russell, Christopher M. P.

    2017-11-01

    360-degree videos are a new type of movie that renders over all 4π steradian. Video sharing sites such as YouTube now allow this unique content to be shared via virtual reality (VR) goggles, hand-held smartphones/tablets, and computers. Creating 360° videos from astrophysical simulations is not only a new way to view these simulations as you are immersed in them, but is also a way to create engaging content for outreach to the public. We present what we believe is the first 360° video of an astrophysical simulation: a hydrodynamics calculation of the central parsec of the Galactic centre. We also describe how to create such movies, and briefly comment on what new science can be extracted from astrophysical simulations using 360° videos.

  2. Identification of training and emergency-planning needs through job-safety analysis

    Energy Technology Data Exchange (ETDEWEB)

    Veltrie, J.

    1987-01-01

    Training and emergency-planning needs within the photovoltaic industry may be more accurately determined through the performance of detailed job-safety analysis. This paper outlines the four major components of such an analysis, namely operational review, hazards evaluation, personnel review and resources evaluation. It then shows how these may be developed into coherent training and planning recommendations, for both emergency and non-emergency situations.

  3. TWRS safety and technical integration risk management plan

    International Nuclear Information System (INIS)

    Fordham, R.A.

    1996-01-01

    The objectives of the Tank Waste Remediation System (TWRS) Safety and Technical Integration (STI) programmatic risk management program are to assess, analyze, and handle risks associated with TWRS STI responsibilities and to communicate information about the actions being taken and the results to enable decision making. The objective of this TWRS STI Risk Management Plan is to communicate a consistent approach to risk management that will be used by the organization

  4. 24 CFR 3282.360 - PIA acceptance of product certification programs or listings.

    Science.gov (United States)

    2010-04-01

    ... ENFORCEMENT REGULATIONS Primary Inspection Agencies § 3282.360 PIA acceptance of product certification... 24 Housing and Urban Development 5 2010-04-01 2010-04-01 false PIA acceptance of product certification programs or listings. 3282.360 Section 3282.360 Housing and Urban Development Regulations Relating...

  5. Preparation, review, and approval of implementation plans for nuclear safety requirements

    International Nuclear Information System (INIS)

    1994-10-01

    This standard describes an acceptable method to prepare, review, and approve implementation plans for DOE Nuclear Safety requirements. DOE requirements are identified in DOE Rules, Orders, Notices, Immediate Action Directives, and Manuals

  6. Management implementation plan for a safety analysis and review system

    International Nuclear Information System (INIS)

    Hulburt, D.A.; Berkey, B.D.

    1981-04-01

    The US Department of Energy has issued an Order, DOE 5481.1, which establishes uniform requirements for the preparation and review of Safety Analysis for DOE Operations. The Management Implementation Plan specified herein establishes the administrative procedures and technical requirements for implementing DOE 5481.1 to Operations under the cognizance of the Pittsburgh Energy Technology Center. This Implementation Plan is applicable to all present and future Operations under the cognizance of PETC. The Plan identifies those Operations for which DOE 5481.1 is applicable and those Operations for which no further analysis is required because the initial determination and review has concluded that DOE 5481.1 does not apply

  7. Stalking: A Multidimensional Framework for Assessment and Safety Planning.

    Science.gov (United States)

    Logan, T K; Walker, Robert

    2015-09-03

    Despite the high prevalence of stalking and the risk of harm it poses to victims, arrest rates, prosecutions, and convictions for stalking continue to be low in the United States. The overall goal of this article is to introduce a multidimensional framework of stalking that adds to the current literature by (1) providing a conceptual framework consistent with legal elements of many stalking statutes to facilitate assessment, communication, documentation, and safety planning for stalking several victims; (2) introducing a more systematic way of assessing course of conduct and the context of fear in stalking situations in order to increase the understanding of cumulative fear for stalking victims; (3) emphasizing the aspects of stalking harm that go beyond violence and that show how harm from stalking accumulates over time including life sabotage; and (4) discussing 12 risk factors derived from the overall multidimensional framework that can be used to describe the big picture of stalking and to facilitate safety planning for victims. Implications for future research are discussed. © The Author(s) 2015.

  8. Health and Safety Management Plan for the Plutonium Stabilization and Packaging System

    International Nuclear Information System (INIS)

    1996-01-01

    This Health and Safety Management Plan (HSMP) presents safety and health policies and a project health and safety organizational structure designed to minimize potential risks of harm to personnel performing activities associated with Plutonium Stabilization and Packaging System (Pu SPS). The objectives of the Pu SPS are to design, fabricate, install, and startup of a glovebox system for the safe repackaging of plutonium oxides and metals, with a requirement of a 50-year storage period. This HSMP is intended as an initial project health and safety submittal as part of a three phase effort to address health and safety issues related to personnel working the Pu SPS project. Phase 1 includes this HSMP and sets up the basic approach to health and safety on the project and addresses health and safety issues related to the engineering and design effort. Phase 2 will include the Site Specific Construction health and Safety Plan (SSCHSP). Phase 3 will include an additional addendum to this HSMP and address health and safety issues associated with the start up and on-site test phase of the project. This initial submittal of the HSMP is intended to address those activities anticipated to be performed during phase 1 of the project. This HSMP is intended to be a living document which shall be modified as information regarding the individual tasks associated with the project becomes available. These modifications will be in the form of addenda to be submitted prior to the initiation of each phase of the project. For additional work authorized under this project this HSMP will be modified as described in section 1.4

  9. 37 CFR 360.10 - General.

    Science.gov (United States)

    2010-07-01

    ....10 Patents, Trademarks, and Copyrights COPYRIGHT ROYALTY BOARD, LIBRARY OF CONGRESS SUBMISSION OF ROYALTY CLAIMS FILING OF CLAIMS TO ROYALTY FEES COLLECTED UNDER COMPULSORY LICENSE Satellite Claims § 360... to be entitled to compulsory license royalty fees for secondary transmissions by satellite carriers...

  10. National plan to enhance aviation safety through human factors improvements

    Science.gov (United States)

    Foushee, Clay

    1990-01-01

    The purpose of this section of the plan is to establish a development and implementation strategy plan for improving safety and efficiency in the Air Traffic Control (ATC) system. These improvements will be achieved through the proper applications of human factors considerations to the present and future systems. The program will have four basic goals: (1) prepare for the future system through proper hiring and training; (2) develop a controller work station team concept (managing human errors); (3) understand and address the human factors implications of negative system results; and (4) define the proper division of responsibilities and interactions between the human and the machine in ATC systems. This plan addresses six program elements which together address the overall purpose. The six program elements are: (1) determine principles of human-centered automation that will enhance aviation safety and the efficiency of the air traffic controller; (2) provide new and/or enhanced methods and techniques to measure, assess, and improve human performance in the ATC environment; (3) determine system needs and methods for information transfer between and within controller teams and between controller teams and the cockpit; (4) determine how new controller work station technology can optimally be applied and integrated to enhance safety and efficiency; (5) assess training needs and develop improved techniques and strategies for selection, training, and evaluation of controllers; and (6) develop standards, methods, and procedures for the certification and validation of human engineering in the design, testing, and implementation of any hardware or software system element which affects information flow to or from the human.

  11. 14 CFR 121.360 - Ground proximity warning-glide slope deviation alerting system.

    Science.gov (United States)

    2010-01-01

    ... deviation alerting system. 121.360 Section 121.360 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION... Equipment Requirements § 121.360 Ground proximity warning-glide slope deviation alerting system. (a) No... system that meets the performance and environmental standards of TSO-C92 (available from the FAA, 800...

  12. Maintenance implementation plan for the B Plant/WESF. Revision 4

    International Nuclear Information System (INIS)

    Tritt, S.E.; Lueck, B.H.

    1996-01-01

    This Maintenance Implementation Plan (MIP) has been developed for maintenance functions associated with the B Plant/WESF (Waste Encapsulation Storage Facility) complex. The objective of this plan is to provide baseline information for establishing and identifying WHC conformance programs and policies applicable to implementation of DOE order 4330.4B guidelines. In addition, this maintenance plan identifies the actions necessary to develop a cost-effective and efficient maintenance program at B Plant/WESF. The B Plant WESF facility complex consists of three main facilities and several support structures located in the 200 East Area of the Hanford site. B Plant is a transition facility that is required to ensure safe storage and management of WESF (operating facility) cesium and strontium capsules. B Plant/WESF also contains substantial radiological inventory from previous campaigns. There are no production activities at B Plant, but several of its operating systems are required to accomplish the current B Plant/WESF mission. B Plant/WESF are each considered a nuclear facility due to the storage of cesium and strontium capsules at WESF and the large radiological inventory from past processing

  13. Safety in times of crises - the importance of industrial emergency plans

    International Nuclear Information System (INIS)

    Rademacher, H.; Schulten, R.

    1989-01-01

    Technical and organizational precautions cannot always avoid everyday risks such as accidents, fire, explosions, and other critical situations which without appropriate countermeasures can easily develop into emergencies. While in recent years considerable efforts have been going into improving the technical safety of industrial plants particularly susceptible to accidents (e.g. the nuclear and chemical industry), organizational safety seems to have been neglected. An analysis of different accidents reveals human fallibility rather than technical failures to be causing damage in many cases. Industrial emergency plans are considered to be contributing to the improvement of organizational safety. (orig.) [de

  14. 324 Facility B-Cell quality process plan

    International Nuclear Information System (INIS)

    Carlson, J.L.

    1998-01-01

    This report documents the quality process plan for the restart of a hot cell in the B Plant, originally a bismuth phosphate processing facility, but later converted to a waste fractionation plant. B-Cell is currently being cleaned out and deactivated. TPA Milestone M-89-02 dictates that all mixed waste and equipment be removed from B-Cell by 5/31/1999. This report describes the major activities that remain for completion of the TPA milestone

  15. The Nordic programme for nuclear safety 1990-1993. Plan for 1993

    International Nuclear Information System (INIS)

    1993-04-01

    In 1993 the fourth Nordic Nuclear Safety Research programme will be concluded with final reports on all of the eighteen projects. Each report will contain the results of the work carried out which has taken four years to complete and, at the same time, give a more general survey of the Northern countries' competence within the fields of emergency readiness in situations of abnormal radiation, radioactive waste and its disposal, radioecology and nuclear reactor safety - accessibility of appropriate information. Some of the reports will be published in the form of reference books or in the form of databases of direct assistance to the authorities. A number of seminars will be held so that the results and professional level of the reports can be discussed. The coordinators' and project leaders' plans for these activities are presented with the the amounts of money that project organizers have asked the Nordic Nuclear Safety Research programme to finance them with. During 1993 the plans for the programme starting in 1994 must be laid, and future researchers, project leaders, involved organizations and sponsors determined. (AB)

  16. Health and safety plan for operations performed for the Environmental Restoration Program. Task, OU 1-03 and OU 4-10 Track 2 investigations

    Energy Technology Data Exchange (ETDEWEB)

    Trippet, W.A. II [IT Corp., (United States); Reneau, M.; Morton, S.L. [EG and G Idaho, Inc., Idaho Falls, ID (United States)

    1992-04-01

    This document constitutes the generic health and safety plan for the Environmental Restoration Program (ERP). It addresses the health and safety requirements of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA); Occupational Safety and Health Administration (OSHA) 29 CFR 1910.120 standard; and EG&G Idaho, Inc. This plan is a guide to individuals who must complete a health and safety plan for a task performed for the EPR. It contains a task specific addendum that, when completed, specifically addresses task specific health and safety issues. This health and safety plan reduces the time it takes to write a task specific health and safety plan by providing discussions of requirements, guidance on where specific information is located, and specific topics in the Addendum that must be discussed at a task level. This format encourages a complete task specific health and safety plan and a standard for all health and safety plans written for ERP.

  17. High sensitivity broadband 360GHz passive receiver for TeraSCREEN

    Science.gov (United States)

    Wang, Hui; Oldfield, Matthew; Maestrojuán, Itziar; Platt, Duncan; Brewster, Nick; Viegas, Colin; Alderman, Byron; Ellison, Brian N.

    2016-05-01

    TeraSCREEN is an EU FP7 Security project aimed at developing a combined active, with frequency channel centered at 360 GHz, and passive, with frequency channels centered at 94, 220 and 360 GHz, imaging system for border controls in airport and commercial ferry ports. The system will include automatic threat detection and classification and has been designed with a strong focus on the ethical, legal and practical aspects of operating in these environments and with the potential threats in mind. Furthermore, both the passive and active systems are based on array receivers with the active system consisting of a 16 element MIMO FMCW radar centered at 360 GHz with a bandwidth of 30 GHz utilizing a custom made direct digital synthesizer. The 16 element passive receiver system at 360 GHz uses commercial Gunn diode oscillators at 90 GHz followed by custom made 90 to 180 GHz frequency doublers supplying the local oscillator for 360 GHz sub-harmonic mixers. This paper describes the development of the passive antenna module, local oscillator chain, frequency mixers and detectors used in the passive receiver array of this system. The complete passive receiver chain is characterized in this paper.

  18. Voluntary research results for five years along the master plan on nuclear safety research. FY 2001 - 2005

    International Nuclear Information System (INIS)

    Sato, Yoshinori

    2006-05-01

    Safety Research has been conducted from FY 2001 to FY 2005 according to the Master Plan on Nuclear Safety Research (FY 2001-2005) in Japan Atomic Energy Agency which took over former Japan Nuclear Cycle Development Institute. This report shows the voluntary research results for five years conducted from FY 2001 to FY 2005 according to the Master Plan on Nuclear Safety Research (FY 2001-2005). (author)

  19. Penilaian Kinerja dengan Menggunakan Konsep 360 Derajat Feedback

    OpenAIRE

    Widya, Rita

    2004-01-01

    The concept of 360 degree appraisal is straight forward enough. In the systems, individuals evalute themselves and receive feedback from other employees and organizational members. The feedback comes from an individuals immediate supervisor and peers, and if the individual is manager from his or her direct subordinates. Employees performance can improved through feedback with evaluate themselves and receives feedback from other employees. With apply the concept of 360 degree feedback for gett...

  20. 12 CFR 563b.110 - Who must review my business plan?

    Science.gov (United States)

    2010-01-01

    ... 12 Banks and Banking 5 2010-01-01 2010-01-01 false Who must review my business plan? 563b.110... business plan? (a) Your chief executive officer and members of the board of directors must review, and at least two-thirds of your board of directors must approve, the business plan. (b) Your chief executive...

  1. Maintenance Action Readiness Assessment Plan for Waste Area Grouping 1 inactive Tanks 3001-B, 3004-B, T-30, and 3013 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1995-07-01

    This Readiness Assessment Plan has been prepared to document operational readiness for the maintenance action consisting of remediation of four inactive liquid low-level radioactive tanks in Waste Area Grouping 1 at Oak Ridge National Laboratory. The four tanks to be remediated are Tanks 3001-B, 3004-B, T-30, and 3013. Tanks 3001-B, 3004-B, and T-30 will be removed from the ground. Because of logistical issues associated with excavation and site access, Tank 3013 will be grouted in place and permanently closed. This project is being performed as a maintenance action rather than an action under the Comprehensive Environmental Response, Compensation, and Liability Act, because the risk to human health and environment is well below the US Environmental Protection Agency's level of concern. The decision to proceed as a maintenance action was documented by an interim action proposed plan, which is included in the administrative record. A Readiness Assessment Team has been assembled to review the criteria deemed necessary to conduct the remediation tasks. These criteria include approval of all plans, acquisition of needed equipment, completion of personnel training, and coordination with plant health and safety personnel. Once the criteria have been met and documented, the task will begin. The readiness assessment is expected to be completed by late July 1995, and the task will begin thereafter

  2. 37 CFR 360.1 - General.

    Science.gov (United States)

    2010-07-01

    ... Patents, Trademarks, and Copyrights COPYRIGHT ROYALTY BOARD, LIBRARY OF CONGRESS SUBMISSION OF ROYALTY CLAIMS FILING OF CLAIMS TO ROYALTY FEES COLLECTED UNDER COMPULSORY LICENSE Cable Claims § 360.1 General... to cable compulsory license royalty fees shall file claims with the Copyright Royalty Board. ...

  3. 44 CFR 360.1 - Purpose.

    Science.gov (United States)

    2010-10-01

    ... intergovernmental endeavor which combines financial and human resources to fill the unique training needs of local... PREPAREDNESS STATE ASSISTANCE PROGRAMS FOR TRAINING AND EDUCATION IN COMPREHENSIVE EMERGENCY MANAGEMENT § 360.1 Purpose. The Emergency Management Training Program is designed to enhance the States' emergency management...

  4. Industrial Fuel Gas Demonstration Plant Program. Task III, Demonstration plant safety, industrial hygiene, and major disaster plan (Deliverable No. 35)

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-03-01

    This Health and Safety Plan has been adopted by the IFG Demonstration Plant managed by Memphis Light, Gas and Water at Memphis, Tennessee. The plan encompasses the following areas of concern: Safety Plan Administration, Industrial Health, Industrial Safety, First Aid, Fire Protection (including fire prevention and control), and Control of Safety Related Losses. The primary objective of this plan is to achieve adequate control of all potentially hazardous activities to assure the health and safety of all employees and eliminate lost work time to both the employees and the company. The second objective is to achieve compliance with all Federal, state and local laws, regulations and codes. Some thirty specific safe practice instruction items are included.

  5. Prioritization of tasks in the draft LWR safety technology program plan. Final report

    International Nuclear Information System (INIS)

    Lim, E.Y.; Miller, W.J.; Parkinson, W.J.; Ritzman, R.L.; vonHerrmann, J.L.; Wood, P.J.

    1980-05-01

    The purpose of this report is to describe both the approach taken and the results produced in the SAI effort to prioritize the tasks in the Sandia draft LWR Safety Technology Program Plan. This work used the description of important safety issues developed in the Reactor Safety Study (2) to quantify the effect of safety improvements resulting from a research and development program on the risk from nuclear power plants. Costs of implementation of these safety improvements were also estimated to allow a presentation of the final results in a value (i.e., risk reduction) vs. impact (i.e., implementation costs) matrix

  6. Safety evaluation report on Tennessee Valley Authority: Browns Ferry nuclear performance plan

    International Nuclear Information System (INIS)

    1989-10-01

    This safety evaluation report (SER) on the information submitted by the Tennessee Valley Authority (TVA) in its Nuclear Performance Plan, through Revision 2, for the Browns Ferry Nuclear Plant and in supporting documents has been prepared by the US Nuclear Regulatory commission staff. The Browns Ferry Nuclear Plant consists of three boiling-water reactors at a site in Limestone County, Alabama. The plan addresses the plant-specific concerns requiring resolution before the startup of Unit 2. The staff will inspect implementation of those TVA programs that address these concerns. Where systems are common to Units 1 and 2 or to Units 2 and 3, the staff safety evaluations of those systems are included herein. 85 refs

  7. 37 CFR 360.20 - General.

    Science.gov (United States)

    2010-07-01

    ....20 Patents, Trademarks, and Copyrights COPYRIGHT ROYALTY BOARD, LIBRARY OF CONGRESS SUBMISSION OF ROYALTY CLAIMS FILING OF CLAIMS TO ROYALTY FEES COLLECTED UNDER COMPULSORY LICENSE Digital Audio Recording Devices and Media Royalty Claims § 360.20 General. This subpart prescribes procedures pursuant to 17 U.S.C...

  8. 12 CFR 563b.115 - How will OTS review my business plan?

    Science.gov (United States)

    2010-01-01

    ... 12 Banks and Banking 5 2010-01-01 2010-01-01 false How will OTS review my business plan? 563b.115... business plan? (a) OTS will review your business plan to determine that it demonstrates a safe and sound... will be determinative. OTS will review every case on its merits. (b) You must file your business plan...

  9. Safety evaluation report on Tennessee Valley Authority: Browns Ferry Nuclear Performance Plan

    International Nuclear Information System (INIS)

    1991-01-01

    This safety evaluation report (SER) was prepared by the US Nuclear Regulatory Commission (NRC) staff and represents the second and last supplement (SSER 2) to the staff's original SER published as Volume 3 of NUREG-1232 in April 1989. Supplement 1 of Volume 3 of NUREG-1232 (SSER 1) was published in October 1989. Like its predecessors, SSER 2 is composed of numerous safety evaluations by the staff regarding specific elements contained in the Browns Ferry Nuclear Performance Plan (BFNPP), Volume 3 (up to and including Revision 2), submitted by the Tennessee Valley Authority (TVA) for the Browns Ferry Nuclear Plant (BFN). The Browns Ferry Nuclear Plant consists of three boiling-water reactors (BWRs) at a site in Limestone County, Alabama. The BFNPP describes the corrective action plans and commitments made by TVA to resolve deficiencies with its nuclear programs before the startup of Unit 2. The staff has inspected and will continue to inspect TVA's implementation of these BFNPP corrective action plans that address staff concerns about TVA's nuclear program. SSER 2 documents the NRC staff's safety evaluations and conclusions for those elements of the BFNPP that were not previously addressed by the staff or that remained open as a result of unresolved issues identified by the staff in previous SERs and inspections

  10. The Applicability of 360 Degree Feedback Performance Appraisal System: A Brigade Sample

    Directory of Open Access Journals (Sweden)

    Hakan TURGUT

    2012-03-01

    Full Text Available On the subject of measuring individual performances, which considered to be one of the fundamental functions of the human resources management process, 360 Degree Feedback Performance Appraisal System (360 DFPAS preferred for taking into account more than one aspect while providing opportunities in order to achieve more objective results. It’s been thought that the applicability of the above mentioned method is not investigated enough in the public sector where most of the employments take place in Turkey. The purpose of this study is to probe into the applicability of the 360 DFPAS on low and mid-level managers in a brigade. Within this framework, differences between the raters (manager, subordinate, peer, client, self-evaluation have been examined and comparisons made between traditional performance appraisal and 360 DFPAS. There are meaningful differences only inner client between two different evaluation methods (Traditional manager evalution-360 DFPAS within evaluation raters. But there aren’t any meaningful differences between traditional performance appraisal and 360 DFPAS as whole method.

  11. B-to-C Digital Marketing Plan for ONAR Studios

    OpenAIRE

    Juvonen, Mirjam

    2016-01-01

    Traditional marketing methods are losing their impact in this continuously more digital world. Most customers are online and businesses need to be there, too. Through a creative plan for digital marketing, businesses can gain an advantage over their competitors, which is highly needed especially in the extremely competitive fashion industry. The objective of this product-based thesis is to create a B-to-C digital marketing plan for the case company, ONAR Studios, a small Finnish fashion b...

  12. 21 CFR 111.360 - What are the requirements for sanitation?

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 2 2010-04-01 2010-04-01 false What are the requirements for sanitation? 111.360... for Manufacturing Operations § 111.360 What are the requirements for sanitation? You must conduct all manufacturing operations in accordance with adequate sanitation principles. ...

  13. Segment scheduling method for reducing 360° video streaming latency

    Science.gov (United States)

    Gudumasu, Srinivas; Asbun, Eduardo; He, Yong; Ye, Yan

    2017-09-01

    360° video is an emerging new format in the media industry enabled by the growing availability of virtual reality devices. It provides the viewer a new sense of presence and immersion. Compared to conventional rectilinear video (2D or 3D), 360° video poses a new and difficult set of engineering challenges on video processing and delivery. Enabling comfortable and immersive user experience requires very high video quality and very low latency, while the large video file size poses a challenge to delivering 360° video in a quality manner at scale. Conventionally, 360° video represented in equirectangular or other projection formats can be encoded as a single standards-compliant bitstream using existing video codecs such as H.264/AVC or H.265/HEVC. Such method usually needs very high bandwidth to provide an immersive user experience. While at the client side, much of such high bandwidth and the computational power used to decode the video are wasted because the user only watches a small portion (i.e., viewport) of the entire picture. Viewport dependent 360°video processing and delivery approaches spend more bandwidth on the viewport than on non-viewports and are therefore able to reduce the overall transmission bandwidth. This paper proposes a dual buffer segment scheduling algorithm for viewport adaptive streaming methods to reduce latency when switching between high quality viewports in 360° video streaming. The approach decouples the scheduling of viewport segments and non-viewport segments to ensure the viewport segment requested matches the latest user head orientation. A base layer buffer stores all lower quality segments, and a viewport buffer stores high quality viewport segments corresponding to the most recent viewer's head orientation. The scheduling scheme determines viewport requesting time based on the buffer status and the head orientation. This paper also discusses how to deploy the proposed scheduling design for various viewport adaptive video

  14. Improving food safety in the supply chain: Integrating traceability in production and distribution planning

    DEFF Research Database (Denmark)

    Grunow, Martin; Rong, Aiying; Akkerman, Renzo

    2008-01-01

    on production and distribution planning. Here, we develop a methodology for production and distribution planning in food supply chains which minimizes production and logistics costs and at the same time reduces food safety concerns, limits the size of potential recalls, and satisfies product quality...... with traceability from the viewpoint of information system development and technology development such as radio frequency identification (RFID) and DNA-based techniques. However, traceability and its implications for food safety are thus far not incorporated in the standard operations management literature...

  15. A hybrid simulation approach for integrating safety behavior into construction planning: An earthmoving case study.

    Science.gov (United States)

    Goh, Yang Miang; Askar Ali, Mohamed Jawad

    2016-08-01

    One of the key challenges in improving construction safety and health is the management of safety behavior. From a system point of view, workers work unsafely due to system level issues such as poor safety culture, excessive production pressure, inadequate allocation of resources and time and lack of training. These systemic issues should be eradicated or minimized during planning. However, there is a lack of detailed planning tools to help managers assess the impact of their upstream decisions on worker safety behavior. Even though simulation had been used in construction planning, the review conducted in this study showed that construction safety management research had not been exploiting the potential of simulation techniques. Thus, a hybrid simulation framework is proposed to facilitate integration of safety management considerations into construction activity simulation. The hybrid framework consists of discrete event simulation (DES) as the core, but heterogeneous, interactive and intelligent (able to make decisions) agents replace traditional entities and resources. In addition, some of the cognitive processes and physiological aspects of agents are captured using system dynamics (SD) approach. The combination of DES, agent-based simulation (ABS) and SD allows a more "natural" representation of the complex dynamics in construction activities. The proposed hybrid framework was demonstrated using a hypothetical case study. In addition, due to the lack of application of factorial experiment approach in safety management simulation, the case study demonstrated sensitivity analysis and factorial experiment to guide future research. Copyright © 2015 Elsevier Ltd. All rights reserved.

  16. Comprehensive work plan and health and safety plan for the 7500 Area Contamination Site sampling at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Burman, S.N.; Landguth, D.C.; Uziel, M.S.; Hatmaker, T.L.; Tiner, P.F.

    1992-05-01

    As part of the Environmental Restoration Program sponsored by the US Department of Energy's Office of Environmental Restoration and Waste Management, this plan has been developed for the environmental sampling efforts at the 7500 Area Contamination Site, Oak Ridge National Laboratory (ORNL), Oak Ridge, Tennessee. This plan was developed by the Measurement Applications and Development Group (MAD) of the Health and Safety Research Division of ORNL and will be implemented by ORNL/MAD. Major components of the plan include (1) a quality assurance project plan that describes the scope and objectives of ORNL/MAD activities at the 7500 Area Contamination Site, assigns responsibilities, and provides emergency information for contingencies that may arise during field operations; (2) sampling and analysis sections; (3) a site-specific health and safety section that describes general site hazards, hazards associated with specific tasks, personnel protection requirements, and mandatory safety procedures; (4) procedures and requirements for equipment decontamination and responsibilities for generated wastes, waste management, and contamination control; and (5) a discussion of form completion and reporting required to document activities at the 7500 Area Contamination Site

  17. Comprehensive work plan and health and safety plan for the 7500 Area Contamination Site sampling at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Burman, S.N.; Landguth, D.C.; Uziel, M.S.; Hatmaker, T.L.; Tiner, P.F.

    1992-05-01

    As part of the Environmental Restoration Program sponsored by the US Department of Energy's Office of Environmental Restoration and Waste Management, this plan has been developed for the environmental sampling efforts at the 7500 Area Contamination Site, Oak Ridge National Laboratory (ORNL), Oak Ridge, Tennessee. This plan was developed by the Measurement Applications and Development Group (MAD) of the Health and Safety Research Division of ORNL and will be implemented by ORNL/MAD. Major components of the plan include (1) a quality assurance project plan that describes the scope and objectives of ORNL/MAD activities at the 7500 Area Contamination Site, assigns responsibilities, and provides emergency information for contingencies that may arise during field operations; (2) sampling and analysis sections; (3) a site-specific health and safety section that describes general site hazards, hazards associated with specific tasks, personnel protection requirements, and mandatory safety procedures; (4) procedures and requirements for equipment decontamination and responsibilities for generated wastes, waste management, and contamination control; and (5) a discussion of form completion and reporting required to document activities at the 7500 Area Contamination Site.

  18. COLLAGE 360: A Model of Person-Centered Care To Promote Health Among Older Adults.

    Science.gov (United States)

    Howard, Elizabeth P; Schreiber, Robert; Morris, John N; Russotto, Aline; Flashner-Fineman, Susan

    2016-01-01

    Health care leaders and providers have introduced the assumption the typical elder, even in the presence of complex, chronic disease and prevailing illness, is capable of assuming greater personal responsibility for their health care, with a shift from provider-centered to a person-centered model of care. For older adults who often and repeatedly face challenges managing and maintaining their health status, guidance and support is needed. In this study, COLLAGE 360 , a comprehensive assessment system and wellness coaching program that focuses on prevention and wellness, care coordination and self-management of health care was implemented in one continuing care retirement community. Following completion of two assessment tools via directed conversation with a wellness coach, older adults developed an individualized vitality plan that outlined life goals, supporting goals and action plans for goal achievement. Results from this program suggest engagement in the assessment and wellness coaching process via the COLLAGE 360 program translated into sample older adults sensing that they live in a more supportive environment when compared with elders not receiving any wellness coaching. In addition, the older adults had positive effects in the areas of mood, loneliness, social interaction, health status, and life satisfaction. Strategies to improve health and well being need an extended focus beyond the older adult's medical conditions and consider psychological, spiritual and social needs with personal preferences being paramount. These issues are foundational to a person-centered, health promotion approach needed among this population.

  19. Health and Safety Plan for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Van Hoesen, S.D.; Clark, C. Jr.; Burman, S.N.; Manis, L.W.; Barre, W.L.

    1993-12-01

    The Martin Marietta Energy Systems, Inc. (Energy Systems), policy is to provide a safe and healthful workplace for all employees and subcontractors. The accomplishment of this policy requires that operations at Waste Area Grouping (WAG) 6 at the Department of Energy (DOE) Oak Ridge National Laboratory are guided by an overall plan and consistent proactive approach to safety and health (S ampersand H) issues. The plan is written to utilize past experience and best management practices to minimize hazards to human health or the environment from events such as fires, explosions, falls, mechanical hazards, or any unplanned release of hazardous or radioactive materials to air, soil, or surface water This plan explains additional site-specific health and safety requirements such as Site Specific Hazards Evaluation Addendums (SSHEAs) to the Site Safety and Health Plan which should be used in concert with this plan and existing established procedures

  20. 3D MODELLING WITH THE SAMSUNG GEAR 360

    Directory of Open Access Journals (Sweden)

    L. Barazzetti

    2017-02-01

    Full Text Available The Samsung Gear 360 is a consumer grade spherical camera able to capture photos and videos. The aim of this work is to test the metric accuracy and the level of detail achievable with the Samsung Gear 360 coupled with digital modelling techniques based on photogrammetry/computer vision algorithms. Results demonstrate that the direct use of the projection generated inside the mobile phone or with Gear 360 Action Direction (the desktop software for post-processing have a relatively low metric accuracy. As results were in contrast with the accuracy achieved by using the original fisheye images (front and rear facing images in photogrammetric reconstructions, an alternative solution to generate the equirectangular projections was developed. A calibration aimed at understanding the intrinsic parameters of the two lenses camera, as well as their relative orientation, allowed one to generate new equirectangular projections from which a significant improvement of geometric accuracy has been achieved.

  1. Overview criteria for the environmental, safety and health evaluation of remedial action project planning

    International Nuclear Information System (INIS)

    Stenner, R.D.; Denham, D.H.

    1984-10-01

    Overview criteria (i.e., subject areas requiring review) for evaluating remedial action project plans with respect to environmental, safety and health issues were developed as part of a Department of Energy, Office of Operational Safety, technical support project. Nineteen elements were identified as criteria that should be addressed during the planning process of a remedial action (decontamination and decommissioning) project. The scope was interpreted broadly enough to include such environmental, safety and health issues as public image, legal obligation and quality assurance, as well as more obvious concerns such as those involving the direct protection of public and worker health. The nineteen elements are discussed along with suggested ways to use a data management software system to organize and report results

  2. 360-MAM-Affect: Sentiment Analysis with the Google Prediction API and EmoSenticNet

    Directory of Open Access Journals (Sweden)

    Eleanor Mulholland

    2015-08-01

    Full Text Available Online recommender systems are useful for media asset management where they select the best content from a set of media assets. We have developed an architecture for 360-MAM- Select, a recommender system for educational video content. 360-MAM-Select will utilise sentiment analysis and gamification techniques for the recommendation of media assets. 360-MAM-Select will increase user participation with digital content through improved video recommendations. Here, we discuss the architecture of 360-MAM-Select and the use of the Google Prediction API and EmoSenticNet for 360-MAM-Affect, 360-MAM-Select's sentiment analysis module. Results from testing two models for sentiment analysis, Sentiment Classifier (Google Prediction API and EmoSenticNetClassifer (Google Prediction API + EmoSenticNet are promising. Future work includes the implementation and testing of 360-MAM-Select on video data from YouTube EDU and Head Squeeze.

  3. WAG 2 remedial investigation and site investigation site-specific work plan/health and safety checklist for the soil and sediment task

    International Nuclear Information System (INIS)

    Holt, V.L.; Burgoa, B.B.

    1993-12-01

    This document is a site-specific work plan/health and safety checklist (WP/HSC) for a task of the Waste Area Grouping 2 Remedial Investigation and Site Investigation (WAG 2 RI ampersand SI). Title 29 CFR Part 1910.120 requires that a health and safety program plan that includes site- and task-specific information be completed to ensure conformance with health- and safety-related requirements. To meet this requirement, the health and safety program plan for each WAG 2 RI ampersand SI field task must include (1) the general health and safety program plan for all WAG 2 RI ampersand SI field activities and (2) a WP/HSC for that particular field task. These two components, along with all applicable referenced procedures, must be kept together at the work site and distributed to field personnel as required. The general health and safety program plan is the Health and Safety Plan for the Remedial Investigation and Site Investigation of Waste Area Grouping 2 at the Oak Ridge National Laboratory, Oak Ridge, Tennessee (ORNL/ER-169). The WP/HSCs are being issued as supplements to ORNL/ER-169

  4. B Plant Complex generator dangerous waste storage areas inspection plan: Revision 1

    International Nuclear Information System (INIS)

    Beam, T.G.

    1994-01-01

    This document contains the inspection plan for the <90 day dangerous/mixed waste storage areas and satellite accumulation areas at B Plant Complex. This inspection plan is designed to comply with all applicable federal, state and US Department of Energy-Richland Operations Office training requirements. In particular, the requirements of WAC 173-303 ''Dangerous Waste Regulations'' are met by this inspection plan. This inspection plan is designed to provide B Plant Complex with the records and documentation showing that the waste storage and handling program is in compliance with applicable regulations. The plan also includes the requirements for becoming a qualified inspector of waste storage areas and the responsibilities of various individuals and groups at B Plant Complex

  5. 20 CFR 408.360 - Can you cancel your request to withdraw your application?

    Science.gov (United States)

    2010-04-01

    ... application? 408.360 Section 408.360 Employees' Benefits SOCIAL SECURITY ADMINISTRATION SPECIAL BENEFITS FOR CERTAIN WORLD WAR II VETERANS Filing Applications Withdrawal of Application § 408.360 Can you cancel your... (c) A cancellation request received after we have approved your withdrawal must be filed no later...

  6. 31 CFR 360.60 - Payment to representative of an estate.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 2 2010-07-01 2010-07-01 false Payment to representative of an estate. 360.60 Section 360.60 Money and Finance: Treasury Regulations Relating to Money and Finance... court, other proof of qualification. (2) Except in the case of corporate fiduciaries, the evidence must...

  7. 21 CFR 1.360 - What are the record retention requirements?

    Science.gov (United States)

    2010-04-01

    ... food, including foods preserved by freezing, dehydrating, or being placed in a hermetically sealed... 21 Food and Drugs 1 2010-04-01 2010-04-01 false What are the record retention requirements? 1.360 Section 1.360 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES GENERAL...

  8. 29 CFR 779.360 - Classification of liquefied-petroleum-gas sales.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 3 2010-07-01 2010-07-01 false Classification of liquefied-petroleum-gas sales. 779.360... Establishments Liquefied-Petroleum-Gas and Fuel Oil Dealers § 779.360 Classification of liquefied-petroleum-gas... ultimate consumer of liquefied-petroleum-gas, whether delivered in portable cylinders or in bulk to the...

  9. 31 CFR 360.23 - Evidence.

    Science.gov (United States)

    2010-07-01

    ... than six months prior to the presentation of the bond. (c) Receiver in equity or similar court officer... BONDS, SERIES I Judicial Proceedings § 360.23 Evidence. (a) General. To establish the validity of... months prior to the presentation of the bond, there must also be submitted a certification from the clerk...

  10. 31 CFR 360.64 - Payment or reinvestment-voluntary guardian of an incapacitated person.

    Science.gov (United States)

    2010-07-01

    ... guardian of an incapacitated person. 360.64 Section 360.64 Money and Finance: Treasury Regulations Relating..., Absentees, et al. § 360.64 Payment or reinvestment—voluntary guardian of an incapacitated person. (a..., responsible for the owner's care and support may submit an application for recognition as voluntary guardian...

  11. Focus State Roadway Departure Safety Plans and High Friction Surface Treatments Peer Exchange : an RPSCB Peer Exchange

    Science.gov (United States)

    2014-08-01

    This report summarizes the Focus State Roadway Departure Safety Plans and High Friction Surface Treatments Peer Exchange, held in Birmingham, Alabama, sponsored by the Federal Highway Administration (FHWA) Office of Safetys Roadway Safety Professi...

  12. 49 CFR Appendix B to Part 222 - Alternative Safety Measures

    Science.gov (United States)

    2010-10-01

    .... 222, App. B Appendix B to Part 222—Alternative Safety Measures Introduction A public authority seeking... requirements associated with an SSM as listed in appendix A is revised or deleted, data or analysis supporting...); d. Photographic or video equipment deployed to capture images sufficient to document the violation...

  13. 29 CFR 2520.104b-2 - Summary plan description.

    Science.gov (United States)

    2010-07-01

    ... welfare plan), required by section 104(b)(1) of the Act, the administrator of an employee benefit plan... to participants and beneficiaries have been completed; and (ii) In the case of an employee welfare... Labor Regulations Relating to Labor (Continued) EMPLOYEE BENEFITS SECURITY ADMINISTRATION, DEPARTMENT OF...

  14. Food safety assurance systems: Microbiological testing, sampling plans, and microbiological criteria

    NARCIS (Netherlands)

    Zwietering, M.H.; Ross, T.; Gorris, L.G.M.

    2014-01-01

    Microbiological criteria give information about the quality or safety of foods. A key component of a microbiological criterion is the sampling plan. Considering: (1) the generally low level of pathogens that are deemed tolerable in foods, (2) large batch sizes, and (3) potentially substantial

  15. B Plant complex hazardous, mixed and low level waste certification plan

    International Nuclear Information System (INIS)

    Beam, T.G.

    1994-11-01

    This plan describes the administrative steps and handling methodology for certification of hazardous waste, mixed waste, and low level waste generated at B Plant Complex. The plan also provides the applicable elements of waste reduction and pollution prevention, including up front minimization and end product reduction of volume and/or toxicity. The plan is written to satisfy requirements for Hanford Site waste generators to have a waste certification program in place at their facility. This plan, as described, applies only to waste which is generated at, or is the responsibility of, B Plant Complex. The scope of this plan is derived from the requirements found in WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria

  16. B Plant complex hazardous, mixed and low level waste certification plan

    Energy Technology Data Exchange (ETDEWEB)

    Beam, T.G.

    1994-11-01

    This plan describes the administrative steps and handling methodology for certification of hazardous waste, mixed waste, and low level waste generated at B Plant Complex. The plan also provides the applicable elements of waste reduction and pollution prevention, including up front minimization and end product reduction of volume and/or toxicity. The plan is written to satisfy requirements for Hanford Site waste generators to have a waste certification program in place at their facility. This plan, as described, applies only to waste which is generated at, or is the responsibility of, B Plant Complex. The scope of this plan is derived from the requirements found in WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria.

  17. Groundwater well services site safety and health plan

    International Nuclear Information System (INIS)

    Tuttle, B.G.

    1996-08-01

    This Site Specific Health and Safety Plan covers well servicing in support of the Environmental Restoration Contractor Groundwater Project. Well servicing is an important part of environmental restoration activities supporting several pump and treat facilities and assisting in evaluation and servicing of various groundwater wells throughout the Hanford Site. Remediation of contaminated groundwater is a major part of the ERC project. Well services tasks help enhance groundwater extraction/injection as well as maintain groundwater wells for sampling and other hydrologic testing and information gathering

  18. HAZWOPER work plan and site safety and health plan for the Alpha characterization project at the solid waste storage area 4 bathtubbing trench at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    1994-07-01

    This work plan/site safety and health plan is for the alpha sampling project at the Solid Waste Storage Area 4 bathtubbing trench. The work will be conducted by the Oak Ridge National Laboratory (ORNL) Environmental Sciences Division and associated ORNL environmental, safety, and health support groups. This activity will fall under the scope of 29 CFR 1910.120, Hazardous Waste Operations and Emergency Response (HAZWOPER). The purpose of this document is to establish health and safety guidelines to be followed by all personnel involved in conducting work for this project. Work will be conducted in accordance with requirements as stipulated in the ORNL HAZWOPER Program Manual and applicable ORNL; Martin Marietta Energy Systems, Inc.; and U.S. Department of Energy policies and procedures. The levels of protection and the procedures specified in this plan are based on the best information available from historical data and preliminary evaluations of the area. Therefore, these recommendations represent the minimum health and safety requirements to be observed by all personnel engaged in this project. Unforeseeable site conditions or changes in scope of work may warrant a reassessment of the stated protection levels and controls. All adjustments to the plan must have prior approval by the safety and health disciplines signing the original plan

  19. Site health and safety plan/work plan for further characterization of waste drums at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Abston, J.P.; Burman, S.N.; Jones, D.L.

    1995-10-01

    The health and safety plan/work plan describes a strategy for characterizing the contents of 172 liquid waste and 33 solid waste drums. It also addresses the control measures that will be taken to (1) prevent or minimize any adverse impact on the environment or personnel safety and health and (2) meet standards that define acceptable management of hazardous and radioactive materials and wastes. When writing this document, the authors considered past experiences, recommendations, and best management practices to minimize possible hazards to human health or the environment from events such as fires, explosions, falls, mechanical hazards, or unplanned releases of hazardous or radioactive materials to air, soil, or surface water

  20. Connected vehicle pilot deployment program phase 1, safety management plan - Tampa (THEA).

    Science.gov (United States)

    2016-04-01

    This document presents the Safety Management Plan for the THEA Connected Vehicle (CV) Pilot Deployment. The THEA CV Pilot : Deployment goal is to advance and enable safe, interoperable, networked wireless communications among vehicles, the : infrastr...

  1. Should 360-Degree Feedback Be Used Only for Developmental Purposes?

    Science.gov (United States)

    Bracken, David W.; Dalton, Maxine A.; Jako, Robert A.; McCauley, Cynthia D.; Pollman, Victoria A.

    This booklet presents five papers that address the issue of whether 360-degree feedback (in which a manager or executive receives feedback on how bosses, peers, and direct reports see him or her) should be used only for development, or whether 360-degree feedback (also known as multi-rater feedback) should be used for administrative purposes such…

  2. 12 CFR Appendix F to Part 360 - Customer File Structure

    Science.gov (United States)

    2010-01-01

    ... 12 Banks and Banking 4 2010-01-01 2010-01-01 false Customer File Structure F Appendix F to Part... POLICY RESOLUTION AND RECEIVERSHIP RULES Pt. 360, App. F Appendix F to Part 360—Customer File Structure This is the structure of the data file to provide to the FDIC information related to each customer who...

  3. MODEL 9977 B(M)F-96 SAFETY ANALYSIS REPORT FOR PACKAGING

    Energy Technology Data Exchange (ETDEWEB)

    Abramczyk, G; Paul Blanton, P; Kurt Eberl, K

    2006-05-18

    This Safety Analysis Report for Packaging (SARP) documents the analysis and testing performed on and for the 9977 Shipping Package, referred to as the General Purpose Fissile Package (GPFP). The performance evaluation presented in this SARP documents the compliance of the 9977 package with the regulatory safety requirements for Type B packages. Per 10 CFR 71.59, for the 9977 packages evaluated in this SARP, the value of ''N'' is 50, and the Transport Index based on nuclear criticality control is 1.0. The 9977 package is designed with a high degree of single containment. The 9977 complies with 10 CFR 71 (2002), Department of Energy (DOE) Order 460.1B, DOE Order 460.2, and 10 CFR 20 (2003) for As Low As Reasonably Achievable (ALARA) principles. The 9977 also satisfies the requirements of the Regulations for the Safe Transport of Radioactive Material--1996 Edition (Revised)--Requirements. IAEA Safety Standards, Safety Series No. TS-R-1 (ST-1, Rev.), International Atomic Energy Agency, Vienna, Austria (2000). The 9977 package is designed, analyzed and fabricated in accordance with Section III of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, 1992 edition.

  4. 45-Day safety screening for Tank 241-B-102 auger samples, riser 1

    International Nuclear Information System (INIS)

    Bell, K.E.

    1994-01-01

    This is the 45-Day report for the fiscal year 1994 Tank 241-B-102 auger sampling characterization effort. Only one of the two planned auger samples was received by the 222-S Laboratory, however it was decided to begin the 45-day clock and issue a report based on receipt of the first auger sample. Included are copies of the differential scanning calorimetry (DSC) and thermogravimetric analysis (TGA) scans as requested. Also included is a copy of any immediate notification documentation, chain of custody forms, the hot cell work plan, extruded segment [auger] description sheets, and total alpha data. The TGA percent moisture results are below the safety criteria limit of 17% in a subsample taken approximately five minutes after extrusion and a second subsample taken from the lower half of the auger. Verbal and written notifications were made as prescribed. The DSC analysis of all subsamples indicates the presence of fraction exotherms, however the results are a factor of two or more below the notification limit of 523 Joules/gram (J/g). Total alpha results are all below the detection limit. In some cases, the tank characterization plan (TCP) accuracy and precision criteria are not met. If a re-run was not performed when a TCP quality control limit was not met, then reasons for not performing the re-run are provided

  5. MO-B-BRB-02: Maintain the Quality of Treatment Planning for Time-Constraint Cases

    International Nuclear Information System (INIS)

    Chang, J.

    2015-01-01

    The radiotherapy treatment planning process has evolved over the years with innovations in treatment planning, treatment delivery and imaging systems. Treatment modality and simulation technologies are also rapidly improving and affecting the planning process. For example, Image-guided-radiation-therapy has been widely adopted for patient setup, leading to margin reduction and isocenter repositioning after simulation. Stereotactic Body radiation therapy (SBRT) and Radiosurgery (SRS) have gradually become the standard of care for many treatment sites, which demand a higher throughput for the treatment plans even if the number of treatments per day remains the same. Finally, simulation, planning and treatment are traditionally sequential events. However, with emerging adaptive radiotherapy, they are becoming more tightly intertwined, leading to iterative processes. Enhanced efficiency of planning is therefore becoming more critical and poses serious challenge to the treatment planning process; Lean Six Sigma approaches are being utilized increasingly to balance the competing needs for speed and quality. In this symposium we will discuss the treatment planning process and illustrate effective techniques for managing workflow. Topics will include: Planning techniques: (a) beam placement, (b) dose optimization, (c) plan evaluation (d) export to RVS. Planning workflow: (a) import images, (b) Image fusion, (c) contouring, (d) plan approval (e) plan check (f) chart check, (g) sequential and iterative process Influence of upstream and downstream operations: (a) simulation, (b) immobilization, (c) motion management, (d) QA, (e) IGRT, (f) Treatment delivery, (g) SBRT/SRS (h) adaptive planning Reduction of delay between planning steps with Lean systems due to (a) communication, (b) limited resource, (b) contour, (c) plan approval, (d) treatment. Optimizing planning processes: (a) contour validation (b) consistent planning protocol, (c) protocol/template sharing, (d) semi

  6. MO-B-BRB-02: Maintain the Quality of Treatment Planning for Time-Constraint Cases

    Energy Technology Data Exchange (ETDEWEB)

    Chang, J. [New York Weill Cornell Medical Ctr (United States)

    2015-06-15

    The radiotherapy treatment planning process has evolved over the years with innovations in treatment planning, treatment delivery and imaging systems. Treatment modality and simulation technologies are also rapidly improving and affecting the planning process. For example, Image-guided-radiation-therapy has been widely adopted for patient setup, leading to margin reduction and isocenter repositioning after simulation. Stereotactic Body radiation therapy (SBRT) and Radiosurgery (SRS) have gradually become the standard of care for many treatment sites, which demand a higher throughput for the treatment plans even if the number of treatments per day remains the same. Finally, simulation, planning and treatment are traditionally sequential events. However, with emerging adaptive radiotherapy, they are becoming more tightly intertwined, leading to iterative processes. Enhanced efficiency of planning is therefore becoming more critical and poses serious challenge to the treatment planning process; Lean Six Sigma approaches are being utilized increasingly to balance the competing needs for speed and quality. In this symposium we will discuss the treatment planning process and illustrate effective techniques for managing workflow. Topics will include: Planning techniques: (a) beam placement, (b) dose optimization, (c) plan evaluation (d) export to RVS. Planning workflow: (a) import images, (b) Image fusion, (c) contouring, (d) plan approval (e) plan check (f) chart check, (g) sequential and iterative process Influence of upstream and downstream operations: (a) simulation, (b) immobilization, (c) motion management, (d) QA, (e) IGRT, (f) Treatment delivery, (g) SBRT/SRS (h) adaptive planning Reduction of delay between planning steps with Lean systems due to (a) communication, (b) limited resource, (b) contour, (c) plan approval, (d) treatment. Optimizing planning processes: (a) contour validation (b) consistent planning protocol, (c) protocol/template sharing, (d) semi

  7. Oak Ridge National Laboratory Health and Safety Long-Range Plan: Fiscal years 1989--1995

    Energy Technology Data Exchange (ETDEWEB)

    1989-06-01

    The health and safety of its personnel is the first concern of ORNL and its management. The ORNL Health and Safety Program has the responsibility for ensuring the health and safety of all individuals assigned to ORNL activities. This document outlines the principal aspects of the ORNL Health and Safety Long-Range Plan and provides a framework for management use in the future development of the health and safety program. Each section of this document is dedicated to one of the health and safety functions (i.e., health physics, industrial hygiene, occupational medicine, industrial safety, nuclear criticality safety, nuclear facility safety, transportation safety, fire protection, and emergency preparedness). Each section includes functional mission and objectives, program requirements and status, a summary of program needs, and program data and funding summary. Highlights of FY 1988 are included.

  8. Oak Ridge National Laboratory Health and Safety Long-Range Plan: Fiscal years 1989--1995

    International Nuclear Information System (INIS)

    1989-06-01

    The health and safety of its personnel is the first concern of ORNL and its management. The ORNL Health and Safety Program has the responsibility for ensuring the health and safety of all individuals assigned to ORNL activities. This document outlines the principal aspects of the ORNL Health and Safety Long-Range Plan and provides a framework for management use in the future development of the health and safety program. Each section of this document is dedicated to one of the health and safety functions (i.e., health physics, industrial hygiene, occupational medicine, industrial safety, nuclear criticality safety, nuclear facility safety, transportation safety, fire protection, and emergency preparedness). Each section includes functional mission and objectives, program requirements and status, a summary of program needs, and program data and funding summary. Highlights of FY 1988 are included

  9. Analisis Kepatuhan Supervisor Terhadap Implementasi Program Occupational Health & Safety (Ohs) Planned Inspection Di PT. Ccai

    OpenAIRE

    Sarah, Dewi; Ekawati, Ekawati; Widjasena, Baju

    2015-01-01

    The Government has issued Regulation Legislation No. 50 Year 2012 on Health and Safety Management System (SMK3). CCAI is a company that has implemented SMK3. The application of the CCAI SMK3 supported by K3 program one of them is OHS Planned Inspection. This study aimed to analyze the implementation of Occupational Health & Safety (OHS) program Planned Inspection in CCAI. The subjects of this study amounted to five people as the main informants and 2 as an informant triangulation. The res...

  10. Nordic Nuclear Safety Research 1994 - 2008: From standardized 4-year classics to customized R and B

    International Nuclear Information System (INIS)

    Bennerstedt, T.N.O.

    2011-10-01

    This is a presentation of NKS (Nordic Nuclear Safety Research), its work and achievements in the years 1994 - 2008, during which the author served as Nordic secretary and (later) as coordinator. NKS and the Nordic perspective are briefly introduced together with the NKS support structure, organization and administration: Owners, Board, Nordic secretary, Bureau and Secretariat. The author then embarks on a journey through the modern history of NKS work. The last two of the six fixed 4-year programs are described as regards planning, contents, project work, administration, dissemination of results, evaluations and conclusions. The trip continues to the land of R and B and the present (2011) structure of two general frameworks, namely, NKS-R: reactor safety, and NKS-B: emergency preparedness; each consisting of a set of flexible activities; hence, R and B. The reasoning behind this makeover is touched upon together with the new organization and simpler administration that developed. Major activities and the produced results are introduced and the evaluations summarized. The author's own conclusions and recommendations are followed by a short and subjective list of references. In a number of appendices some important background material has been compiled: bullet point versions of minutes of Owners Group and Board meetings; economic contributions and budgets; the NKS policy document; an overview of all NKS programs and evaluations; lists of R and B activities and funding; the author's personal remarks; a list of some NKS documents (other than technical reports and minutes); and a list of acronyms used in this report. (Author)

  11. Nordic Nuclear Safety Research 1994 - 2008: From standardized 4-year classics to customized R and B

    Energy Technology Data Exchange (ETDEWEB)

    Bennerstedt, T N.O. [TeknoTelje HB, Torhamn (Sweden)

    2011-10-15

    This is a presentation of NKS (Nordic Nuclear Safety Research), its work and achievements in the years 1994 - 2008, during which the author served as Nordic secretary and (later) as coordinator. NKS and the Nordic perspective are briefly introduced together with the NKS support structure, organization and administration: Owners, Board, Nordic secretary, Bureau and Secretariat. The author then embarks on a journey through the modern history of NKS work. The last two of the six fixed 4-year programs are described as regards planning, contents, project work, administration, dissemination of results, evaluations and conclusions. The trip continues to the land of R and B and the present (2011) structure of two general frameworks, namely, NKS-R: reactor safety, and NKS-B: emergency preparedness; each consisting of a set of flexible activities; hence, R and B. The reasoning behind this makeover is touched upon together with the new organization and simpler administration that developed. Major activities and the produced results are introduced and the evaluations summarized. The author's own conclusions and recommendations are followed by a short and subjective list of references. In a number of appendices some important background material has been compiled: bullet point versions of minutes of Owners Group and Board meetings; economic contributions and budgets; the NKS policy document; an overview of all NKS programs and evaluations; lists of R and B activities and funding; the author's personal remarks; a list of some NKS documents (other than technical reports and minutes); and a list of acronyms used in this report. (Author)

  12. Nordic Nuclear Safety Research 1994 - 2008: From standardized 4-year classics to customized R and B

    Energy Technology Data Exchange (ETDEWEB)

    Bennerstedt, T.N.O. (TeknoTelje HB, Torhamn (Sweden))

    2011-10-15

    This is a presentation of NKS (Nordic Nuclear Safety Research), its work and achievements in the years 1994 - 2008, during which the author served as Nordic secretary and (later) as coordinator. NKS and the Nordic perspective are briefly introduced together with the NKS support structure, organization and administration: Owners, Board, Nordic secretary, Bureau and Secretariat. The author then embarks on a journey through the modern history of NKS work. The last two of the six fixed 4-year programs are described as regards planning, contents, project work, administration, dissemination of results, evaluations and conclusions. The trip continues to the land of R and B and the present (2011) structure of two general frameworks, namely, NKS-R: reactor safety, and NKS-B: emergency preparedness; each consisting of a set of flexible activities; hence, R and B. The reasoning behind this makeover is touched upon together with the new organization and simpler administration that developed. Major activities and the produced results are introduced and the evaluations summarized. The author's own conclusions and recommendations are followed by a short and subjective list of references. In a number of appendices some important background material has been compiled: bullet point versions of minutes of Owners Group and Board meetings; economic contributions and budgets; the NKS policy document; an overview of all NKS programs and evaluations; lists of R and B activities and funding; the author's personal remarks; a list of some NKS documents (other than technical reports and minutes); and a list of acronyms used in this report. (Author)

  13. Patient safety in the care of mentally ill people in Switzerland: Action plan 2016

    Science.gov (United States)

    Richard, Aline; Mascherek, Anna C; Schwappach, David L B

    2017-01-01

    Background: Patient safety in mental healthcare has not attracted great attention yet, although the burden and the prevalence of mental diseases are high. The risk of errors with potential for harm of patients, such as aggression against self and others or non-drug treatment errors is particularly high in this vulnerable group. Aim: To develop priority topics and strategies for action to foster patient safety in mental healthcare. Method: The Swiss patient safety foundation together with experts conducted round table discussions and a Delphi questionnaire to define topics along the treatment pathway, and to prioritise these topics. Finally, fields of action were developed. Results: An action plan was developed including the definition and prioritization of 9 topics where errors may occur. A global rating task revealed errors concerning diagnostics and structural errors as most important. This led to the development of 4 fields of action (awareness raising, research, implementation, and education and training) including practice-oriented potential starting points to enhance patient safety. Conclusions: The action plan highlights issues of high concern for patient safety in mental healthcare. It serves as a starting point for the development of strategies for action as well as of concrete activities.

  14. Environment, safety, and health regulatory implementation plan

    International Nuclear Information System (INIS)

    1993-01-01

    To identify, document, and maintain the Uranium Mill Tailings Remedial Action (UMTRA) Project's environment, safety, and health (ES ampersand H) regulatory requirements, the US Department of Energy (DOE) UMTRA Project Office tasked the Technical Assistance Contractor (TAC) to develop a regulatory operating envelope for the UMTRA Project. The system selected for managing the UMTRA regulatory operating envelope data bass is based on the Integrated Project Control/Regulatory Compliance System (IPC/RCS) developed by WASTREN, Inc. (WASTREN, 1993). The IPC/RCS is a tool used for identifying regulatory and institutional requirements and indexing them to hardware, personnel, and program systems on a project. The IPC/RCS will be customized for the UMTRA Project surface remedial action and groundwater restoration programs. The purpose of this plan is to establish the process for implementing and maintaining the UMTRA Project's regulatory operating envelope, which involves identifying all applicable regulatory and institutional requirements and determining compliance status. The plan describes how the Project will identify ES ampersand H regulatory requirements, analyze applicability to the UMTRA Project, and evaluate UMTRA Project compliance status

  15. WebVR meets WebRTC: Towards 360-degree social VR experiences

    NARCIS (Netherlands)

    Gunkel, S.; Prins, M.J.; Stokking, H.M.; Niamut, O.A.

    2017-01-01

    Virtual Reality (VR) and 360-degree video are reshaping the media landscape, creating a fertile business environment. During 2016 new 360-degree cameras and VR headsets entered the consumer market, distribution platforms are being established and new production studios are emerging. VR is evermore

  16. 37 CFR 360.14 - Copies of claims.

    Science.gov (United States)

    2010-07-01

    ... Section 360.14 Patents, Trademarks, and Copyrights COPYRIGHT ROYALTY BOARD, LIBRARY OF CONGRESS SUBMISSION OF ROYALTY CLAIMS FILING OF CLAIMS TO ROYALTY FEES COLLECTED UNDER COMPULSORY LICENSE Satellite... royalty fees. ...

  17. Planning and architectural safety considerations in designing nuclear power plants

    International Nuclear Information System (INIS)

    Konsowa, Ahmed A.

    2009-01-01

    To achieve optimum safety and to avoid possible hazards in nuclear power plants, considering architectural design fundamentals and all operating precautions is mandatory. There are some planning and architectural precautions should be considered to achieve a high quality design and construction of nuclear power plant with optimum safety. This paper highlights predicted hazards like fire, terrorism, aircraft crash attacks, adversaries, intruders, and earthquakes, proposing protective actions against these hazards that vary from preventing danger to evacuating and sheltering people in-place. For instance; using safeguards program to protect against sabotage, theft, and diversion. Also, site and building well design focusing on escape pathways, emergency exits, and evacuation zones, and the safety procedures such as; evacuation exercises and sheltering processes according to different emergency classifications. In addition, this paper mentions some important codes and regulations that control nuclear power plants design, and assessment methods that evaluate probable risks. (author)

  18. Overheads, Safety Analysis and Engineering FY 1995 Site Support Program Plan WBS 6.3.5

    Energy Technology Data Exchange (ETDEWEB)

    DiVincenzo, E.P.

    1994-09-27

    The Safety Analysis & Engineering (SA&E) department provides core competency for safety analysis and risk documentation that supports achievement of the goals and mission as described in the Hanford Mission Plan, Volume I, Site Guidance (DOE-RL 1993). SA&E operations are integrated into the programs that plan and conduct safe waste management, environmental restoration, and operational activities. SA&E personnel are key members of task teams assigned to eliminate urgent risks and inherent threats that exist at the Hanford Site. Key to ensuring protection of public health and safety, and that of onsite workers, are the products and services provided by the department. SA&E will continue to provide a leadership role throughout the DOE complex with innovative, cost-effective approaches to ensuring safety during environmental cleanup operations. The SA&E mission is to provide support to direct program operations through safety analysis and risk documentation and to maintain an infrastructure responsive to the evolutionary climate at the Hanford Site. SA&E will maintain the appropriate skills mix necessary to fulfill the customers need to conduct all operations in a safe and cost-effective manner while ensuring the safety of the public and the onsite worker.

  19. Safety research in nuclear fuel cycle at PNC

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    This report collects the results of safety research in nuclear fuel cycle at Power Reactor and Nuclear Fuel Development Corporation, in order to answer to the Questionnaire of OECD/NEA. The Questionnaire request to include information concerning to research topic, description, main results (if available), reference documents, research institutes involved, sponsoring organization and other pertinent information about followings: a) Recently completed research projects. b) Ongoing (current) research projects. Achievements on following items are omitted by the request of OECD/NEA, uranium mining and milling, uranium refining and conversion to UF{sub 6}, uranium enrichment, fuel manufacturers, spent fuel storage, radioactive waste management, transport of radioactive materials, decommissioning. We select topics from the fields of a) nuclear installation, b) seismic, and c) PSA, in projects from frame of annual safety research plan for nuclear installations established by Nuclear Safety Commission. We apply for the above a) and b) projects as follows: a) Achievements in Safety Research, fiscal 1991-1995, b) fiscal 1996 Safety Research Achievements: Progress. (author)

  20. Safety research in nuclear fuel cycle at PNC

    International Nuclear Information System (INIS)

    1998-09-01

    This report collects the results of safety research in nuclear fuel cycle at Power Reactor and Nuclear Fuel Development Corporation, in order to answer to the Questionnaire of OECD/NEA. The Questionnaire request to include information concerning to research topic, description, main results (if available), reference documents, research institutes involved, sponsoring organization and other pertinent information about followings: a) Recently completed research projects. b) Ongoing (current) research projects. Achievements on following items are omitted by the request of OECD/NEA, uranium mining and milling, uranium refining and conversion to UF 6 , uranium enrichment, fuel manufacturers, spent fuel storage, radioactive waste management, transport of radioactive materials, decommissioning. We select topics from the fields of a) nuclear installation, b) seismic, and c) PSA, in projects from frame of annual safety research plan for nuclear installations established by Nuclear Safety Commission. We apply for the above a) and b) projects as follows: a) Achievements in Safety Research, fiscal 1991-1995, b) fiscal 1996 Safety Research Achievements: Progress. (author)

  1. B Plant Complex pollution prevention plan. Revision 1

    International Nuclear Information System (INIS)

    Beam, T.G.

    1994-01-01

    The US Department of Energy (DOE) has directed Westinghouse Hanford Company (WHC) to develop an effective strategy to minimize the generation of hazardous, radioactive, and mixed wastes at Hanford in compliance with state and federal regulations. WHC has formalized a pollution prevention program composed of management policies, management requirements and procedures. This plan addresses pollution prevention for B Plant Complex. A pollution prevention team is in place and has been assigned responsibility for implementing the plan. This plan includes actions and goals for reducing volume and toxicity of waste generated, as well as a basis for evaluation of progress. Descriptions of waste streams, current specific goals, general pollution prevention methods, and specific accomplishments are in the appendices of this plan

  2. Plan of Nordic research in nuclear safety 1994-97

    International Nuclear Information System (INIS)

    1993-04-01

    A new four-year Nordic research programme in the field of nuclear safety and radiation protection is to start in 1994 as a followup of several preceding Nordic programmes. It will include seven projects and a joint coordination function. The programme is intended to sustain a common understanding among safety authorities in the Nordic countries with respect to reactor safety and radiation protection. It mainly deals with questions that are actual within the Nordic region, but it may also include problems of concern to its eastern neighbours. Two of the projects deal with reactor safety, and one with radioactive waste. The other four projects are on environmental aspects: two of them deal with radioecology, and two with questions related to emergency preparedness. The programme is managed by the Nordic Committee for Safety Research, NKS, consisting of representatives from regulatory authorities, research bodies, and industry. Basic financing is provided by one consortium member from each of the five Nordic countries, whereby an annual budget of approximately 8 million Danish Kroner will be provided. Additional financing comes from sponsors interested in the programme as well as from those organizations taking part in the project work. Definite project plans are to be elaborated within the more general frames described in the present outline. The flexibility of the programme is enhanced by limiting the duration of individual activities to one or two years. This will make it possible to adjust the programme to actual needs in the Nordic countries. (au)

  3. 21 CFR 175.360 - Vinylidene chloride copolymer coatings for nylon film.

    Science.gov (United States)

    2010-04-01

    ... film. 175.360 Section 175.360 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND... coatings for nylon film. Vinylidene chloride copolymer coatings identified in this section and applied on nylon film may be safely used as food-contact surfaces, in accordance with the following prescribed...

  4. Updating a Strategic Highway Safety Plan : Learning from the Idaho Transportation Department (ITD) - Proceedings from the Federal Highway Administration's (FHWA) Highway Safety Peer-to-Peer Exchange Program

    Science.gov (United States)

    2009-10-01

    On November 4, 2009, ITDs Office of Highway Operations and Safety partnered with the FHWA Office of Safety to host a one-day peer exchange. This event focused on the update of Idahos Strategic Highway Safety Plan (SHSP), entitled Toward Zero...

  5. Phase II -- Photovoltaics for Utility Scale Applications (PVUSA): Safety and health action plan

    Energy Technology Data Exchange (ETDEWEB)

    Berg, K.

    1994-09-01

    To establish guidelines for the implementation and administration of an injury and illness prevention program for PVUSA and to assign specific responsibilities for the execution of the program. To provide a basic Safety and Health Action Plan (hereinafter referred to as Plan) that assists management, supervision, and project personnel in the recognition, evaluation, and control of hazardous activities and/or conditions within their respective areas of responsibility.

  6. Health and Safety Work Plan for Sampling Colloids in Waste Area Grouping 5 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Marsh, J.D.; McCarthy, J.F.

    1994-01-01

    This Work Plan/Site Safety and Health Plan (SSHP) and the attached work plan are for the performance of the colloid project at WAG 5. The work will be conducted by the Oak Ridge National Laboratory (ORNL) Environmental Sciences Division (ESD) and associated ORNL environmental, safety, and health support groups. The purpose of this document is to establish health and safety guidelines to be followed by all personnel involved in conducting work for this project. The levels of protection and the procedures specified in this plan are based on the best information available from historical data and preliminary evaluations of the area. Therefore, these recommendations represent the minimum health and safety requirements to be observed by all personnel engaged in this project

  7. Health and Safety Work Plan for Sampling Colloids in Waste Area Grouping 5 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Marsh, J.D.; McCarthy, J.F.

    1994-01-01

    This Work Plan/Site Safety and Health Plan (SSHP) and the attached work plan are for the performance of the colloid project at WAG 5. The work will be conducted by the Oak Ridge National Laboratory (ORNL) Environmental Sciences Division (ESD) and associated ORNL environmental, safety, and health support groups. The purpose of this document is to establish health and safety guidelines to be followed by all personnel involved in conducting work for this project. The levels of protection and the procedures specified in this plan are based on the best information available from historical data and preliminary evaluations of the area. Therefore, these recommendations represent the minimum health and safety requirements to be observed by all personnel engaged in this project.

  8. [B-BS and occupational health and safety management systems: the SGSL certification].

    Science.gov (United States)

    Calabrese, G; Candura, G

    2010-01-01

    The social costs deriving from the lack of occupational safety, which nowadays constitute approximately 2.8% of the GDP, tend not to come down despite the regulations, the inspections and the sanctions. The problems may be ascribed both to a shortage of systemic actions and to inappropriate training of the workers. Possible solutions are represented by the adoption of organizational models (D. Lgs. 81 art. 30) and by the implementation of protocols such as the Behavior-Based Safety (B-BS). Organisational and Management Models have been introduced with art. 30 D.Lgs. 81/2008 and with art. 6 D.Lgs. 231/2001. The comparison between their requisites and the ones specified by the OHSAS 18001 standards, confirms the partial overlapping of the Organizational Models with the Occupational Health & Safety Management Systems. Nevertheless such Systems are rarely adopted by Italian companies and their implementation still doesn't grant complete effectiveness. The B-BS protocol is proving to be a tool of extraordinary value to increase the level of safety, especially when used along with the known Health & Safety Management Systems.

  9. Safety margin evaluation concepts for plant Up rates and life extension. Results of the OECD/NEA/CSNI working group on Safety Margin Action Plan (SMAP)

    International Nuclear Information System (INIS)

    Belac, J

    2006-01-01

    This presentation summarizes results of the OECD/NEA/CSNI working group on Safety Margin Action Plan (SMAP) aimed to develop generalized safety margin concept and means of its quantification for the process of evaluating plant safety in the frame of plant life extension and power up rating activities to be used by OECD member countries. (author)

  10. Scleral depressed vitreous shaving, 360 laser, and perfluoropropane (C 3 F 8 for retinal detachment

    Directory of Open Access Journals (Sweden)

    Vivek Chaturvedi

    2014-01-01

    Full Text Available Purpose : To review the characteristics and outcomes of patients who underwent pars plana vitrectomy (PPV with scleral depressed vitreous shaving, 360 degree peripheral endolaser, and 14% C3F8 gas for rhegmatogenous retinal detachment (RRD. Materials and Methods : A retrospective review of a consecutive series of patients who underwent primary repair of RRD by PPV with scleral depressed vitreous shaving, 360 degree peripheral endolaser, and 14% perfluoropropane (C 3 F 8 was conducted. Patients with less than 3 months follow-up, previous retinal surgery, and higher than grade B proliferative vitreoretinopathy were excluded. Results : Ninety-one eyes were included in the study. The mean age was 60.1 years. The mean follow-up was 13.7 months. The macula was detached in 63% (58/91 of the eyes. The reattachment rate after one surgical procedure was 95% (86/91 while overall reattachment rate was 100%. There was no statistically significant difference between reattachment rates of superior, nasal/temporal, or inferior RRDs. The mean final best corrected visual acuity (BCVA was 20/40. Of all the patients, 66% of patients with macula-off RRDs had a final BCVA of 20/40 or better. Conclusions: PPV with scleral depressed vitreous shaving, 360 degree peripheral endolaser, and 14% C 3 F 8 leads to successful anatomical reattachment with visual improvement in patients with primary RRD.

  11. Management response plan for the Chemical Safety Vulnerability Working Group report. Volume 2

    International Nuclear Information System (INIS)

    1994-09-01

    The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 146 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. To address the facility-specific and site-specific vulnerabilities, responsible DOE and site-contractor line organizations have developed initial site response plans. These plans, presented as Volume 2 of this Management Response Plan, describe the actions needed to mitigate or eliminate the facility- and site-specific vulnerabilities identified by the CSV Working Group field verification teams. Initial site response plans are described for: Brookhaven National Lab., Hanford Site, Idaho National Engineering Lab., Lawrence Livermore National Lab., Los Alamos National Lab., Oak Ridge Reservation, Rocky Flats Plant, Sandia National Laboratories, and Savannah River Site

  12. Do 360-degree feedback survey results relate to patient satisfaction measures?

    Science.gov (United States)

    Hageman, Michiel G J S; Ring, David C; Gregory, Paul J; Rubash, Harry E; Harmon, Larry

    2015-05-01

    There is evidence that feedback from 360-degree surveys-combined with coaching-can improve physician team performance and quality of patient care. The Physicians Universal Leadership-Teamwork Skills Education (PULSE) 360 is one such survey tool that is used to assess work colleagues' and coworkers' perceptions of a physician's leadership, teamwork, and clinical practice style. The Clinician & Group-Consumer Assessment of Healthcare Providers and System (CG-CAHPS), developed by the US Department of Health and Human Services to serve as the benchmark for quality health care, is a survey tool for patients to provide feedback that is based on their recent experiences with staff and clinicians and soon will be tied to Medicare-based compensation of participating physicians. Prior research has indicated that patients and coworkers often agree in their assessment of physicians' behavioral patterns. The goal of the current study was to determine whether 360-degree, also called multisource, feedback provided by coworkers could predict patient satisfaction/experience ratings. A significant relationship between these two forms of feedback could enable physicians to take a more proactive approach to reinforce their strengths and identify any improvement opportunities in their patient interactions by reviewing feedback from team members. An automated 360-degree software process may be a faster, simpler, and less resource-intensive approach than telephoning and interviewing patients for survey responses, and it potentially could facilitate a more rapid credentialing or quality improvement process leading to greater fiscal and professional development gains for physicians. Our primary research question was to determine if PULSE 360 coworkers' ratings correlate with CG-CAHPS patients' ratings of overall satisfaction, recommendation of the physician, surgeon respect, and clarity of the surgeon's explanation. Our secondary research questions were to determine whether CG-CAHPS scores

  13. Safety and immunogenicity of a candidate parvovirus B19 vaccine.

    Science.gov (United States)

    Bernstein, David I; El Sahly, Hana M; Keitel, Wendy A; Wolff, Mark; Simone, Gina; Segawa, Claire; Wong, Susan; Shelly, Daniel; Young, Neal S; Dempsey, Walla

    2011-10-06

    Parvovirus B19 is an important human pathogen causing erythema infectiosum, transient aplastic crisis in individuals with underlying hemolytic disorders and hydropsfetalis. We therefore evaluated a parvovirus B19 virus like particle (VLP) vaccine. The safety and immunogenicity of a 25 μg dose of parvovirus B19 recombinant capsid; 2.5 and 25 μg doses of the recombinant capsid given with MF59; and saline placebo were assessed in healthy adults. Because of 3 unexplained cutaneous events the study was halted after enrollment of 43 subjects and before any subject received their third scheduled dose. The rashes developed 5-9 days after the first or second injection and were seen in one placebo recipient (without an injection site lesion) and two vaccine recipients (with injection site reactions). No clear cause was established. Other safety evaluations revealed mostly injection site reactions that were mild to moderate with an increase in pain in subjects receiving vaccine and MF59. After dose 2 the majority of vaccine recipients developed ELISA and neutralizing antibody to parvovirus B19. Given the possible severe consequences of parvovirus B19 infection, further development of a safe and effective vaccine continues to be important. Copyright © 2011 Elsevier Ltd. All rights reserved.

  14. Overheads, Safety Analysis and Engineering FY 1995 Site Support Program Plan WBS 6.3.5

    International Nuclear Information System (INIS)

    DiVincenzo, E.P.

    1994-01-01

    The Safety Analysis ampersand Engineering (SA ampersand E) department provides core competency for safety analysis and risk documentation that supports achievement of the goals and mission as described in the Hanford Mission Plan, Volume I, Site Guidance (DOE-RL 1993). SA ampersand E operations are integrated into the programs that plan and conduct safe waste management, environmental restoration, and operational activities. SA ampersand E personnel are key members of task teams assigned to eliminate urgent risks and inherent threats that exist at the Hanford Site. Key to ensuring protection of public health and safety, and that of onsite workers, are the products and services provided by the department. SA ampersand E will continue to provide a leadership role throughout the DOE complex with innovative, cost-effective approaches to ensuring safety during environmental cleanup operations. The SA ampersand E mission is to provide support to direct program operations through safety analysis and risk documentation and to maintain an infrastructure responsive to the evolutionary climate at the Hanford Site. SA ampersand E will maintain the appropriate skills mix necessary to fulfill the customers need to conduct all operations in a safe and cost-effective manner while ensuring the safety of the public and the onsite worker

  15. Environment, Safety, Health, and Quality Plan for the Buried Waste Integrated Demonstration Program

    International Nuclear Information System (INIS)

    Walker, S.

    1994-05-01

    The Buried Waste Integrated Demonstration (BWID) is a program funded by the US Department of Energy Office of Technology Development. BWID supports the applied research, development, demonstration, testing, and evaluation of a suite of advanced technologies that together form a comprehensive remediation system for the effective and efficient remediation of buried waste. This document describes the Environment, Safety, Health, and Quality requirements for conducting BWID activities at the Idaho National Engineering Laboratory. Topics discussed in this report, as they apply to BWID operations, include Federal, State of Idaho, and Environmental Protection Agency regulations, Health and Safety Plans, Quality Program Plans, Data Quality Objectives, and training and job hazard analysis. Finally, a discussion is given on CERCLA criteria and System and Performance audits as they apply to the BWID Program

  16. The Emergency Action Plan of the Spanish Nuclear Safety Council (CSN)

    International Nuclear Information System (INIS)

    Calvin Cuarteto, M.; Camarma, J. R.; Martin Calvarro, J. M

    2007-01-01

    The Spanish Nuclear safety Council (CSN) has assigned by law among others the function to coordinate the measures of support and answer to nuclear emergency situations for all the aspects related with nuclear safety and radiological protection. Integrating and coordinating the different organisations public and private companies whose aid is necessary for the fulfilment of the functions attributed to the Regulatory Body. In order to suitable perform this function, CSN has equipped itself with an Emergency Action Plan that structures the response organization, establishes responsibility levels, incorporates basic performance procedures and includes capabilities to face the nuclear and radiological emergencies considering the external supports, resulting from the collaboration agreements with public institutions and private companies. To accomplish the above mentioned Emergency Action Plan, CSN has established and implanted a formation and training and re-training program for the organization response for emergencies and has update an operative centre (Emergency Room called Salem), equipped with infrastructures, tools and communication and operative systems that incorporate the more advanced technologies available to date. (Author)

  17. Safety and Immunogenicity of a Candidate Parvovirus B19 Vaccine

    OpenAIRE

    Bernstein, David I; El Sahly, Hana M; Keitel, Wendy A; Wolff, Mark; Simone, Gina; Segawa, Claire; Wong, Susan; Shelly, Daniel; Young, Neal S; Dempsey, Walla

    2011-01-01

    Parvovirus B19 is an important human pathogen causing erythema infectiosum, transient aplastic crisis in individuals with underlying hemolytic disorders and hydrops fetalis. We therefore evaluated a parvovirus B19 virus like particle (VLP) vaccine. The safety and immunogenicity of a 25 μg dose of parvovirus B19 recombinant capsid; 2.5 and 25 μg doses of the recombinant capsid given with MF59; and saline placebo were assessed in healthy adults. Because of 3 unexplained cutaneous events the stu...

  18. B Plant treatment, storage, and disposal (TSD) units inspection plan

    International Nuclear Information System (INIS)

    Beam, T.G.

    1996-01-01

    This inspection plan is written to meet the requirements of WAC 173-303 for operations of a TSD facility. Owners/operators of TSD facilities are required to inspection their facility and active waste management units to prevent and/or detect malfunctions, discharges and other conditions potentially hazardous to human health and the environment. A written plan detailing these inspection efforts must be maintained at the facility in accordance with Washington Administrative Code (WAC), Chapter 173-303, ''Dangerous Waste Regulations'' (WAC 173-303), a written inspection plan is required for the operation of a treatment, storage and disposal (TSD) facility and individual TSD units. B Plant is a permitted TSD facility currently operating under interim status with an approved Part A Permit. Various operational systems and locations within or under the control of B Plant have been permitted for waste management activities. Included are the following TSD units: Cell 4 Container Storage Area; B Plant Containment Building; Low Level Waste Tank System; Organic Waste Tank System; Neutralized Current Acid Waste (NCAW) Tank System; Low Level Waste Concentrator Tank System. This inspection plan complies with the requirements of WAC 173-303. It addresses both general TSD facility and TSD unit-specific inspection requirements. Sections on each of the TSD units provide a brief description of the system configuration and the permitted waste management activity, a summary of the inspection requirements, and details on the activities B Plant uses to maintain compliance with those requirements

  19. MO-B-BRB-03: Systems Engineering Tools for Treatment Planning Process Optimization in Radiation Medicine

    International Nuclear Information System (INIS)

    Kapur, A.

    2015-01-01

    The radiotherapy treatment planning process has evolved over the years with innovations in treatment planning, treatment delivery and imaging systems. Treatment modality and simulation technologies are also rapidly improving and affecting the planning process. For example, Image-guided-radiation-therapy has been widely adopted for patient setup, leading to margin reduction and isocenter repositioning after simulation. Stereotactic Body radiation therapy (SBRT) and Radiosurgery (SRS) have gradually become the standard of care for many treatment sites, which demand a higher throughput for the treatment plans even if the number of treatments per day remains the same. Finally, simulation, planning and treatment are traditionally sequential events. However, with emerging adaptive radiotherapy, they are becoming more tightly intertwined, leading to iterative processes. Enhanced efficiency of planning is therefore becoming more critical and poses serious challenge to the treatment planning process; Lean Six Sigma approaches are being utilized increasingly to balance the competing needs for speed and quality. In this symposium we will discuss the treatment planning process and illustrate effective techniques for managing workflow. Topics will include: Planning techniques: (a) beam placement, (b) dose optimization, (c) plan evaluation (d) export to RVS. Planning workflow: (a) import images, (b) Image fusion, (c) contouring, (d) plan approval (e) plan check (f) chart check, (g) sequential and iterative process Influence of upstream and downstream operations: (a) simulation, (b) immobilization, (c) motion management, (d) QA, (e) IGRT, (f) Treatment delivery, (g) SBRT/SRS (h) adaptive planning Reduction of delay between planning steps with Lean systems due to (a) communication, (b) limited resource, (b) contour, (c) plan approval, (d) treatment. Optimizing planning processes: (a) contour validation (b) consistent planning protocol, (c) protocol/template sharing, (d) semi

  20. MO-B-BRB-03: Systems Engineering Tools for Treatment Planning Process Optimization in Radiation Medicine

    Energy Technology Data Exchange (ETDEWEB)

    Kapur, A. [Long Island Jewish Medical Center (United States)

    2015-06-15

    The radiotherapy treatment planning process has evolved over the years with innovations in treatment planning, treatment delivery and imaging systems. Treatment modality and simulation technologies are also rapidly improving and affecting the planning process. For example, Image-guided-radiation-therapy has been widely adopted for patient setup, leading to margin reduction and isocenter repositioning after simulation. Stereotactic Body radiation therapy (SBRT) and Radiosurgery (SRS) have gradually become the standard of care for many treatment sites, which demand a higher throughput for the treatment plans even if the number of treatments per day remains the same. Finally, simulation, planning and treatment are traditionally sequential events. However, with emerging adaptive radiotherapy, they are becoming more tightly intertwined, leading to iterative processes. Enhanced efficiency of planning is therefore becoming more critical and poses serious challenge to the treatment planning process; Lean Six Sigma approaches are being utilized increasingly to balance the competing needs for speed and quality. In this symposium we will discuss the treatment planning process and illustrate effective techniques for managing workflow. Topics will include: Planning techniques: (a) beam placement, (b) dose optimization, (c) plan evaluation (d) export to RVS. Planning workflow: (a) import images, (b) Image fusion, (c) contouring, (d) plan approval (e) plan check (f) chart check, (g) sequential and iterative process Influence of upstream and downstream operations: (a) simulation, (b) immobilization, (c) motion management, (d) QA, (e) IGRT, (f) Treatment delivery, (g) SBRT/SRS (h) adaptive planning Reduction of delay between planning steps with Lean systems due to (a) communication, (b) limited resource, (b) contour, (c) plan approval, (d) treatment. Optimizing planning processes: (a) contour validation (b) consistent planning protocol, (c) protocol/template sharing, (d) semi

  1. Integrated operations plan for the MFTF-B Mirror Fusion Test Facility. Volume II. Integrated operations plan

    Energy Technology Data Exchange (ETDEWEB)

    1981-12-01

    This document defines an integrated plan for the operation of the Lawrence Livermore National Laboratory (LLNL) Mirror Fusion Test Facility (MFTF-B). The plan fulfills and further delineates LLNL policies and provides for accomplishing the functions required by the program. This plan specifies the management, operations, maintenance, and engineering support responsibilities. It covers phasing into sustained operations as well as the sustained operations themselves. Administrative and Plant Engineering support, which are now being performed satisfactorily, are not part of this plan unless there are unique needs.

  2. Integrated operations plan for the MFTF-B Mirror Fusion Test Facility. Volume II. Integrated operations plan

    International Nuclear Information System (INIS)

    1981-12-01

    This document defines an integrated plan for the operation of the Lawrence Livermore National Laboratory (LLNL) Mirror Fusion Test Facility (MFTF-B). The plan fulfills and further delineates LLNL policies and provides for accomplishing the functions required by the program. This plan specifies the management, operations, maintenance, and engineering support responsibilities. It covers phasing into sustained operations as well as the sustained operations themselves. Administrative and Plant Engineering support, which are now being performed satisfactorily, are not part of this plan unless there are unique needs

  3. Comprehensive work plan and health and safety plan for the 7500 Area Contamination Site sampling at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    Burman, S.N.; Landguth, D.C.; Uziel, M.S.; Hatmaker, T.L.; Tiner, P.F.

    1992-05-01

    As part of the Environmental Restoration Program sponsored by the US Department of Energy`s Office of Environmental Restoration and Waste Management, this plan has been developed for the environmental sampling efforts at the 7500 Area Contamination Site, Oak Ridge National Laboratory (ORNL), Oak Ridge, Tennessee. This plan was developed by the Measurement Applications and Development Group (MAD) of the Health and Safety Research Division of ORNL and will be implemented by ORNL/MAD. Major components of the plan include (1) a quality assurance project plan that describes the scope and objectives of ORNL/MAD activities at the 7500 Area Contamination Site, assigns responsibilities, and provides emergency information for contingencies that may arise during field operations; (2) sampling and analysis sections; (3) a site-specific health and safety section that describes general site hazards, hazards associated with specific tasks, personnel protection requirements, and mandatory safety procedures; (4) procedures and requirements for equipment decontamination and responsibilities for generated wastes, waste management, and contamination control; and (5) a discussion of form completion and reporting required to document activities at the 7500 Area Contamination Site.

  4. Safety and immunogenicity of two Haemophilus influenzae type b ...

    African Journals Online (AJOL)

    Objectives. Haemophilus influenzae type b (Hib) infection remains a major public health problem inthe developing world. We evaluated the safety and immunogenicity of a new PRP-CRM197 conjugate Hib vaccine (Vaxem Hib, Chiron Vacdnes), compared with theHibTITER vaccine (WyethLederle Vaccines), following the ...

  5. Reflux and Belching After 270 Degree Versus 360 Degree Laparoscopic Posterior Fundoplication

    NARCIS (Netherlands)

    Broeders, Joris A.; Bredenoord, Albert J.; Hazebroek, Eric J.; Broeders, Ivo A.; Gooszen, Hein G.; Smout, André J.

    2012-01-01

    Objective: To investigate differences in effects of 270 degrees (270 degrees LPF) and 360 degrees laparoscopic posterior fundoplication (360 degrees LPF) on reflux characteristics and belching. Background: Three hundred sixty degrees LPF greatly reduces the ability of the stomach to vent ingested

  6. Structural and Thermal Safety Analysis Report for the Type B Radioactive Waste Transport Package

    Energy Technology Data Exchange (ETDEWEB)

    Kim, D. H.; Seo, K. S.; Lee, J. C.; Bang, K. S

    2007-09-15

    We carried out structural safety evaluation for the type B radioactive waste transport package. Requirements for type B packages according to the related regulations such as IAEA Safety Standard Series No. TS-R-1, Korea Most Act. 2001-23 and US 10 CFR Part 71 were evaluated. General requirements for packages such as those for a lifting attachment, a tie-down attachment and pressure condition were considered. For the type B radioactive waste transport package, the structural, thermal and containment analyses were carried out under the normal transport conditions. Also the safety analysis were conducted under the accidental transport conditions. The 9 m drop test, 1 m puncture test, fire test and water immersion test under the accidental transport conditions were consecutively done. The type B radioactive waste transport packages were maintained the structural and thermal integrities.

  7. Using Groupware to Gather and Analyze Intelligence in a Public Setting: Development of Integral Safety Plans in an Electronic Meeting

    NARCIS (Netherlands)

    Rouwette, E.A.J.A.; Vennix, J.A.M.; Vriens, D.J.

    2003-01-01

    This chapter focuses on the use of groupware to support local governments in activities in the intelligence cycle. Local governments in The Netherlands have a central role in developing integral safety plans for their district. However, in the implementation of safety plans the contribution of

  8. Developing tools for the safety specification in risk management plans: lessons learned from a pilot project.

    Science.gov (United States)

    Cooper, Andrew J P; Lettis, Sally; Chapman, Charlotte L; Evans, Stephen J W; Waller, Patrick C; Shakir, Saad; Payvandi, Nassrin; Murray, Alison B

    2008-05-01

    Following the adoption of the ICH E2E guideline, risk management plans (RMP) defining the cumulative safety experience and identifying limitations in safety information are now required for marketing authorisation applications (MAA). A collaborative research project was conducted to gain experience with tools for presenting and evaluating data in the safety specification. This paper presents those tools found to be useful and the lessons learned from their use. Archive data from a successful MAA were utilised. Methods were assessed for demonstrating the extent of clinical safety experience, evaluating the sensitivity of the clinical trial data to detect treatment differences and identifying safety signals from adverse event and laboratory data to define the extent of safety knowledge with the drug. The extent of clinical safety experience was demonstrated by plots of patient exposure over time. Adverse event data were presented using dot plots, which display the percentages of patients with the events of interest, the odds ratio, and 95% confidence interval. Power and confidence interval plots were utilised for evaluating the sensitivity of the clinical database to detect treatment differences. Box and whisker plots were used to display laboratory data. This project enabled us to identify new evidence-based methods for presenting and evaluating clinical safety data. These methods represent an advance in the way safety data from clinical trials can be analysed and presented. This project emphasises the importance of early and comprehensive planning of the safety package, including evaluation of the use of epidemiology data.

  9. Performance comparison of AV1, HEVC, and JVET video codecs on 360 (spherical) video

    Science.gov (United States)

    Topiwala, Pankaj; Dai, Wei; Krishnan, Madhu; Abbas, Adeel; Doshi, Sandeep; Newman, David

    2017-09-01

    This paper compares the coding efficiency performance on 360 videos, of three software codecs: (a) AV1 video codec from the Alliance for Open Media (AOM); (b) the HEVC Reference Software HM; and (c) the JVET JEM Reference SW. Note that 360 video is especially challenging content, in that one codes full res globally, but typically looks locally (in a viewport), which magnifies errors. These are tested in two different projection formats ERP and RSP, to check consistency. Performance is tabulated for 1-pass encoding on two fronts: (1) objective performance based on end-to-end (E2E) metrics such as SPSNR-NN, and WS-PSNR, currently developed in the JVET committee; and (2) informal subjective assessment of static viewports. Constant quality encoding is performed with all the three codecs for an unbiased comparison of the core coding tools. Our general conclusion is that under constant quality coding, AV1 underperforms HEVC, which underperforms JVET. We also test with rate control, where AV1 currently underperforms the open source X265 HEVC codec. Objective and visual evidence is provided.

  10. RAMONA-4B development for SBWR safety studies

    Energy Technology Data Exchange (ETDEWEB)

    Rohatgi, U.S.; Aronson, A.L.; Cheng, H.S.; Khan, H.J.; Mallen, A.N.

    1993-12-31

    The Simplified Boiling Water Reactor (SBWR) is a revolutionary design of a boiling-water reactor. The reactor is based on passive safety systems such as natural circulation, gravity flow, pressurized gas, and condensation. SBWR has no active systems, and the flow in the vessel is by natural circulation. There is a large chimney section above the core to provide a buoyancy head for natural circulation. The reactor can be shut down by either of four systems; namely, scram, Fine Motion Control Rod Drive (FMCRD), Alternate Rod Insertion (ARI), and Standby Liquid Control System (SLCS). The safety injection is by gravity drain from the Gravity Driven Cooling System (GDCS) and Suppression Pool (SP). The heat sink is through two types of heat exchangers submerged in the tank of water. These heat exchangers are the Isolation Condenser (IC) and the Passive Containment Cooling System (PCCS). The RAMONA-4B code has been developed to simulate the normal operation, reactivity transients, and to address the instability issues for SBWR. The code has a three-dimensional neutron kinetics coupled to multiple parallel-channel thermal-hydraulics. The two-phase thermal hydraulics is based on a nonhomogeneous nonequilibrium drift-flux formulation. It employs an explicit integration to solve all state equations (except for neutron kinetics) in order to predict the instability without numerical damping. The objective of this project is to develop a Sun SPARC and IBM RISC 6000 based RAMONA-4B code for applications to SBWR safety analyses, in particular for stability and ATWS studies.

  11. RAMONA-4B development for SBWR safety studies

    International Nuclear Information System (INIS)

    Rohatgi, U.S.; Aronson, A.L.; Cheng, H.S.; Khan, H.J.; Mallen, A.N.

    1993-01-01

    The Simplified Boiling Water Reactor (SBWR) is a revolutionary design of a boiling-water reactor. The reactor is based on passive safety systems such as natural circulation, gravity flow, pressurized gas, and condensation. SBWR has no active systems, and the flow in the vessel is by natural circulation. There is a large chimney section above the core to provide a buoyancy head for natural circulation. The reactor can be shut down by either of four systems; namely, scram, Fine Motion Control Rod Drive (FMCRD), Alternate Rod Insertion (ARI), and Standby Liquid Control System (SLCS). The safety injection is by gravity drain from the Gravity Driven Cooling System (GDCS) and Suppression Pool (SP). The heat sink is through two types of heat exchangers submerged in the tank of water. These heat exchangers are the Isolation Condenser (IC) and the Passive Containment Cooling System (PCCS). The RAMONA-4B code has been developed to simulate the normal operation, reactivity transients, and to address the instability issues for SBWR. The code has a three-dimensional neutron kinetics coupled to multiple parallel-channel thermal-hydraulics. The two-phase thermal hydraulics is based on a nonhomogeneous nonequilibrium drift-flux formulation. It employs an explicit integration to solve all state equations (except for neutron kinetics) in order to predict the instability without numerical damping. The objective of this project is to develop a Sun SPARC and IBM RISC 6000 based RAMONA-4B code for applications to SBWR safety analyses, in particular for stability and ATWS studies

  12. Safety demonstration test (SR-1/S1C-1) plan of HTTR (Contract research)

    Energy Technology Data Exchange (ETDEWEB)

    Nakagawa, Shigeaki; Sakaba, Nariaki; Takada, Eiji; Tachibana, Yukio; Saito, Kenji; Furusawa, Takayuki; Sawa, Kazuhiro [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment

    2003-03-01

    Safety demonstration tests in the HTTR (High Temperature Engineering Test Reactor) will be carried out in order to verify inherent safety features of the HTGR (High Temperature Gas-cooled Reactor). The first phase of the safety demonstration tests includes the reactivity insertion test by the control rod withdrawal and the coolant flow reduction test by the circulator trip. In the second phase, accident simulation tests will be conducted. By comparison of their experimental and analytical results, the prediction capability of the safety evaluation codes such as the core and the plant dynamics codes will be improved and verified, which will contribute to establish the safety design and the safety evaluation technologies of the HTGRs. The results obtained through its safety demonstration tests will be also utilised for the establishment of the safety design guideline, the safety evaluation guideline, etc. This paper describes the test program of the overall safety demonstration tests and the test method, the test conditions and the results of the pre-test analysis of the reactivity insertion test and the partial gas circulator trip test planned in March 2003. (author)

  13. Masterplan, plan B, bobler og spirer

    DEFF Research Database (Denmark)

    Nielsen, Tom

    2017-01-01

    Artiklen introducerer en række begreber, der kan bruges til at forstå og tænke midlertidige byudvikling og inddragende byudvikling med. Samtidig giver artiklen en byhistorisk kontekst for arbejdet med midlertidighed i arkitekturen og bydannelsen. Artiklen er struktureret med udgangspunkt i to cen...... to centrale begrebspar: Masterplan vs. Plan B og Bobler vs. Spirer. De overordnede pointer og internationale tendenser eksemplificeres og diskuteres med en række eksempler fra planlægningen af Aarhus....

  14. The strategic plan for the Committee on the Safety of Nuclear Installations

    International Nuclear Information System (INIS)

    2000-01-01

    Following the request from the NEA that all the committees should develop Strategic Plans and the report of the Effectiveness Review Group (ERG) on the effectiveness of CSNI's activities, CSNI created a Strategic Planning Group to review their working processes. In developing a five year rolling Strategic Plan, the Group has considered the need for more top-down direction by CSNI, stricter control on time limited Task Groups and improved communications including timely review and publication of reports. The Strategic Planning Group, after reviewing the current work structure of CSNI and the current technical issues as laid out in the SESAR series of reports and the CNRA report on Regulatory Effectiveness, have made the following recommendations. The basic elements of the CSNI will continue to be the Principal Working Groups, which will be known in future simply as Working Groups. The number of Working Groups and their areas of expertise will be reviewed periodically when the strategic plan undergoes a review. It is recommended that this Plan be reviewed every five years. In order to provide better top-down direction by the CSNI, it is recommended that a small Programme Review Group (PRG) be created. The PRG will assist the CSNI Bureau to review proposals from the Working Groups, and enable the review of major reports to ensure high quality. To ensure timely management of projects and reviews of proposals and reports it is recommended that CSNI have a second full meeting in early summer. It is recommended that Special Expert Groups (SEGs) be created reporting directly to CSNI. These Groups would deal with issues that cut across the disciplines of more than one Working Group and be assigned clear time-limited mandates. The creation of SEGs on Fuel Safety Margins and on Human and Organisational Factors is proposed at this time. Restructuring of the five Principal Working Groups into four Working Groups is recommended. This would be accomplished by merging the former

  15. A General Procedure to Assess the Internal Structure of a Noncognitive Measure--The Student360 Insight Program (S360) Time Management Scale. Research Report. ETS RR-11-42

    Science.gov (United States)

    Ling, Guangming; Rijmen, Frank

    2011-01-01

    The factorial structure of the Time Management (TM) scale of the Student 360: Insight Program (S360) was evaluated based on a national sample. A general procedure with a variety of methods was introduced and implemented, including the computation of descriptive statistics, exploratory factor analysis (EFA), and confirmatory factor analysis (CFA).…

  16. Standard plans for timber bridge superstructures

    Science.gov (United States)

    James P. Wacker; Matthew S. Smith

    2001-01-01

    These standardized bridge plans are for superstructures consisting of treated timber. Seven superstructure types are includes: five longitudinal and two transverse deck systems. Both HS520 and HS25 loadings are included, along with L/360 and L/500 deflection criteria.

  17. Water reactor safety research program. A description of current and planned research

    International Nuclear Information System (INIS)

    1978-07-01

    The U.S. Nuclear Regulatory Commission (NRC) sponsors confirmatory safety research on lightwater reactors in support of the NRC regulatory program. The principal responsibility of the NRC, as implemented through its regulatory program is to ensure that public health, public safety, and the environment are adequately protected. The NRC performs this function by defining conditions for the use of nuclear power and by ensuring through technical review, audit, and follow-up that these conditions are met. The NRC research program provides technical information, independent of the nuclear industry, to aid in discharging these regulatory responsibilities. The objectives of NRC's research program are the following: (1) to maintain a confirmatory research program that supports assurance of public health and safety, and public confidence in the regulatory program, (2) to provide objectively evaluated safety data and analytical methods that meet the needs of regulatory activities, (3) to provide better quantified estimates of the margins of safety for reactor systems, fuel cycle facilities, and transportation systems, (4) to establish a broad and coherent exchange of safety research information with other Federal agencies, industry, and foreign organization. Current and planned research toward these goals is described

  18. A Phase-1b study of tivantinib (ARQ 197) in adult patients with hepatocellular carcinoma and cirrhosis

    Science.gov (United States)

    Santoro, A; Simonelli, M; Rodriguez-Lope, C; Zucali, P; Camacho, L H; Granito, A; Senzer, N; Rimassa, L; Abbadessa, G; Schwartz, B; Lamar, M; Savage, R E; Bruix, J

    2013-01-01

    Background: The mesenchymal-epithelial transition factor (MET) receptor is dysregulated in hepatocellular carcinoma (HCC), and tivantinib (ARQ 197) is an oral, selective, MET inhibitor. Methods: This Phase-1b study assessed tivantinib safety as primary objective in patients with previously treated HCC and Child-Pugh A or B liver cirrhosis. Patients received oral tivantinib 360 mg twice daily until disease progression or unacceptable toxicity. Results: Among 21 HCC patients, common drug-related adverse events (AEs) were neutropaenia, anaemia, asthenia, leucopaenia, anorexia, diarrhoea, and fatigue. No drug-related worsening of liver function or performance status occurred, but one Child-Pugh B patient experienced drug-related bilirubin increase. Four patients had drug-related serious AEs, including one neutropaenia-related death. Haematologic toxicities were more frequent than in previous tivantinib studies but were manageable with prompt therapy. Best response was stable disease (median, 5.3 months) in 9 of 16 evaluable patients (56%). Median time to progression was 3.3 months. Conclusion: Tivantinib demonstrated a manageable safety profile and preliminary antitumour activity in patients with HCC and Child-Pugh A or B cirrhosis. PMID:23287988

  19. Can we Use Low-Cost 360 Degree Cameras to Create Accurate 3d Models?

    Science.gov (United States)

    Barazzetti, L.; Previtali, M.; Roncoroni, F.

    2018-05-01

    360 degree cameras capture the whole scene around a photographer in a single shot. Cheap 360 cameras are a new paradigm in photogrammetry. The camera can be pointed to any direction, and the large field of view reduces the number of photographs. This paper aims to show that accurate metric reconstructions can be achieved with affordable sensors (less than 300 euro). The camera used in this work is the Xiaomi Mijia Mi Sphere 360, which has a cost of about 300 USD (January 2018). Experiments demonstrate that millimeter-level accuracy can be obtained during the image orientation and surface reconstruction steps, in which the solution from 360° images was compared to check points measured with a total station and laser scanning point clouds. The paper will summarize some practical rules for image acquisition as well as the importance of ground control points to remove possible deformations of the network during bundle adjustment, especially for long sequences with unfavorable geometry. The generation of orthophotos from images having a 360° field of view (that captures the entire scene around the camera) is discussed. Finally, the paper illustrates some case studies where the use of a 360° camera could be a better choice than a project based on central perspective cameras. Basically, 360° cameras become very useful in the survey of long and narrow spaces, as well as interior areas like small rooms.

  20. Linac upgrade plan for the KEK B-Factory

    International Nuclear Information System (INIS)

    Enomoto, Atsushi; Anami, Shozo; Kamitani, Takuya; Hanaki, Hirofumi; Shidara, Tetsuo; Sato, Isamu

    1993-01-01

    In the KEK B-Factory plan, e+/e- collider rings with 3.5- GeV positions and 8-GeV electrons are being considered, and full-energy injection from the existing linac is required. The acceleration energy of the linac must be upgraded from 2.5 to 8 GeV. The most effective way has been searched from several points of view, such as the beam quality, ease of beam handling, and construction. This article describes the basic plan of the energy upgrade and recent progress regarding this project

  1. Implementing 360° Quantified Self for childhood obesity: feasibility study and experiences from a weight loss camp in Qatar.

    Science.gov (United States)

    Fernandez-Luque, Luis; Singh, Meghna; Ofli, Ferda; Mejova, Yelena A; Weber, Ingmar; Aupetit, Michael; Jreige, Sahar Karim; Elmagarmid, Ahmed; Srivastava, Jaideep; Ahmedna, Mohamed

    2017-04-13

    The explosion of consumer electronics and social media are facilitating the rise of the Quantified Self (QS) movement where millions of users are tracking various aspects of their daily life using social media, mobile technology, and wearable devices. Data from mobile phones, wearables and social media can facilitate a better understanding of the health behaviors of individuals. At the same time, there is an unprecedented increase in childhood obesity rates worldwide. This is a cause for grave concern due to its potential long-term health consequences (e.g., diabetes or cardiovascular diseases). Childhood obesity is highly prevalent in Qatar and the Gulf Region. In this study we examine the feasibility of capturing quantified-self data from social media, wearables and mobiles within a weight lost camp for overweight children in Qatar. Over 50 children (9-12 years old) and parents used a wide range of technologies, including wearable sensors (actigraphy), mobile and social media (WhatsApp and Instagram) to collect data related to physical activity and food, that was then integrated with physiological data to gain insights about their health habits. In this paper, we report about the acquired data and visualization techniques following the 360° Quantified Self (360QS) methodology (Haddadi et al., ICHI 587-92, 2015). 360QS allows for capturing insights on the behavioral patterns of children and serves as a mechanism to reinforce education of their mothers via social media. We also identified human factors, such as gender and cultural acceptability aspects that can affect the implementation of this technology beyond a feasibility study. Furthermore, technical challenges regarding the visualization and integration of heterogeneous and sparse data sets are described in the paper. We proved the feasibility of using 360QS in childhood obesity through this pilot study. However, in order to fully implement the 360QS technology careful planning and integration in the health

  2. Health and Safety Plan for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    Van Hoesen, S.D.; Clark, C. Jr.; Burman, S.N. [Oak Ridge National Lab., TN (United States); Manis, L.W.; Barre, W.L. [Analysas Corp., Oak Ridge, TN (United States)

    1993-12-01

    The Martin Marietta Energy Systems, Inc. (Energy Systems), policy is to provide a safe and healthful workplace for all employees and subcontractors. The accomplishment of this policy requires that operations at Waste Area Grouping (WAG) 6 at the Department of Energy (DOE) Oak Ridge National Laboratory are guided by an overall plan and consistent proactive approach to safety and health (S&H) issues. The plan is written to utilize past experience and best management practices to minimize hazards to human health or the environment from events such as fires, explosions, falls, mechanical hazards, or any unplanned release of hazardous or radioactive materials to air, soil, or surface water This plan explains additional site-specific health and safety requirements such as Site Specific Hazards Evaluation Addendums (SSHEAs) to the Site Safety and Health Plan which should be used in concert with this plan and existing established procedures.

  3. B plant/WESF integrated annual safety appraisal

    International Nuclear Information System (INIS)

    Anderson, J.K.

    1990-12-01

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

  4. Management response plan for the Chemical Safety Vulnerability Working Group report. Volume 1

    International Nuclear Information System (INIS)

    1994-09-01

    The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 146 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 1 contains a discussion of the chemical safety improvements planned or already underway at DOE sites to correct facility or site-specific vulnerabilities. The main part of the report is a discussion of each of the programmatic deficiencies; a description of the tasks to be accomplished; the specific actions to be taken; and the organizational responsibilities for implementation

  5. 44 CFR 360.2 - Description of program.

    Science.gov (United States)

    2010-10-01

    ... for travel and per diem expenses of students selected by the States for courses reflecting... Section 360.2 Emergency Management and Assistance FEDERAL EMERGENCY MANAGEMENT AGENCY, DEPARTMENT OF... costs and participant's travel and per diem. These specifics of date, place, and costs will be required...

  6. 12 CFR 563b.125 - Must my board of directors adopt a plan of conversion?

    Science.gov (United States)

    2010-01-01

    ... 12 Banks and Banking 5 2010-01-01 2010-01-01 false Must my board of directors adopt a plan of... board of directors adopt a plan of conversion? Prior to filing an application for conversion, your board of directors must adopt a plan of conversion that conforms to §§ 563b.320 through 563b.485 and 563b...

  7. Project health and safety plan for the Gunite and Associated Tanks at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Abston, J.P.

    1997-04-01

    The Lockheed Martin Energy Systems, Inc. (Energy Systems) policy is to provide a safe and healthful workplace for all employees and subcontractors. The accomplishment of this policy requires that operations at the Gunite and Associated Tanks (GAAT) in the North and South Tank Farms (NTF and STF) at the Department of Energy (DOE) Oak Ridge National Laboratory are guided by an overall plan and consistent proactive approach to health and safety (H and S) issues. The policy and procedures in this plan apply to all GAAT operations in the NTF and STF. The provisions of this plan are to be carried out whenever activities identifies s part of the GAAT are initiated that could be a threat to human health or the environment. This plan implements a policy and establishes criteria for the development of procedures for day-to-day operations to prevent or minimize any adverse impact to the environment and personnel safety and health and to meet standards that define acceptable management of hazardous and radioactive materials and wastes. The plan is written to utilize past experience and best management practices in order to minimize hazards to human health or the environment from events such as fires, explosions, falls, mechanical hazards, or any unplanned release of hazardous or radioactive materials to the air. This plan explains additional task-specific health and safety requirements such as the Site Safety and health Addendum and Activity Hazard Analysis, which should be used in concert with this plan and existing established procedures

  8. Project health and safety plan for the Gunite and Associated Tanks at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Abston, J.P.

    1997-04-01

    The Lockheed Martin Energy Systems, Inc. (Energy Systems) policy is to provide a safe and healthful workplace for all employees and subcontractors. The accomplishment of this policy requires that operations at the Gunite and Associated Tanks (GAAT) in the North and South Tank Farms (NTF and STF) at the Department of Energy (DOE) Oak Ridge National Laboratory are guided by an overall plan and consistent proactive approach to health and safety (H and S) issues. The policy and procedures in this plan apply to all GAAT operations in the NTF and STF. The provisions of this plan are to be carried out whenever activities identifies s part of the GAAT are initiated that could be a threat to human health or the environment. This plan implements a policy and establishes criteria for the development of procedures for day-to-day operations to prevent or minimize any adverse impact to the environment and personnel safety and health and to meet standards that define acceptable management of hazardous and radioactive materials and wastes. The plan is written to utilize past experience and best management practices in order to minimize hazards to human health or the environment from events such as fires, explosions, falls, mechanical hazards, or any unplanned release of hazardous or radioactive materials to the air. This plan explains additional task-specific health and safety requirements such as the Site Safety and health Addendum and Activity Hazard Analysis, which should be used in concert with this plan and existing established procedures.

  9. 12 CFR Appendix G to Part 360 - Deposit-Customer Join File Structure

    Science.gov (United States)

    2010-01-01

    ..._Code Relationship CodeThe code indicating how the customer is related to the account. Possible values... 12 Banks and Banking 4 2010-01-01 2010-01-01 false Deposit-Customer Join File Structure G Appendix... GENERAL POLICY RESOLUTION AND RECEIVERSHIP RULES Pt. 360, App. G Appendix G to Part 360—Deposit-Customer...

  10. Environmental Management Waste Management Facility (EMWMF) Site-Specific Health and Safety Plan, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Flynn, N.C. Bechtel Jacobs

    2008-04-21

    The Bechtel Jacobs Company LLC (BJC) policy is to provide a safe and healthy workplace for all employees and subcontractors. The implementation of this policy requires that operations of the Environmental Management Waste Management Facility (EMWMF), located one-half mile west of the U.S. Department of Energy (DOE) Y-12 National Security Complex, be guided by an overall plan and consistent proactive approach to environment, safety and health (ES&H) issues. The BJC governing document for worker safety and health, BJC/OR-1745, 'Worker Safety and Health Program', describes the key elements of the BJC Safety and Industrial Hygiene (IH) programs, which includes the requirement for development and implementation of a site-specific Health and Safety Plan (HASP) where required by regulation (refer also to BJC-EH-1012, 'Development and Approval of Safety and Health Plans'). BJC/OR-1745, 'Worker Safety and Health Program', implements the requirements for worker protection contained in Title 10 Code of Federal Regulations (CFR) Part 851. The EMWMF site-specific HASP requirements identifies safe operating procedures, work controls, personal protective equipment, roles and responsibilities, potential site hazards and control measures, site access requirements, frequency and types of monitoring, site work areas, decontamination procedures, and outlines emergency response actions. This HASP will be available on site for use by all workers, management and supervisors, oversight personnel and visitors. All EMWMF assigned personnel will be briefed on the contents of this HASP and will be required to follow the procedures and protocols as specified. The policies and procedures referenced in this HASP apply to all EMWMF operations activities. In addition the HASP establishes ES&H criteria for the day-to-day activities to prevent or minimize any adverse effect on the environment and personnel safety and health and to meet standards that define acceptable

  11. The technical approach: The IAEA action plan on the safety of radiation sources

    International Nuclear Information System (INIS)

    Bilbao, A.; Wrixon, A.; Ortiz-Lopez, P.

    2001-01-01

    As part of the measures to strengthen international co-operation in nuclear, radiation and waste safety, the report refers to the implementation of the Action Plan for the Safety of Radiation Sources and the Security of Radioactive Materials. Starting with background information, the report references the main results of the Dijon Conference and of General Conference resolution GC(42)/RES/12 in September 1998, describing the actions taken by the Secretariat pursuant such resolution and also by the Board of Governors, in its sessions of March and September 1999, as well as by the General Conference, in October 1999 when by resolution GC(43)/RES/10 the Action Plan was endorsed and the Secretariat was urged to implement it. Finally, the report provides information on the status of implementation of the seven areas covered by the Action Plan and on the suggested further actions to be carried out for its implementation taking into account the decisions of the Board in its meeting of 11 September 2000 and the resolutions GC(44)/RES/11, GC(44)/RES/13 and GC(44)/RES/16 of the forty-fourth regular session of the General Conference. (author)

  12. Draft IAEA Action Plan on Nuclear Safety. Report by the Director General

    International Nuclear Information System (INIS)

    Amano, Y.

    2011-01-01

    In accordance with paragraphs 23 and 24 of the Declaration adopted by the Ministerial Conference on Nuclear Safety held on 20-24 June 2011, the Director General was requested to prepare and present to the Board of Governors and the General Conference at their September 2011 meetings a report on the Ministerial Conference and a draft Action Plan, building on the Ministerial Declaration, the conclusions and recommendations of the working sessions of the Ministerial Conference and the expertise and knowledge available therein, and to facilitate consultations among Member States on the draft Action Plan. This draft Action Plan is the result of an extensive process of consultations with Member States and responds to the request contained in the Ministerial Declaration.

  13. The Dutch Bicycle Master Plan and road safety : measures to be taken.

    NARCIS (Netherlands)

    Noordzij, P.C. & Blokpoel, A.

    1998-01-01

    The Bicycle Master Plan was launched in 1990 and concluded in 1996. To mark its conclusion, a study was carried out to assess developments in road safety for cyclists. An overview of future measures was also compiled. Since 1950, there have been three broad periods: (1) 1950-1975: an increase in the

  14. Comprehensive development plans for the low- and intermediate-level radioactive waste disposal facility in Korea and preliminary safety assessment

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Kang Il; Kim, Jin Hyeong; Kwon, Mi Jin; Jeong, Mi Seon; Hong, Sung Wook; Park, Jin Beak [Korea Radioactive Waste Agency, Daejeon (Korea, Republic of)

    2016-12-15

    The disposal facility in Gyeongju is planning to dispose of 800,000 packages of low- and intermediate- level radioactive waste. This facility will be developed as a complex disposal facility that has various types of disposal facilities and accompanying management. In this study, based on the comprehensive development plan of the disposal facility, a preliminary post-closure safety assessment is performed to predict the phase development of the total capacity for the 800,000 packages to be disposed of at the site. The results for each scenario meet the performance target of the disposal facility. The assessment revealed that there is a significant impact of the inventory of intermediate-level radionuclide waste on the safety evaluation. Due to this finding, we introduce a disposal limit value for intermediate-level radioactive waste. With stepwise development of safety case, this development plan will increase the safety of disposal facilities by reducing uncertainties within the future development of the underground silo disposal facilities.

  15. 26 CFR 54.4980B-2 - Plans that must comply.

    Science.gov (United States)

    2010-04-01

    ... requirements apply only to the type and level of coverage under the cafeteria plan or other flexible benefit... section 125) or other flexible benefit arrangement. (See paragraphs (b) through (e) in Q&A-8 of this... considered to be the provision of health care and so is considered a group health plan. (c) Whether a benefit...

  16. INFLUENCE OF PLANNING, ORGANIZATIONAL CHARACTERISTICS AND REGULATION ON ROAD TRAFFIC SAFETY OF PEDESTRIANS

    Directory of Open Access Journals (Sweden)

    G. M. Kuharenok

    2011-01-01

    Full Text Available The paper presents results of research on planning, organizational characteristics and regulation modes at  the regulated pedestrian crossings, located out of crossroads in the street and road network of Minsk. Some regularities pertaining to the influence of the investigated characteristics on road traffic safety of pedestrians are revealed in the paper. Practical offers on increase of road traffic safety of pedestrians in the Republic of Belarus have been developed on the basis of the executed investigations and cited in the paper. 

  17. Quarterly report on the Ferrocyanide Safety Program for the period ending, March 31, 1995

    International Nuclear Information System (INIS)

    Cash, R.J.; Meacham, J.E.; Dukelow, G.T.

    1995-04-01

    This quarterly report provides a status of the activities underway on the Ferrocyanide Safety Issue at the Hanford Site, including actions in response to Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 90-7 (FR 1990). In March 1991, a DNFSB implementation plan (Cash 1991) responding to the six parts of Recommendation 90-7 was prepared and sent to the DNFSB. A Ferrocyanide Safety Program Plan addressing the total Ferrocyanide Safety Program, including the six parts of DNFSB Recommendation 90-7, was released in October 1994 (DOE 1994b). Activities in the program plan are underway or have been completed, and the status of each is described in Sections 2.0 and 3.0 of this report

  18. 37 CFR 360.5 - Copies of claims.

    Science.gov (United States)

    2010-07-01

    ... Section 360.5 Patents, Trademarks, and Copyrights COPYRIGHT ROYALTY BOARD, LIBRARY OF CONGRESS SUBMISSION OF ROYALTY CLAIMS FILING OF CLAIMS TO ROYALTY FEES COLLECTED UNDER COMPULSORY LICENSE Cable Claims... hand delivery or by mail, file an original and one copy of the claim to cable royalty fees. ...

  19. Tank 241-B-106 tank characterization plan. Revision 1

    International Nuclear Information System (INIS)

    Homi, C.S.

    1995-01-01

    This document is a plan that identifies the information needed to address relevant issues concerning short-term and long-term safe storage and long-term management of Single-Shell Tank (SST) 241-B-106

  20. Swedish Nuclear Power Inspectorate, Office of Reactor Safety. Research plans for the period 1997-1999

    International Nuclear Information System (INIS)

    1997-02-01

    Office of Reactor Safety research is carried out within the following areas: Safety evaluation, Safety analysis, MTO, Materials and chemistry, Non-Destructive Testing, Strength of materials, Thermohydraulics, Nuclear fuel, Serious accidents and Process control. Research is carried out to fulfill SKIs overall goals in accordance with the directives from the Swedish government and parliament, in particular to be a driving force in safety related work when justified by operating experience, research results and technical progress, towards licensees as well as in international cooperation in safety; to promote the maintenance and development of competence in the safety related work at the SKI as well as the licensees and generally in the country, and as a specific role for the Office of Reactor Safety as designated in the internal routines to take initiative to encourage and carry out research into areas of importance for the Office as well as ensuring that research results are disseminated and used both within SKI and in the general work concerning nuclear safety. Research efforts within the Office of Reactor safety are carried out in the form of separate projects which form part of the priority work plans. Project managers, the necessary personnel resources and the budget for each year are included in the Annual Plan and the work is followed up in the same manner as other efforts. Research is performed in different ways, that can vary from laboratory studies to more consultative efforts, and be organised in many different ways such as examination projects, post-graduate studies, work sponsored at research institutes and companies in Sweden and abroad, collaboration in larger international projects, and participation in conferences which provide an important contribution to keeping SKI personnel informed within their specialist areas

  1. 19 CFR 360.104 - Steel import monitoring.

    Science.gov (United States)

    2010-04-01

    ... ANALYSIS SYSTEM § 360.104 Steel import monitoring. (a) Throughout the duration of the licensing requirement... include import quantity (metric tons), import Customs value (U.S. $), and average unit value ($/metric ton... and will also present a range of historical data for comparison purposes. Provision of this aggregate...

  2. Safety Evaluation Report on Tennessee Valley Authority: Browns Ferry Nuclear Performance Plan: Browns Ferry Unit 2 restart

    International Nuclear Information System (INIS)

    1989-04-01

    This safety evaluation report (SER) on the information submitted by the Tennessee Valley Authority (TVA) in its Nuclear Performance Plan, through Revision 2, for the Browns Ferry Nuclear Power Station and in supporting documents has been prepared by the US Nuclear Regulatory Commission staff. The plan addresses the plant-specific concerns requiring resolution before startup of Unit 2. The staff will inspect implementation of those programs. Where systems are common to Units 1 and 2 or to Units 2 and 3, the staff safety evaluations of those systems are included herein. 3 refs

  3. German risk study, phase (DRS-B)

    International Nuclear Information System (INIS)

    Werner, W.

    1992-01-01

    The first risk investigations were primarily intended to estimate the risk of accidents in nuclear power plants and to compare it with other natural risk and civilization risks. The American reactor safety study WASH 1400 and the German risk study phase A (DRS-A) gave a detailed analyses of the offsite consequences of accidents, especially the magnitude and frequency of health damage for the population. Risk investigations today are primarily used to examine the design of safety systems and to further develop the entire safety concept. Safety investigations have shown that nuclear power plants still possess safety reserves if safety systems do not operate as planned. These safety reserves can be exploited in the sense of a further development of safety by plant internal emergency measures. One purpose of risk analyses is to identify such measures and to evaluate their feasibility and effectiveness. The most important goals of the investigations in DRS-B were: Identification of vulnerabilities and possible safety improvements; determination of safety reserves during accident sequences exceeding the design limits; evaluation of plant internal emergency measures. Thus, goals in phase B compared with phase A have changed from investigations of the magnitude of damage to detailed analysis of the plant systems response under accident conditions. The magnitude of possible fission product releases is also determined in phase B. However, no new accident consequence calculations are performed. Figs and tabs

  4. Interim-status groundwater monitoring plan for the 216-B-63 trench

    Energy Technology Data Exchange (ETDEWEB)

    Sweeney, M.D.

    1995-02-09

    This document outlines the groundwater monitoring plan, under RCRA regulations in 40 CFR 265 Subpart F and WAC173-300-400, for the 216-B-63 Trench. This interim status facility is being sampled under detection monitoring criteria and this plan provides current program conditions and requirements.

  5. Managing "Academic Value": The 360-Degree Perspective

    Science.gov (United States)

    Wilson, Margaret R.; Corr, Philip J.

    2018-01-01

    The "raison d'etre" of all universities is to create and deliver "academic value", which we define as the sum total of the contributions from the 360-degree "angles" of the academic community, including all categories of staff, as well as external stakeholders (e.g. regulatory, commercial, professional and community…

  6. Health and Safety Plan for Operations Performed for the Environmental Restoration Program: Task, Characterization of Potential Waste Sources at Auxiliary Reactor Area-1 Operable Unit 5--07 site ARA-02

    International Nuclear Information System (INIS)

    Pickett, S.L.; Morton, S.L.

    1992-06-01

    This document constitutes the generic health and safety plan for the Environmental Restoration Program (ERP). It addresses the health and safety requirements of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA); Occupational Safety and Health Administration (OSHA) 29 CFR 1910.120 standard; and EG ampersand G Idaho, Inc. This plan is a guide to individuals who must complete a health and safety plan for a task performed for the ERP. It contains a task specific addendum that, when completed, specifically addresses task specific health and safety issues. This health and safety plan reduces the time it takes to write a task specific health and safety plan by providing discussions of requirements, guidance on where specific information is located, and specific topics in the Addendum that must be discussed at a task level. This format encourages a complete task specific health and safety plan and a standard for all health and safety plans written for ERP

  7. Health and Safety Plan for Operations Performed for the Environmental Restoration Program: Task, Characterization of Potential Waste Sources at Auxiliary Reactor Area-1 Operable Unit 5--07 site ARA-02

    Energy Technology Data Exchange (ETDEWEB)

    Pickett, S.L.; Morton, S.L.

    1992-06-01

    This document constitutes the generic health and safety plan for the Environmental Restoration Program (ERP). It addresses the health and safety requirements of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA); Occupational Safety and Health Administration (OSHA) 29 CFR 1910.120 standard; and EG G Idaho, Inc. This plan is a guide to individuals who must complete a health and safety plan for a task performed for the ERP. It contains a task specific addendum that, when completed, specifically addresses task specific health and safety issues. This health and safety plan reduces the time it takes to write a task specific health and safety plan by providing discussions of requirements, guidance on where specific information is located, and specific topics in the Addendum that must be discussed at a task level. This format encourages a complete task specific health and safety plan and a standard for all health and safety plans written for ERP.

  8. Health and Safety Plan for Operations Performed for the Environmental Restoration Program: Task, Characterization of Potential Waste Sources at Auxiliary Reactor Area-1 Operable Unit 5--07 site ARA-02

    Energy Technology Data Exchange (ETDEWEB)

    Pickett, S.L.; Morton, S.L.

    1992-06-01

    This document constitutes the generic health and safety plan for the Environmental Restoration Program (ERP). It addresses the health and safety requirements of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA); Occupational Safety and Health Administration (OSHA) 29 CFR 1910.120 standard; and EG&G Idaho, Inc. This plan is a guide to individuals who must complete a health and safety plan for a task performed for the ERP. It contains a task specific addendum that, when completed, specifically addresses task specific health and safety issues. This health and safety plan reduces the time it takes to write a task specific health and safety plan by providing discussions of requirements, guidance on where specific information is located, and specific topics in the Addendum that must be discussed at a task level. This format encourages a complete task specific health and safety plan and a standard for all health and safety plans written for ERP.

  9. River Protection Project Integrated safety management system phase II verification review plan - 7/29/99

    International Nuclear Information System (INIS)

    SHOOP, D.S.

    1999-01-01

    The purpose of this review is to verify the implementation status of the Integrated Safety Management System (ISMS) for the River Protection Project (RPP) facilities managed by Fluor Daniel Hanford, Inc. (FDH) and operated by Lockheed Martin Hanford Company (LMHC). This review will also ascertain whether within RPP facilities and operations the work planning and execution processes are in place and functioning to effectively protect the health and safety of the workers, public, environment, and federal property over the RPP life cycle. The RPP ISMS should support the Hanford Strategic Plan (DOERL-96-92) to safely clean up and manage the site's legacy waste and deploy science and technology while incorporating the ISMS central theme to ''Do work safely'' and protect human health and the environment

  10. WAG 2 remedial investigation and site investigation site-specific work plan/health and safety checklist for the sediment transport modeling task

    International Nuclear Information System (INIS)

    Holt, V.L.; Baron, L.A.

    1994-05-01

    This site-specific Work Plan/Health and Safety Checklist (WP/HSC) is a supplement to the general health and safety plan (HASP) for Waste Area Grouping (WAG) 2 remedial investigation and site investigation (WAG 2 RI ampersand SI) activities [Health and Safety Plan for the Remedial Investigation and Site Investigation of Waste Area Grouping 2 at the Oak Ridge National Laboratory, Oak Ridge, Tennessee (ORNL/ER-169)] and provides specific details and requirements for the WAG 2 RI ampersand SI Sediment Transport Modeling Task. This WP/HSC identifies specific site operations, site hazards, and any recommendations by Oak Ridge National Laboratory (ORNL) health and safety organizations [i.e., Industrial Hygiene (IH), Health Physics (HP), and/or Industrial Safety] that would contribute to the safe completion of the WAG 2 RI ampersand SI. Together, the general HASP for the WAG 2 RI ampersand SI (ORNL/ER-169) and the completed site-specific WP/HSC meet the health and safety planning requirements specified by 29 CFR 1910.120 and the ORNL Hazardous Waste Operations and Emergency Response (HAZWOPER) Program Manual. In addition to the health and safety information provided in the general HASP for the WAG 2 RI ampersand SI, details concerning the site-specific task are elaborated in this site-specific WP/HSC, and both documents, as well as all pertinent procedures referenced therein, will be reviewed by all field personnel prior to beginning operations

  11. Tank 241-AZ-102 tank characterization plan

    International Nuclear Information System (INIS)

    Schreiber, R.D.

    1995-01-01

    The Defense Nuclear Facilities Safety Board has advised the DOE to concentrate the near-term sampling and analysis activities on identification and resolution of safety issues. The Data Quality Objective (DQO) process was chosen as a tool to be used in the resolution of safety issues. As a result, a revision in the Federal Facilities Agreement and Consent Order (Tri-Party Agreement) milestone M-44 has been made, which states that ''A Tank Characterization Plan (TCP) will also be developed for each double-shell tank (DST) and single-shell tank (SST) using the DQO process ... Development of TCPs by the DQO process is intended to allow users to ensure their needs will be met and that resources are devoted to gaining only necessary information''. This document satisfies that requirement for tank 241-AZ-102 (AZ-102) sampling activities. Tank AZ-102 is currently a non-Watch List tank, so the only DQOs applicable to this tank are the safety screening DQO and the compatibility DQO, as described below. The current contents of Tank AZ-102, as of October 31, 1994, consisted of 3,600 kL (950 kgal) of dilute non-complexed waste and aging waste from PUREX (NCAW, neutralized current acid waste). Tank AZ-102 is expected to have two primary layers. The bottom layer is composed of 360 kL of sludge, and the top layer is composed of 3,240 kL of supernatant, with a total tank waste depth of approximately 8.9 meters

  12. Bechtel Hanford, Inc./ERC team health and safety plan Environmental Restoration Disposal Facility operations

    International Nuclear Information System (INIS)

    Turney, S.R.

    1996-02-01

    A comprehensive safety and health program is essential for reducing work-related injuries and illnesses while maintaining a safe and health work environment. This document establishes Bechtel Hanford, Inc. (BHI)/Environmental Restoration Contractor (ERC) team requirements, policies, and procedures and provides preliminary guidance to the Environmental Restoration Disposal Facility (ERDF) subcontractor for use in preparing essential safety and health documents. This health and safety plan (HASP) defines potential safety and health issues associated with operating and maintaining the ERDF. A site-specific HASP shall be developed by the ERDF subcontractor and shall be implemented before operations and maintenance work can proceed. An activity hazard analysis (AHA) shall also be developed to provide procedures to identify, assess, and control hazards or potential incidents associated with specific operations and maintenance activities

  13. 37 CFR 360.2 - Time of filing.

    Science.gov (United States)

    2010-07-01

    ... ROYALTY CLAIMS FILING OF CLAIMS TO ROYALTY FEES COLLECTED UNDER COMPULSORY LICENSE Cable Claims § 360.2... compulsory license royalty fees for secondary transmissions of one or more of its works during the preceding calendar year shall file a claim to such fees with the Copyright Royalty Board. No royalty fees shall be...

  14. Planning the Unplanned Experiment: Assessing the Efficacy of Standards for Safety Critical Software

    Science.gov (United States)

    Graydon, Patrick J.; Holloway, C. Michael

    2015-01-01

    We need well-founded means of determining whether software is t for use in safety-critical applications. While software in industries such as aviation has an excellent safety record, the fact that software aws have contributed to deaths illustrates the need for justi ably high con dence in software. It is often argued that software is t for safety-critical use because it conforms to a standard for software in safety-critical systems. But little is known about whether such standards `work.' Reliance upon a standard without knowing whether it works is an experiment; without collecting data to assess the standard, this experiment is unplanned. This paper reports on a workshop intended to explore how standards could practicably be assessed. Planning the Unplanned Experiment: Assessing the Ecacy of Standards for Safety Critical Software (AESSCS) was held on 13 May 2014 in conjunction with the European Dependable Computing Conference (EDCC). We summarize and elaborate on the workshop's discussion of the topic, including both the presented positions and the dialogue that ensued.

  15. 49 CFR Appendix B to Part 512 - General Class Determinations

    Science.gov (United States)

    2010-10-01

    ... significant reverse engineering; (2) Future specific model plans (to be protected only until the date on which the specific model to which the plan pertains is first offered for sale); and (3) Future vehicle... SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION CONFIDENTIAL BUSINESS INFORMATION Pt. 512, App. B...

  16. Nevada State plan; final approval determination. Occupational Safety and Health Administration (OSHA), U.S. Department of Labor. Final State plan approval--Nevada.

    Science.gov (United States)

    2000-04-18

    This document amends OSHA's regulations to reflect the Assistant Secretary's decision granting final approval to the Nevada State plan. As a result of this affirmative determination under section 18(e) of the Occupational Safety and Health Act of 1970, Federal OSHA's standards and enforcement authority no longer apply to occupational safety and health issues covered by the Nevada plan, and authority for Federal concurrent jurisdiction is relinquished. Federal enforcement jurisdiction is retained over any private sector maritime employment, private sector employers on Indian land, and any contractors or subcontractors on any Federal establishment where the land is exclusive Federal jurisdiction. Federal jurisdiction remains in effect with respect to Federal government employers and employees. Federal OSHA will also retain authority for coverage of the United States Postal Service (USPS), including USPS employees, contract employees, and contractor-operated facilities engaged in USPS mail operations.

  17. Nordic nuclear safety research. Summary report for 1995. Plans for 1996 and 1997

    International Nuclear Information System (INIS)

    1996-04-01

    NKS (Nordic Nuclear Safety Research) is a cooperative body in nuclear safety and radiation protection. Its purpose is to carry out cost-effective Nordic projects, thus producing research results, exercises, information, recommendations, manuals and other types of background material, to be used by decision makers and other concerned staff members at authorities and within the nuclear industry. This is the annual report for 1995. The report also contains plans for the rest of the program period. The program comprises four major fields of research: reactor safety; radioactive waste; radioecology; and emergency preparedness. Finland and Sweden presently operate a total of 16 power producing reactors. Denmark, Norway and Sweden operate research reactors. There is a plant for nuclear fuel manufacture in Sweden. All five Nordic countries have intermediate waste storage facilities. In addition, there are a number of power, research and naval reactors and other nuclear installations in Nordic surroundings, both in Eastern and Western Europe. Hence, nuclear safety, radiation protection, waste management, environmental impact and emergency preparedness issues are of common interest to all Nordic countries. Environmental impact of radioactive releases is studied in two radioecology projects. The project on marine radioecology, including sediment research (EKO-1), includes sampling, analysis and modeling. These are also key issues in the project on long ecological half-lives in semi-natural systems (EKO-2). The transfer of the seven presently ongoing projects are summarized in this report by the project leaders, both in terms of results in 1995 and plans for 1996/97. (EG)

  18. Risk management for drinking water safety in low and middle income countries - cultural influences on water safety plan (WSP) implementation in urban water utilities.

    Science.gov (United States)

    Omar, Yahya Y; Parker, Alison; Smith, Jennifer A; Pollard, Simon J T

    2017-01-15

    We investigated cultural influences on the implementation of water safety plans (WSPs) using case studies from WSP pilots in India, Uganda and Jamaica. A comprehensive thematic analysis of semi-structured interviews (n=150 utility customers, n=32 WSP 'implementers' and n=9 WSP 'promoters'), field observations and related documents revealed 12 cultural themes, offered as 'enabling', 'limiting', or 'neutral', that influence WSP implementation in urban water utilities to varying extents. Aspects such as a 'deliver first, safety later' mind set; supply system knowledge management and storage practices; and non-compliance are deemed influential. Emergent themes of cultural influence (ET1 to ET12) are discussed by reference to the risk management, development studies and institutional culture literatures; by reference to their positive, negative or neutral influence on WSP implementation. The results have implications for the utility endorsement of WSPs, for the impact of organisational cultures on WSP implementation; for the scale-up of pilot studies; and they support repeated calls from practitioner communities for cultural attentiveness during WSP design. Findings on organisational cultures mirror those from utilities in higher income nations implementing WSPs - leadership, advocacy among promoters and customers (not just implementers) and purposeful knowledge management are critical to WSP success. Copyright © 2016 The Authors. Published by Elsevier B.V. All rights reserved.

  19. Coal Mine Health and Safety Regulation 2006 under the Coal Mine Health and Safety Act 2002

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-12-22

    The aim of the Act is to secure the health, safety and welfare of people in connection with coal operations (which include all places of work where coal is mined and certain other places). The Regulation contains provisions about the following matters: (a) places of work to which the Act does not apply, (b) duties relating to health, welfare and safety at coal operations, including the following: (i) the nomination of the operator of a coal operation and the provision of health and safety information for incoming operators, (ii) the contents of health and safety management systems for coal operations, (iii) major hazards and the contents of major hazard management plans for coal operations, (iv) duties relating to contractors, (v) the contents of management structures and emergency management systems for coal operations, escape and rescue plans and fire fighting plans and high risk activities, (c) notifications, including (i) notification of incidents, (ii) inquiries, (iii) notification of other matters to the Chief Inspector), (d) aspects of safety at coal operations, including the following: (i) controlled materials, plants and practices, (ii) coal dust explosion prevention and suppression, (iii) ventilation at coal operations, (iv) escape from coal operations, (v) the operation of transport at coal operations, (vi) surveys and certified plans, (vii) employment at coal operations, (e) the licensing of certain activities, (f) competence standards, (g) the Coal Competence Board, (h) check inspectors, (i) exemptions from provisions of this Regulation, (j) the following miscellaneous matters concerning coal mine health and safety: (i) the keeping of records and reporting, (ii) penalties, the review of decisions by the Administrative Decisions Tribunal, fees and charges, consultation, information and other miscellaneous matters, (k) savings and transitional provisions.

  20. Integrated vehicle-based safety systems (IVBSS) : light vehicle platform field operational test data analysis plan.

    Science.gov (United States)

    2009-12-22

    This document presents the University of Michigan Transportation Research Institutes plan to : perform analysis of data collected from the light vehicle platform field operational test of the : Integrated Vehicle-Based Safety Systems (IVBSS) progr...

  1. Integrated vehicle-based safety systems (IVBSS) : heavy truck platform field operational test data analysis plan.

    Science.gov (United States)

    2009-11-23

    This document presents the University of Michigan Transportation Research Institutes plan to perform : analysis of data collected from the heavy truck platform field operational test of the Integrated Vehicle- : Based Safety Systems (IVBSS) progra...

  2. Canadian Nuclear Safety Commission 2003-2004 estimates. Part III - report on plans and priorities

    International Nuclear Information System (INIS)

    2003-01-01

    The Commission replace the Atomic Energy Control Board in 2000 as Canada's independent agency which regulates the use of nuclear energy and materials to protect health, safety, security, and the environment. This report is an individual expenditure plan that provides details on a business line basis and contains information on objectives, initiatives, and planned results, including links to related resource requirements over a three-year period. It also provides details on human resource requirements, major capital projects, grants and contributions, and net program costs. Introductory sections with a minister's message are followed by sections giving a departmental or organization overview; plans, results, activities, resources, and initiatives, as applicable; and financial information

  3. Planned activities to improve safety

    International Nuclear Information System (INIS)

    1998-01-01

    This document presents the fulfilling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 6 of the document contains some details about the planed activities to safety improvements

  4. European Counterpublics? DiEM25, Plan B and the Agonistic European Public Sphere

    DEFF Research Database (Denmark)

    Agustin, Oscar Garcia

    2017-01-01

    Plan B in Europe’ (Plan B) and the Democracy in Europe Movement 2025 (DiEM25). These initiatives emerged to promote a new European project as a rejection of EU austerity policies and lack of democracy. The shaping of alternatives is understood within the framework of the public sphere...... and agonistic public sphere from perspectives and experiences which, while sharing the need of internationalization, develop different strategies....

  5. Using the Theory of Planned Behaviour to examine health professional students' behavioural intentions in relation to medication safety and collaborative practice.

    Science.gov (United States)

    Lapkin, Samuel; Levett-Jones, Tracy; Gilligan, Conor

    2015-08-01

    Safe medication practices depend upon, not only on individual responsibilities, but also effective communication and collaboration between members of the medication team. However, measurement of these skills is fraught with conceptual and practical difficulties. The aims of this study were to explore the utility of a Theory of Planned Behaviour-based questionnaire to predict health professional students' behavioural intentions in relation to medication safety and collaborative practice; and to determine the contribution of attitudes, subjective norms, and perceived control to behavioural intentions. A descriptive cross-sectional survey based upon the Theory of Planned Behaviour was designed and tested. A convenience sample of 65 undergraduate pharmacy, nursing and medicine students from one semi-metropolitan Australian university were recruited for the study. Participants' behavioural intentions, attitudes, subjective norms, and perceived control to behavioural intentions in relation to medication safety were measured using an online version of the Theory of Planned Behaviour Medication Safety Questionnaire. The Questionnaire had good internal consistency with a Cronbach's alpha of 0.844. The three predictor variables of attitudes, subjective norms, and perceived control accounted for between 30 and 46% of the variance in behavioural intention; this is a strong prediction in comparison to previous studies using the Theory of Planned Behaviour. Data analysis also indicated that attitude was the most significant predictor of participants' intention to collaborate with other team members to improve medication safety. The results from this study provide preliminary support for the Theory of Planned Behaviour-Medication Safety Questionnaire as a valid instrument for examining health professional students' behavioural intentions in relation to medication safety and collaborative practice. Copyright © 2015 Elsevier Ltd. All rights reserved.

  6. Safety Improvement in Radiotherapy Treatment Plan. Planning vs Redundant Check vs in vivo Dosimetry

    International Nuclear Information System (INIS)

    Torres Diaz, J.; Ascencion Ybarra, Y.; La Fuentes Rosales, L. de; Lara Mas, E.; Larrinaga Cortinas, E.

    2013-01-01

    In Cuba it is mandatory to have an independent monitor units check before any radiotherapy treatment is started. The main objective of this paper is to enhance the safety of the radiotherapy planning by developing and testing a practical tool to double check the monitor units calculation for external beam high energy photon therapy. A software for monitor units (MUs) verification was designed and coded. It considers the common in clinical practice isocentric set-ups. The in vivo dosimetry measurements were done with a silicon diode system for 6 MV photon beams to support the validation of the software. The results show a discrepancy within 5% between the 3 methods which is in accordance with international recommendations. (Author)

  7. 77 FR 50727 - Configuration Management Plans for Digital Computer Software Used in Safety Systems of Nuclear...

    Science.gov (United States)

    2012-08-22

    ... enhanced consensus practices for planning software configuration management (SCM) as described in the... testing of structures, systems, and components important to safety throughout the life of the unit. This...

  8. 2 CFR 180.360 - What happens if I fail to disclose information required under § 180.355?

    Science.gov (United States)

    2010-01-01

    ... Doing Business With Other Persons Disclosing Information-Lower Tier Participants § 180.360 What happens... 2 Grants and Agreements 1 2010-01-01 2010-01-01 false What happens if I fail to disclose information required under § 180.355? 180.360 Section 180.360 Grants and Agreements OFFICE OF MANAGEMENT AND...

  9. Site specific health and safety plan for drilling in support of in situ redox manipulation

    International Nuclear Information System (INIS)

    Tuttle, B.G.

    1997-02-01

    This document contains the Site Specific Health and Safety Plan for Drilling in support of the In Situ REDOX Manipulation in the 100-HR-3 Operable Unit. Approximately eight wells will be drilled in the 100-D/DR Area using rotary, sonic, or cable tool drilling methods. Split-spoon sampling will be done in conjunction with the drilling. The drilling may be spread out over several months. Included in this document are checklists for health and safety procedures

  10. 49 CFR 244.15 - Subjects to be addressed in a Safety Integration Plan not involving an amalgamation of operations.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 4 2010-10-01 2010-10-01 false Subjects to be addressed in a Safety Integration... Regulations Relating to Transportation (Continued) FEDERAL RAILROAD ADMINISTRATION, DEPARTMENT OF TRANSPORTATION REGULATIONS ON SAFETY INTEGRATION PLANS GOVERNING RAILROAD CONSOLIDATIONS, MERGERS, AND...

  11. Safety Analysis Report: X17B2 beamline Synchrotron Medical Research Facility

    International Nuclear Information System (INIS)

    Gmuer, N.F.; Thomlinson, W.

    1990-02-01

    This report contains a safety analysis for the X17B2 beamline synchrotron medical research facility. Health hazards, risk assessment and building systems are discussed. Reference is made to transvenous coronary angiography

  12. 200-ZP-1 phase II and III IRM groundwater pump and treat site safety plan

    International Nuclear Information System (INIS)

    St. John, C.H.

    1996-07-01

    This safety plan covers operations, maintenance, and support activities related to the 200-ZP-1 Phase II and III Ground Water Pump- and-Treat Facility. The purpose of the facility is to extract carbon tetrachloride contaminated groundwater underlying the ZP-1 Operable Unit; separate the contaminant from the groundwater; and reintroduce the treated water to the aquifer. An air stripping methodology is employed to convert volatile organics to a vapor phase for absorption onto granular activated carbon. The automated process incorporates a variety of process and safety features that shut down the process system in the event that process or safety parameters are exceeded or compromised

  13. Awareness and use of and barriers to family planning services ...

    African Journals Online (AJOL)

    Methods. In a quantitative descriptive survey, 360 female undergraduate students ... Access to services was good. ... Levels of awareness and utilisation of family planning services are high among female students at the University of Lesotho.

  14. A comparative study of standard intensity-modulated radiotherapy and RapidArc planning techniques for ipsilateral and bilateral head and neck irradiation

    Energy Technology Data Exchange (ETDEWEB)

    Pursley, Jennifer, E-mail: jpursley@mgh.harvard.edu [Department of Radiation Oncology, Dana-Farber Cancer Institute/Brigham and Women' s Hospital, Boston, MA (United States); Department of Radiation Oncology, Massachusetts General Hospital, Boston, MA (United States); Damato, Antonio L.; Czerminska, Maria A.; Margalit, Danielle N. [Department of Radiation Oncology, Dana-Farber Cancer Institute/Brigham and Women' s Hospital, Boston, MA (United States); Sher, David J. [Department of Radiation Oncology, Dana-Farber Cancer Institute/Brigham and Women' s Hospital, Boston, MA (United States); Department of Radiation Oncology, UT Southwestern Medical Center, Dallas, TX (United States); Tishler, Roy B. [Department of Radiation Oncology, Dana-Farber Cancer Institute/Brigham and Women' s Hospital, Boston, MA (United States)

    2017-04-01

    The purpose of this study was to investigate class solutions using RapidArc volumetric-modulated arc therapy (VMAT) planning for ipsilateral and bilateral head and neck (H&N) irradiation, and to compare dosimetric results with intensity-modulated radiotherapy (IMRT) plans. A total of 14 patients who received ipsilateral and 10 patients who received bilateral head and neck irradiation were retrospectively replanned with several volumetric-modulated arc therapy techniques. For ipsilateral neck irradiation, the volumetric-modulated arc therapy techniques included two 360° arcs, two 360° arcs with avoidance sectors around the contralateral parotid, two 260° or 270° arcs, and two 210° arcs. For bilateral neck irradiation, the volumetric-modulated arc therapy techniques included two 360° arcs, two 360° arcs with avoidance sectors around the shoulders, and 3 arcs. All patients had a sliding-window-delivery intensity-modulated radiotherapy plan that was used as the benchmark for dosimetric comparison. For ipsilateral neck irradiation, a volumetric-modulated arc therapy technique using two 360° arcs with avoidance sectors around the contralateral parotid was dosimetrically comparable to intensity-modulated radiotherapy, with improved conformity (conformity index = 1.22 vs 1.36, p < 0.04) and lower contralateral parotid mean dose (5.6 vs 6.8 Gy, p < 0.03). For bilateral neck irradiation, 3-arc volumetric-modulated arc therapy techniques were dosimetrically comparable to intensity-modulated radiotherapy while also avoiding irradiation through the shoulders. All volumetric-modulated arc therapy techniques required fewer monitor units than sliding-window intensity-modulated radiotherapy to deliver treatment, with an average reduction of 35% for ipsilateral plans and 67% for bilateral plans. Thus, for ipsilateral head and neck irradiation a volumetric-modulated arc therapy technique using two 360° arcs with avoidance sectors around the contralateral parotid is

  15. Understanding safety and production risks in rail engineering planning and protection.

    Science.gov (United States)

    Wilson, John R; Ryan, Brendan; Schock, Alex; Ferreira, Pedro; Smith, Stuart; Pitsopoulos, Julia

    2009-07-01

    Much of the published human factors work on risk is to do with safety and within this is concerned with prediction and analysis of human error and with human reliability assessment. Less has been published on human factors contributions to understanding and managing project, business, engineering and other forms of risk and still less jointly assessing risk to do with broad issues of 'safety' and broad issues of 'production' or 'performance'. This paper contains a general commentary on human factors and assessment of risk of various kinds, in the context of the aims of ergonomics and concerns about being too risk averse. The paper then describes a specific project, in rail engineering, where the notion of a human factors case has been employed to analyse engineering functions and related human factors issues. A human factors issues register for potential system disturbances has been developed, prior to a human factors risk assessment, which jointly covers safety and production (engineering delivery) concerns. The paper concludes with a commentary on the potential relevance of a resilience engineering perspective to understanding rail engineering systems risk. Design, planning and management of complex systems will increasingly have to address the issue of making trade-offs between safety and production, and ergonomics should be central to this. The paper addresses the relevant issues and does so in an under-published domain - rail systems engineering work.

  16. Safety risk assessment using analytic hierarchy process (AHP) during planning and budgeting of construction projects.

    Science.gov (United States)

    Aminbakhsh, Saman; Gunduz, Murat; Sonmez, Rifat

    2013-09-01

    The inherent and unique risks on construction projects quite often present key challenges to contractors. Health and safety risks are among the most significant risks in construction projects since the construction industry is characterized by a relatively high injury and death rate compared to other industries. In construction project management, safety risk assessment is an important step toward identifying potential hazards and evaluating the risks associated with the hazards. Adequate prioritization of safety risks during risk assessment is crucial for planning, budgeting, and management of safety related risks. In this paper, a safety risk assessment framework is presented based on the theory of cost of safety (COS) model and the analytic hierarchy process (AHP). The main contribution of the proposed framework is that it presents a robust method for prioritization of safety risks in construction projects to create a rational budget and to set realistic goals without compromising safety. The framework provides a decision tool for the decision makers to determine the adequate accident/injury prevention investments while considering the funding limits. The proposed safety risk framework is illustrated using a real-life construction project and the advantages and limitations of the framework are discussed. Copyright © 2013 National Safety Council and Elsevier Ltd. All rights reserved.

  17. The SOLAR-C Mission: Plan B Payload Concept

    Science.gov (United States)

    Shimizu, T.; Sakao, T.; Katsukawa, Y.; Group, J. S. W.

    2012-08-01

    The telescope concepts for the SOLAR-C Plan B mission as of the time of the Hinode-3 meeting were briefly presented for having comments from the international solar physics community. The telescope candidates are 1) near IR-visible-UV telescope with 1.5m aperture and enhanced spectro-polarimetric capability, 2) UV/EUV high throughput spectrometer, and 3) next generation X-ray telescope.

  18. 360-degree videos: a new visualization technique for astrophysical simulations, applied to the Galactic Center

    Science.gov (United States)

    Russell, Christopher

    2018-01-01

    360-degree videos are a new type of movie that renders over all 4π steradian. Video sharing sites such as YouTube now allow this unique content to be shared via virtual reality (VR) goggles, hand-held smartphones/tablets, and computers. Creating 360-degree videos from astrophysical simulations not only provide a new way to view these simulations due to their immersive nature, but also yield engaging content for outreach to the public. We present our 360-degree video of an astrophysical simulation of the Galactic center: a hydrodynamics calculation of the colliding and accreting winds of the 30 Wolf-Rayet stars orbiting within the central parsec. Viewing the movie, which renders column density, from the location of the supermassive black hole gives a unique and immersive perspective of the shocked wind material inspiraling and tidally stretching as it plummets toward the black hole. We also describe how to create such movies, discuss what type of content does and does not look appealing in 360-degree format, and briefly comment on what new science can be extracted from astrophysical simulations using 360-degree videos.

  19. Safety planning for nuclear power stations

    International Nuclear Information System (INIS)

    Tadmor, J.

    1979-01-01

    The article shows that compared to the many industries and other human activities, nuclear power stations are among the safest. A short description of the measures taken to prevent accidents and of the additional safety means entering into action if an accident does occur is presented. It is shown that in nuclear plants the death frequency following malfunctioning is 1 death in 100.000 years whereas deaths following other human activities is 1 in 2 to 100 years and following natural calamities like earthquakes and floods is 1 in 10 years. As an example it is shown that for a population of 15.000.000 living in a radius of 40 km around 100 power stations the average number of deaths will be of 2 per year as compared to 4200 from road accidents with the corresponding number of injuries of 20 and 375.000 respectively. (B.G.)

  20. Plutonium Vulnerability Management Plan

    International Nuclear Information System (INIS)

    1995-03-01

    This Plutonium Vulnerability Management Plan describes the Department of Energy's response to the vulnerabilities identified in the Plutonium Working Group Report which are a result of the cessation of nuclear weapons production. The responses contained in this document are only part of an overall, coordinated approach designed to enable the Department to accelerate conversion of all nuclear materials, including plutonium, to forms suitable for safe, interim storage. The overall actions being taken are discussed in detail in the Department's Implementation Plan in response to the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-1. This is included as Attachment B

  1. Health and safety work plan for sampling colloids in Waste Area Grouping 5 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Marsh, J.D.; McCarthy, J.F.

    1994-07-01

    This Work Plan/Site Safety and Health Plan (SSHP) and the attached work plan are for the performance of the colloid sampling project at WAG 5. The work will be conducted by the Oak Ridge National Laboratory (ORNL) Environmental Sciences Division (ESD) and associated ORNL environmental, safety, and health support groups. This activity will fall under the scope of 29 CFR 1910.120, Hazardous Waste Operations and Emergency Response (HAZWOPER). The purpose of this document is to establish health and safety guidelines to be followed by all personnel involved in conducting work for this project. Work will be conducted in accordance with requirements as stipulated in the ORNL HAZWOPER Program manual, and applicable ORNL, Martin Marietta Energy Systems, Inc., and US Department of Energy (DOE) policies and procedures

  2. 12 CFR 563b.105 - What information must I include in my business plan?

    Science.gov (United States)

    2010-01-01

    ... information must I include in my business plan? (a) Prior to filing an application for conversion, you must adopt a business plan reflecting your intended plans for deployment of the proposed conversion proceeds. Your business plan is required, under § 563b.150, to be included in your conversion application. At a...

  3. THE ROLE OF NAVIGATIONAL AIDS IN FLIGHT SAFETY MANAGEMENT WITHIN ICAO GLOBAL AIR NAVIGATION PLAN

    Directory of Open Access Journals (Sweden)

    Vadim V. Vurobyov

    2017-01-01

    Full Text Available The development of the global civil aviation is provided on the basis of the ICAO Communication and Surveillance/Air Traffic Management Concept, which has determined the basic strategy for further commercial flight management effectiveness improvement. On the basis of this concept a Global Air Navigation Plan has been developed by ICAO recently. The core strategies of CNS/ATM concept were specified and combined into so-called blocks. Thus the term Global Aviation System block upgrade has been introduced. At the same time, GANP states that the introduction of new procedures and flight management systems will inevitably affect flight safety. Accordingly, there is a task of flight safety management level maintaining, or even increasing within the Global Air Navigation Plan implementation. Various air navigational aids play a significant role in the process as they are directly associated with the new systems and structures introduction.This breeds the new global challenge of flight safety management level change assessment during the introduction of new procedures and systems connected with the use of both navigational aids and instruments. Some aspects of this problem solution are covered in the article.

  4. HAL/S-360 compiler system specification

    Science.gov (United States)

    Johnson, A. E.; Newbold, P. N.; Schulenberg, C. W.; Avakian, A. E.; Varga, S.; Helmers, P. H.; Helmers, C. T., Jr.; Hotz, R. L.

    1974-01-01

    A three phase language compiler is described which produces IBM 360/370 compatible object modules and a set of simulation tables to aid in run time verification. A link edit step augments the standard OS linkage editor. A comprehensive run time system and library provide the HAL/S operating environment, error handling, a pseudo real time executive, and an extensive set of mathematical, conversion, I/O, and diagnostic routines. The specifications of the information flow and content for this system are also considered.

  5. Research and Application of Autodesk Fusion360 in Industrial Design

    Science.gov (United States)

    Song, P. P.; Qi, Y. M.; Cai, D. C.

    2018-05-01

    In 2016, Fusion 360, a productintroduced byAutodesk and integrating industrial design, structural design, mechanical simulation, and CAM, turns out a design platform supportingcollaboration and sharing both cross-platform and via the cloud. In previous products, design and manufacturing use to be isolated. In the course of design, research and development, the communication between designers and engineers used to go on through different software products, tool commands, and even industry terms. Moreover, difficulty also lies with the communication between design thoughts and machining strategies. Naturally, a difficult product design and R & D process would trigger a noticeable gap between the design model and the actual product. A complete product development process tends to cover several major areas, such as industrial design, mechanical design, rendering and animation, computer aided emulation (CAE), and computer aided manufacturing (CAM). Fusion 360, a perfect design solving the technical problems of cross-platform data exchange, realizes the effective control of cross-regional collaboration and presents an overview of collaboration and breaks the barriers between art and manufacturing, andblocks between design and processing. The “Eco-development of Fusion360 Industrial Chain” is both a significant means to and an inevitable trend forthe manufacturers and industrial designers to carry out innovation in China.

  6. Environmental, Safety, and Health Plan for the remedial investigation/feasibility study at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1993-05-01

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

  7. Safety Evaluation report on Tennessee Valley Authority: Sequoyah nuclear performance plan

    International Nuclear Information System (INIS)

    1988-05-01

    This Safety Evaluation Report (SER) on the information submitted by the Tennessee Valley Authority (TVA) in its Sequoyah Nuclear Performance Plan, through Revision 2, and supporting documents has been prepared by the US Nuclear Regulatory Commission staff. The plan addresses the plant-specific concerns requiring resolution before startup of either of the Sequoyah units. In particular, the SER addresses required actions for Unit 2 restart. In many cases, the programmatic aspects for Unit 1 are identical to those for Unit 2; the staff will conduct inspections of implementation of those programs. Where the Unit 1 program is different, the staff evaluation will be provided in a supplement to this SER. On the basis of its review, the staff concludes that Sequoyah-specific issues have been resolved to the extent that would support restart of Sequoyah Unit 2

  8. Automated and connected vehicle (AV/CV) test bed to improve transit, bicycle, and pedestrian safety : concept of operations plan.

    Science.gov (United States)

    2017-02-01

    This document presents the Concept of Operations (ConOps) Plan for the Automated and Connected Vehicle (AV/CV) Test Bed to Improve Transit, Bicycle, and Pedestrian Safety. As illustrated in Figure 1, the plan presents the overarching vision and goals...

  9. Interim-status groundwater monitoring plan for the 216-B-63 trench. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Sweeney, M.D.

    1995-06-13

    This document outlines the groundwater monitoring plan for interim-status detection-level monitoring of the 216-B-63 Trench. This is a revision of the initial groundwater monitoring plan prepared for Westinghouse Hanford Company (WHC) by Bjornstad and Dudziak (1989). The 216-B-63 Trench, located at the Hanford Site in south-central Washington State, is an open, unlined, earthern trench approximately 1.2 m (4 ft) wide at the bottom, 427 m (1400 ft) long, and 3 m (10 ft) deep that received wastewater containing hazardous waste and radioactive materials from B Plant, located in the 200 East Area. Liquid effluent discharge to the 216-B-63 Trench began in March 1970 and ceased in February 1992. The trench is now managed by Waste Tank Operations.

  10. Interim-status groundwater monitoring plan for the 216-B-63 trench. Revision 1

    International Nuclear Information System (INIS)

    Sweeney, M.D.

    1995-01-01

    This document outlines the groundwater monitoring plan for interim-status detection-level monitoring of the 216-B-63 Trench. This is a revision of the initial groundwater monitoring plan prepared for Westinghouse Hanford Company (WHC) by Bjornstad and Dudziak (1989). The 216-B-63 Trench, located at the Hanford Site in south-central Washington State, is an open, unlined, earthern trench approximately 1.2 m (4 ft) wide at the bottom, 427 m (1400 ft) long, and 3 m (10 ft) deep that received wastewater containing hazardous waste and radioactive materials from B Plant, located in the 200 East Area. Liquid effluent discharge to the 216-B-63 Trench began in March 1970 and ceased in February 1992. The trench is now managed by Waste Tank Operations

  11. 2011 Annual Criticality Safety Program Performance Summary

    Energy Technology Data Exchange (ETDEWEB)

    Andrea Hoffman

    2011-12-01

    The 2011 review of the INL Criticality Safety Program has determined that the program is robust and effective. The review was prepared for, and fulfills Contract Data Requirements List (CDRL) item H.20, 'Annual Criticality Safety Program performance summary that includes the status of assessments, issues, corrective actions, infractions, requirements management, training, and programmatic support.' This performance summary addresses the status of these important elements of the INL Criticality Safety Program. Assessments - Assessments in 2011 were planned and scheduled. The scheduled assessments included a Criticality Safety Program Effectiveness Review, Criticality Control Area Inspections, a Protection of Controlled Unclassified Information Inspection, an Assessment of Criticality Safety SQA, and this management assessment of the Criticality Safety Program. All of the assessments were completed with the exception of the 'Effectiveness Review' for SSPSF, which was delayed due to emerging work. Although minor issues were identified in the assessments, no issues or combination of issues indicated that the INL Criticality Safety Program was ineffective. The identification of issues demonstrates the importance of an assessment program to the overall health and effectiveness of the INL Criticality Safety Program. Issues and Corrective Actions - There are relatively few criticality safety related issues in the Laboratory ICAMS system. Most were identified by Criticality Safety Program assessments. No issues indicate ineffectiveness in the INL Criticality Safety Program. All of the issues are being worked and there are no imminent criticality concerns. Infractions - There was one criticality safety related violation in 2011. On January 18, 2011, it was discovered that a fuel plate bundle in the Nuclear Materials Inspection and Storage (NMIS) facility exceeded the fissionable mass limit, resulting in a technical safety requirement (TSR) violation. The

  12. Using historical crash data as part of traffic work zone safety planning and project management strategies.

    Science.gov (United States)

    2014-07-01

    This funding enabled the project entitled, USING HISTORICAL CRASH DATA AS PART OF TRAFFIC WORK ZONE SAFETY : PLANNING AND PROJECT MANAGEMENT STRATEGIES to address the following: : Evaluate current organizational strategies with respect to w...

  13. Tank 241-B-203 push mode core sampling and analysis plan. Revision 1

    International Nuclear Information System (INIS)

    Jo, J.

    1995-01-01

    This Sampling and Analysis Plan (SAP) identifies characterization objectives pertaining to sample collection, laboratory analytical evaluation, and reporting requirements for two push-mode core samples from tank 241-B-203 (B-203)

  14. Tank 241-B-204 push mode core sampling and analysis plan. Revision 1

    International Nuclear Information System (INIS)

    Sasaki, L.M.

    1995-01-01

    This Sampling and Analysis Plan (SAP) identifies characterization objectives pertaining to sample collection, laboratory analytical evaluation, and reporting requirements for two push-mode core samples from tank 241-B-204 (B-204)

  15. 75 FR 68383 - Hearing on Reasonable Contracts or Arrangements for Welfare Benefit Plans Under Section 408(b)(2...

    Science.gov (United States)

    2010-11-05

    ... Arrangements for Welfare Benefit Plans Under Section 408(b)(2)--Welfare Plan Fee Disclosure AGENCY: Employee... health, disability, severance and other employee welfare benefit plans under section 408(b)(2) of the... affect employee welfare benefit plans. At least one commenter addressed specific concerns of pharmacy...

  16. Planning maximum extraction of a safety pillar in the Most surface mine

    Energy Technology Data Exchange (ETDEWEB)

    Helis, P; Hess, L; Kubiznak, K [SHR - Banske Projekty, Teplice (Czechoslovakia)

    1990-11-01

    Discusses planned coal surface mining in the Most mine in the area of the Hnevin safety pillar with coal reserves amounting to about 7.5 Mt. The following aspects are evaluated: coal reserves and their distribution in the pillar, coal seam thickness and dip angles, water conditions, water influx rates, mechanical properties of the overburden and strata situated in the seam floor, slope stability and hazards of landslides, effects of water influx on landslide hazards, types of bucket wheel excavators used for overburden removal and mining, types of belt conveyors used for mine haulage, stackers, position of mining equipment in the mine. A scheme developed by Banske Projekty Teplice for partial extraction of the safety pillar would result in extraction of 4.5 Mt coal. About 1.7 Mt coal would be left in a safety coal layer about 10.0 m thick situated in the floor in zones with landslide hazards. KU 300 bucket wheel excavators, belt conveyors 1,200 mm wide and ZP 2,500 stackers would be used. 4 refs.

  17. A novel 360-degree shape measurement using a simple setup with two mirrors and a laser MEMS scanner

    Science.gov (United States)

    Jin, Rui; Zhou, Xiang; Yang, Tao; Li, Dong; Wang, Chao

    2017-09-01

    There is no denying that 360-degree shape measurement technology plays an important role in the field of threedimensional optical metrology. Traditional optical 360-degree shape measurement methods are mainly two kinds: the first kind, by placing multiple scanners to achieve 360-degree measurements; the second kind, through the high-precision rotating device to get 360-degree shape model. The former increases the number of scanners and costly, while the latter using rotating devices lead to time consuming. This paper presents a low cost and fast optical 360-degree shape measurement method, which possesses the advantages of full static, fast and low cost. The measuring system consists of two mirrors with a certain angle, a laser projection system, a stereoscopic calibration block, and two cameras. And most of all, laser MEMS scanner can achieve precise movement of laser stripes without any movement mechanism, improving the measurement accuracy and efficiency. What's more, a novel stereo calibration technology presented in this paper can achieve point clouds data registration, and then get the 360-degree model of objects. A stereoscopic calibration block with special coded patterns on six sides is used in this novel stereo calibration method. Through this novel stereo calibration technology we can quickly get the 360-degree models of objects.

  18. Application of safety standards and rules in the Shelter Implementation Plan at the destroyed power unit of Chernobyl NPP

    International Nuclear Information System (INIS)

    Berthold, A.; Bogorinski, P.; Bykov, V.; Redko, V.; Erickson, L.; Kadkin, Ye.; Kondratiev, S.; Simonov, I.; Smyshliaieva, S.; Yesipenko, Yu.

    2002-01-01

    This report deals with the application of safety standards and rules to the Shelter Implementation Plan (SIP) measures. Since 1998 this plan is being implemented at the Chornobyl NPP destroyed unit (which is now known as the Shelter). It includes a set of various tasks whose performance will help partially achieve the established safety objectives. The Regulatory Authority should establish for the Shelter safety goals, principles, and criteria in general, while the Operator of the Shelter is free to independently select the optimum method for their implementation. The Operator of the Shelter must demonstrate (in safety analysis report) that established safety goals are achieved and safety principles and criteria are met. Safety goals, principles, and criteria established for radioactive waste management are reasonable to apply in measures provided for by SIP. However, due to the unique nature of the Shelter, some criteria should not be applied directly and in full scope. Norms and rules on radiation protection should be applied in full scope. The specifics of radiation protection during each Shelter-related activity are considered individually. Safety standards and rules related to technical aspects are reasonable only as a basis. Effective resolution of specific technical issues associated with safety assurance is achieved through interaction between the Operator and the Regulatory Authority during design of SIP structures and systems. Hence, effectiveness of the licensing process plays an important role in the success of the SIP.(author)

  19. IMMUNOGENICITY AND SAFETY OF QUINVAXEM® (DIPHTHERIA, TETANUS, WHOLE-CELL PERTUSSIS, HEPATITIS B AND HAEMOPHILUS INFLUENZAE TYPE B VACCINE) GIVEN TO VIETNAMESE INFANTS AT 2 TO 4 MONTHS OF AGE.

    Science.gov (United States)

    Huu, Tran Ngoc; Phuong, Nguyen Thi Minh; Toan, Nguyen Trong; Thang, Ho Vinh

    2015-07-01

    Vietnam plans to replace the routine childhood diphtheria, pertussis and tetanus combination (DPT) vaccine with a pentavalent vaccine. The present study was performed to assess the immunogenicity and safety of the combined diphtheria, tetanus, whole-cell pertussis, hepatitis B (HepB), and Haemophilus influenzae type b (Hib) (DTwP-HepB-Hib) Quinvaxem® vaccine in children. A total of 131 infants received the Quinvaxem® vaccine at 2, 3 and 4 months. Antibody levels were measured at baseline, at one month after the third injection and one year after the first injection. Seroprotection rates were high for each vaccine antigen at one month after the third dose: 93.1% for diphtheria, 98.5% for tetanus, 99.2% for pertussis (seroconversion rate), 93.1% for HepB, and 100% for Hib (anti-PRP ≥ 0.15 µg/ml). The rate of children with protective antibodies persisting at one year after the first dose was 88.4% for diphtheria, 49.6% for pertussis, 82.2% for tetanus, 76.7% for HepB and 97.7% for Hib (anti-PRP ≥ 0.15 µg/ml). The Quinvaxem® vaccine was well tolerated and has a low rate of adverse events. Quinvaxem® given at 2, 3 and 4 months of age was immunogenic and safe for primary immunization among infants in Vietnam.

  20. 11. Strategic planning.

    Science.gov (United States)

    2014-05-01

    There are several types of planning processes and plans, including strategic, operational, tactical, and contingency. For this document, operational planning includes tactical planning. This chapter examines the strategic planning process and includes an introduction into disaster response plans. "A strategic plan is an outline of steps designed with the goals of the entire organisation as a whole in mind, rather than with the goals of specific divisions or departments". Strategic planning includes all measures taken to provide a broad picture of what must be achieved and in which order, including how to organise a system capable of achieving the overall goals. Strategic planning often is done pre-event, based on previous experience and expertise. The strategic planning for disasters converts needs into a strategic plan of action. Strategic plans detail the goals that must be achieved. The process of converting needs into plans has been deconstructed into its components and includes consideration of: (1) disaster response plans; (2) interventions underway or planned; (3) available resources; (4) current status vs. pre-event status; (5) history and experience of the planners; and (6) access to the affected population. These factors are tempered by the local: (a) geography; (b) climate; (c) culture; (d) safety; and (e) practicality. The planning process consumes resources (costs). All plans must be adapted to the actual conditions--things never happen exactly as planned.

  1. 360-degree video and X-ray modeling of the Galactic center's inner parsec

    Science.gov (United States)

    Russell, Christopher Michael Post; Wang, Daniel; Cuadra, Jorge

    2017-08-01

    360-degree videos, which render an image over all 4pi steradian, provide a unique and immersive way to visualize astrophysical simulations. Video sharing sites such as YouTube allow these videos to be shared with the masses; they can be viewed in their 360° nature on computer screens, with smartphones, or, best of all, in virtual-reality (VR) goggles. We present the first such 360° video of an astrophysical simulation: a hydrodynamics calculation of the Wolf-Rayet stars and their ejected winds in the inner parsec of the Galactic center. Viewed from the perspective of the super-massive black hole (SMBH), the most striking aspect of the video, which renders column density, is the inspiraling and stretching of clumps of WR-wind material as they makes their way towards the SMBH. We will brielfy describe how to make 360° videos and how to publish them online in their desired 360° format. Additionally we discuss computing the thermal X-ray emission from a suite of Galactic-center hydrodynamic simulations that have various SMBH feedback mechanisms, which are compared to Chandra X-ray Visionary Program observations of the region. Over a 2-5” ring centered on Sgr A*, the spectral shape is well matched, indicating that the WR winds are the dominant source of the thermal X-ray emission. Furthermore, the X-ray flux depends on the SMBH feedback due to the feedback's ability to clear out material from the central parsec. A moderate outburst is necessary to explain the current thermal X-ray flux, even though the outburst ended ˜100 yr ago.

  2. Safety of a meningococcal group B vaccine used in response to two university outbreaks.

    Science.gov (United States)

    Duffy, Jonathan; Johnsen, Peter; Ferris, Mary; Miller, Mary; Leighton, Kevin; McGilvray, Mark; McNamara, Lucy; Breakwell, Lucy; Yu, Yon; Bhavsar, Tina; Briere, Elizabeth; Patel, Manisha

    2017-03-31

    To assess the safety of meningococcal group B (MenB)-4C vaccine. Undergraduates, dormitory residents, and persons with high-risk medical conditions received the MenB-4C vaccine two-dose series during mass vaccination clinics from 12/2013 through 11/2014. Adverse events (AEs) were identified by 15 minutes of observation postvaccination, spontaneous reports, surveys, and hospital surveillance. Causality was assessed for serious adverse events (SAEs). 16,974 persons received 31,313 MenB-4C doses. The incidence of syncope during the 15-minutes post-dose 1 was 0.88/1000 persons. 2% of participants spontaneously reported an AE (most common were arm pain and fever). 3 SAEs were suspected of being caused by the vaccine, including one case of anaphylaxis. Most AEs reported were nonserious and consistent with previous clinical trial findings. Measures to prevent injury from syncope and to treat anaphylaxis should be available wherever vaccines are administered. Our safety evaluation supports the use of MenB-4C in response to outbreaks.

  3. FitKids360: Design, Conduct, and Outcomes of a Stage 2 Pediatric Obesity Program

    Directory of Open Access Journals (Sweden)

    Jared M. Tucker

    2014-01-01

    Full Text Available This paper describes FitKids360, a stage 2 pediatric weight management program. FitKids360 is a physician-referred, multicomponent, low-cost healthy lifestyle program for overweight and obese youth 5–16 years of age and their families. FitKids360 provides an evidence-based approach to the treatment of pediatric overweight by targeting patients’ physical activity, screen time, and dietary behaviors using a family-centered approach. The intervention begins with a two-hour orientation and assessment period followed by six weekly sessions. Assessments include lifestyle behaviors, anthropometry, and the Family Nutrition and Physical Activity (FNPA survey, which screens for obesogenic risk factors in the home environment. Outcomes are presented from 258 patients who completed one of 33 FitKids360 classes. After completing FitKids360, patients increased moderate to vigorous physical activity by 14 minutes (P=0.019, reduced screen time by 44 minutes (P<0.001, and improved key dietary behaviors. Overall, FNPA scores increased by 9% (P<0.001 and 69% of patients with “high risk” FNPA scores at baseline dropped below the “high risk” range by followup. Patients also lowered BMIs (P=0.011 and age- and sex-adjusted BMI z-scores (P<0.001 after completing the 7-week program. We hope this report will be useful to medical and public health professionals seeking to develop stage 2 pediatric obesity programs.

  4. Our Journey to Summon and 360: The KAUST experience

    KAUST Repository

    Ramli, Rindra M.

    2017-01-01

    to embark on the project to evaluate, assess and recommend for a new and robust discovery layer. On top of that, the presenters would elaborate the project timeline (which also include the implementation phase for Summon and 360 Core), the challenges faced

  5. 360-degrees profilometry using strip-light projection coupled to Fourier phase-demodulation.

    Science.gov (United States)

    Servin, Manuel; Padilla, Moises; Garnica, Guillermo

    2016-01-11

    360 degrees (360°) digitalization of three dimensional (3D) solids using a projected light-strip is a well-established technique in academic and commercial profilometers. These profilometers project a light-strip over the digitizing solid while the solid is rotated a full revolution or 360-degrees. Then, a computer program typically extracts the centroid of this light-strip, and by triangulation one obtains the shape of the solid. Here instead of using intensity-based light-strip centroid estimation, we propose to use Fourier phase-demodulation for 360° solid digitalization. The advantage of Fourier demodulation over strip-centroid estimation is that the accuracy of phase-demodulation linearly-increases with the fringe density, while in strip-light the centroid-estimation errors are independent. Here we proposed first to construct a carrier-frequency fringe-pattern by closely adding the individual light-strip images recorded while the solid is being rotated. Next, this high-density fringe-pattern is phase-demodulated using the standard Fourier technique. To test the feasibility of this Fourier demodulation approach, we have digitized two solids with increasing topographic complexity: a Rubik's cube and a plastic model of a human-skull. According to our results, phase demodulation based on the Fourier technique is less noisy than triangulation based on centroid light-strip estimation. Moreover, Fourier demodulation also provides the amplitude of the analytic signal which is a valuable information for the visualization of surface details.

  6. HACCP and water safety plans in Icelandic water supply: preliminary evaluation of experience.

    Science.gov (United States)

    Gunnarsdóttir, María J; Gissurarson, Loftur R

    2008-09-01

    Icelandic waterworks first began implementing hazard analysis and critical control points (HACCP) as a preventive approach for water safety management in 1997. Since then implementation has been ongoing and currently about 68% of the Icelandic population enjoy drinking water from waterworks with a water safety plan based on HACCP. Preliminary evaluation of the success of HACCP implementation was undertaken in association with some of the waterworks that had implemented HACCP. The evaluation revealed that compliance with drinking water quality standards improved considerably following the implementation of HACCP. In response to their findings, waterworks implemented a large number of corrective actions to improve water safety. The study revealed some limitations for some, but not all, waterworks in relation to inadequate external and internal auditing and a lack of oversight by health authorities. Future studies should entail a more comprehensive study of the experience with the use of HACCP with the purpose of developing tools to promote continuing success.

  7. Long-term safety of rituximab induced peripheral B-cell depletion in autoimmune neurological diseases.

    Directory of Open Access Journals (Sweden)

    Anza B Memon

    Full Text Available B-cells play a pivotal role in several autoimmune diseases, including patients with immune-mediated neurological disorders (PIMND, such as neuromyelitis optica (NMO, multiple sclerosis (MS, and myasthenia gravis (MG. Targeting B-cells has been an effective approach in ameliorating both central and peripheral autoimmune diseases. However, there is a paucity of literature on the safety of continuous B-cell depletion over a long period of time.The aim of this study was to examine the long-term safety, incidence of infections, and malignancies in subjects receiving continuous therapy with a B-cell depleting agent rituximab over at least 3 years or longer.This was a retrospective study involving PIMND who received continuous cycles of rituximab infusions every 6 to 9 months for up to 7 years. The incidence of infection related adverse events (AE, serious adverse events (SAE, and malignancies were observed.There were a total of 32 AE and 4 SAE with rituximab treatment. The 3 SAE were noted after 9 cycles (48 months and 1 SAE was observed after 11 cycles (60 months of rituximab. There were no cases of Progressive multifocal leukoencephalopathy (PML and malignancies observed throughout the treatment period. Rituximab was well tolerated without any serious infusion reactions. Also, rituximab was found to be beneficial in treating PIMND over a 7-year period.This study demonstrates that long-term depletion of peripheral B-cells appears safe and efficacious in treating PIMND. Longer and larger prospective studies with rituximab are needed to carefully ascertain risks associated with chronic B-cell depletion, including malignancies. Recognizing that this is a small, retrospective study, such data nonetheless complement the growing literature documenting the safety and tolerability of B-cell depleting agents in neurological diseases.

  8. Water Safety Plan on cruise ships: a promising tool to prevent waterborne diseases.

    Science.gov (United States)

    Mouchtouri, Varvara A; Bartlett, Christopher L R; Diskin, Arthur; Hadjichristodoulou, Christos

    2012-07-01

    Legionella spp. and other waterborne pathogens have been isolated from various water systems on land based premises as well as on ships and cases of Legionnaires' disease have been associated with both sites. Peculiarities of cruise ships water systems make the risk management a challenging process. The World Health Organization suggests a Water Safety Plan (WSP) as the best approach to mitigate risks and hazards such as Legionella spp. and others. To develop WSP on a cruise ship and discuss challenges, perspectives and key issues to success. Hazards and hazardous events were identified and risk assessment was conducted of the ship water system. Ship company management, policies and procedures were reviewed, site visits were conducted, findings and observations were recorded and discussed with engineers and key crew members were interviewed. A total of 53 hazards and hazardous events were taken into consideration for the risk assessment and additional essential barriers were established when needed. Most of them concerned control measures for biofilm development and Legionella spp. contamination. A total of 29 operational limits were defined. Supplementary verification and supportive programs were established. Application of the WSP to ship water systems, including potable water, recreational water facilities and decorative water features and fountains, is expected to improve water management on ships. The success of a WSP depends on support from senior management, commitment of the Captain and crew members, correct execution of all steps of a risk assessment and practicality and applicability in routine operation. The WSP provides to shipping industry a new approach and a move toward evidence based water safety policy. Copyright © 2012 Elsevier B.V. All rights reserved.

  9. Study on European Nuclear Safety Practices during Planned Outages at Nuclear Power Plants

    International Nuclear Information System (INIS)

    2001-12-01

    The present project was aimed at providing: a description of the current status of nuclear safety practices during planned outages at nuclear power plants followed in Europe; the criteria for the safety analysis of future reactors at the design stage; proposing a set of recommendations on good practices and criteria leading to the improvement of nuclear safety during those conditions. The work was organised in 3 phases: Collecting data on current practices; Analysis of questionnaire answers and drawing up of safety good practices references and recommendations; Collecting relevant ideas related to the future reactors at design stage (European Pressurised Water Reactor, European Passive Plant project, European Utilities Requirements and Utilities Requirement Document project). The key element of the performed work was the detailed questionnaire, based on bibliographical review, expert experience and outage practices available in the working team. Different safety areas and activities were covered: outage context; nuclear safety; outage strategy, organisation and control; operating feedback; use of Probabilistic Safety Assessment. The questionnaire was answered by 12 European nuclear power plants, representing 9 different European countries and three different types of reactors (Pressurised Water Reactor, Boiling Water Reactor and Water Water Energy Reactor). Conclusions were drawn under the following headers: Organisational survey and generalities Organisational effectiveness Quality of maintenance Quality of operation Engineering support, management of modification Specific aspects Each analysed subject includes the following topics: Questions background with a summary and the aim of the questions. Current status, that describes common practices, as derived from the answers to the questionnaire, and some examples of good specific practices. Identified good practices. (author)

  10. The State Surveillance over Nuclear Safety of Nuclear Facilities Act No. 28/1984

    International Nuclear Information System (INIS)

    1995-01-01

    The Act lays down responsibilities of the Czechoslovak Atomic Energy Commission in the field of state surveillance over nuclear safety of nuclear facilities; determines the responsibilities of nuclear safety inspectors in their inspection activities; specifies duties of bodies and corporations responsible for nuclear safety of nuclear facilities; stipulates the obligation to set up emergency plans; and specifies penalties imposed on corporations and individuals for noncompliance with nuclear safety provisions. The Act entered into force on 4 April 1984. (J.B.)

  11. Safety culture in the nuclear field

    International Nuclear Information System (INIS)

    2005-09-01

    The council of IAEA governors ratified twelve elemental principles of physical protection of nuclear matters and installations. These principles will be included in the future updating of the international convention on the physical protection. The F basic principle proposes a definition of the safety culture and recommends that its implementation and its perenniality to be a reality in the concerned organisms.It appears as necessary to precise the concept of safety culture. The twelve principles are as follow: A State liability, B liability during international transports, C legislative and regulatory framework, D competent authority, E operators liability, F safety culture, G threats, H graduated approach, I deep defence, J assurance of the quality, K emergency plan, L confidentiality. The present document is complementary of INSAG-4, 1991 (safety series number 75, INSAG-4 safety culture, a report by the international nuclear safety advisory group, IAEA, 1991) that presents a concept of safety culture. It proposes also, in a particular chapter, the comparisons( common points and specificities) between safety culture and security culture. (N.C.)

  12. Review of domestic and international experience on optimization of tests planning for safety related systems at NPP

    International Nuclear Information System (INIS)

    Skalozubov, V.I.; Komarov, Yu.A.; Kolykanov, V.N.; Kochneva, V.Yu.; Gablaya, T.V.

    2009-01-01

    There are represented the basic requirements of normative and operating documents on test periodicity of safety related systems at NPPs, sets out the theoretical methods of test optimization of the technical systems, and analyses foreign engineering methods for changing test periodicity of the NPP systems. Based on this review analyses further tasks are formulated for improvement of the methodical base of optimization of tests planning for safety related systems

  13. A plan for safety evaluation of tsunamis at the Uljin nuclear power plant site

    International Nuclear Information System (INIS)

    Lee, H. K.; Lee, D. S.

    1999-01-01

    The sites of many nuclear and thermal power plants are located along the coast line to obtain necessary cooling water. Therefore, they are vulnerable to coastal disasters like tsunamis. The safety evaluation on tsunamis of the site of Uljin nuclear power plants was performed with the maximum potential earthquake magnitude and related fault parameters in 1986. But according to the results of recent research, the possibility was suggested that the earthquake which has bigger magnitude than was expected is likely to happen in the seismic gaps near Akita, Japan. Therefore, a plan for safety evaluation of tsunamis at the Uljin nuclear power plants was laid out

  14. Utah ITS/CVO business plan : using technology to maximize highway safety and improve government and industry productivity

    Science.gov (United States)

    1997-12-31

    This plan was produced to maximize highway safety and increase government and industry productivity through the application of Intelligent Transportation System/Commercial Vehicle Operations (ITS/CVO) technologies to support regulatory and enforcemen...

  15. Doctors' perceptions of why 360-degree feedback does (not) work: a qualitative study.

    Science.gov (United States)

    Overeem, Karlijn; Wollersheim, Hub; Driessen, Erik; Lombarts, Kiki; van de Ven, Geertje; Grol, Richard; Arah, Onyebuchi

    2009-09-01

    Delivery of 360-degree feedback is widely used in revalidation programmes. However, little has been done to systematically identify the variables that influence whether or not performance improvement is actually achieved after such assessments. This study aims to explore which factors represent incentives, or disincentives, for consultants to implement suggestions for improvement from 360-degree feedback. In 2007, 109 consultants in the Netherlands were assessed using 360-degree feedback and portfolio learning. We carried out a qualitative study using semi-structured interviews with 23 of these consultants, purposively sampled based on gender, hospital, work experience, specialty and views expressed in a previous questionnaire. A grounded theory approach was used to analyse the transcribed tape-recordings. We identified four groups of factors that can influence consultants' practice improvement after 360-degree feedback: (i) contextual factors related to workload, lack of openness and social support, lack of commitment from hospital management, free-market principles and public distrust; (ii) factors related to feedback; (iii) characteristics of the assessment system, such as facilitators and a portfolio to encourage reflection, concrete improvement goals and annual follow-up interviews, and (iv) individual factors, such as self-efficacy and motivation. It appears that 360-degree feedback can be a positive force for practice improvement provided certain conditions are met, such as that skilled facilitators are available to encourage reflection, concrete goals are set and follow-up interviews are carried out. This study underscores the fact that hospitals and consultant groups should be aware of the existing lack of openness and absence of constructive feedback. Consultants indicated that sharing personal reflections with colleagues could improve the quality of collegial relationships and heighten the chance of real performance improvement.

  16. 31 CFR 360.6 - Authorized forms of registration.

    Science.gov (United States)

    2010-07-01

    ... coowners. The form of registration “A and B” is not authorized. Examples: David R. Johnson 123-45-6789 or Anna B. Johnson. Maria S. Gonzalez 987-65-4321 or Juan C. Gonzalez. (3) Beneficiary form. A bond may be... Pension Fund of Safety Manufacturing Company, U/A with the company, dated March 31, 1996, 12-3456789...

  17. Guidance for implementing an environmental, safety, and health-assurance program. Volume 15. A model plan for line organization environmental, safety, and health-assurance programs

    Energy Technology Data Exchange (ETDEWEB)

    Ellingson, A.C.; Trauth, C.A. Jr.

    1982-01-01

    This is 1 of 15 documents designed to illustrate how an Environmental, Safety and Health (ES and H) Assurance Program may be implemented. The generic definition of ES and H Assurance Programs is given in a companion document entitled An Environmental, Safety and Health Assurance Program Standard. This particular document presents a model operational-level ES and H Assurance Program that may be used as a guide by an operational-level organization in developing its own plan. The model presented here reflects the guidance given in the total series of 15 documents.

  18. 118-B-1 excavation treatability test plan

    International Nuclear Information System (INIS)

    1994-07-01

    The Hanford 118-B-1 Burial Ground Treatability Study has been required by milestone change request number-sign M-15-93-04, dated September 30, 1993. The change request requires that a treatability test be conducted at the 100-B Area to obtain additional engineering information for remedial design of burial grounds receiving waste from 100 Area removal actions. This treatability study has two purposes: (1) to support development of the Proposed Plan (PP) and Record of Decision (ROD), which will identify the approach to be used for burial ground remediation, and (2) to provide specific engineering information for receiving waste generated from the 100 Area removal actions. Data generated from this test also will provide critical performance and cost information necessary for remedy evaluation in the detailed analysis of alternatives during preparation of the focused feasibility study (FFS). This treatability testing supports the following 100 Area alternatives: (1) excavation and disposal, and (2) excavation, sorting, (treatment), and disposal

  19. National ignition facility environment, safety, and health management plan

    International Nuclear Information System (INIS)

    1995-11-01

    The ES ampersand H Management Plan describes all of the environmental, safety, and health evaluations and reviews that must be carried out in support of the implementation of the National Ignition Facility (NIF) Project. It describes the policy, organizational responsibilities and interfaces, activities, and ES ampersand H documents that will be prepared by the Laboratory Project Office for the DOE. The only activity not described is the preparation of the NIF Project Specific Assessment (PSA), which is to be incorporated into the Programmatic Environmental Impact Statement for Stockpile Stewardship and Management (PEIS). This PSA is being prepared by Argonne National Laboratory (ANL) with input from the Laboratory participants. As the independent NEPA document preparers ANL is directly contracted by the DOE, and its deliverables and schedule are agreed to separately with DOE/OAK

  20. Regulating nuclear and radiation safety in the frame of the Chernobyl shelter Implementation Plan

    Energy Technology Data Exchange (ETDEWEB)

    Bykov, V.; Demchyuk, A.; Kilochitska, T.; Redko, V. [State Nuclear Regulatory Committee of Ukraine, SNRCU, Arsenalna St. 9/11, Kyiv (Ukraine); Bogorinski, P. [GRS/IPSN-RISKAUDIT, Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Koeln (Germany); Vasilchenko, V.; Erickson, L.; Kadkin, E.; Kondratyev, S.; Kutina, L.; Smyshliaeva, S. [SSTC NRS, Stusa St. 35-37, 03142, Kyiv (Ukraine)

    2003-07-01

    Since 1998 the Shelter Implementation Plan (SIP) has been carried out on the Chernobyl NPP Unit 4 (the object Shelter - OS). The State Nuclear Regulatory Committee of Ukraine (SNRCU) recognizes the exceptional importance of successful and efficient SIP implementation and acts accordingly in regulation, licensing, and inspection. Technical support of the SNRCU in SIP licensing are provided by the State Scientific and Technical Center for Nuclear and Radiation Safety (SSTC) and the SIP Licensing Consultant (LC) representing RISKAUDIT IPSN/GRS International and SCIENTECH, Inc. Support of the SNRCU is also provided by the International Consultative Committee of Regulatory Bodies (ICCRB). ICCRB members represent regulatory authorities from nine European countries, Canada and the U.S. Summarizing the information above, it can be stated that a sound basis has been created for the licensing process for SIP. The approach for using the regulatory base has been determined. It ensures the establishment of safety objectives and gives ChNPP the freedom of optimal choice of specific technical decisions. The License has been issued for OS-related activities and a number of documents have been developed to conduct an effective and high quality authorization process: the Licensing Process; Recommendations on single SSR, Licensing Plan for SIP. The Order of State Safety Supervision for SIP has been approved. Working groups are functioning, whose purposes are to coordinate actions of participants in authorization activities, including ChNPP, SNRCU, and other RA.

  1. Regulating nuclear and radiation safety in the frame of the Chernobyl shelter Implementation Plan

    International Nuclear Information System (INIS)

    Bykov, V.; Demchyuk, A.; Kilochitska, T.; Redko, V.; Bogorinski, P.; Vasilchenko, V.; Erickson, L.; Kadkin, E.; Kondratyev, S.; Kutina, L.; Smyshliaeva, S.

    2003-01-01

    Since 1998 the Shelter Implementation Plan (SIP) has been carried out on the Chernobyl NPP Unit 4 (the object Shelter - OS). The State Nuclear Regulatory Committee of Ukraine (SNRCU) recognizes the exceptional importance of successful and efficient SIP implementation and acts accordingly in regulation, licensing, and inspection. Technical support of the SNRCU in SIP licensing are provided by the State Scientific and Technical Center for Nuclear and Radiation Safety (SSTC) and the SIP Licensing Consultant (LC) representing RISKAUDIT IPSN/GRS International and SCIENTECH, Inc. Support of the SNRCU is also provided by the International Consultative Committee of Regulatory Bodies (ICCRB). ICCRB members represent regulatory authorities from nine European countries, Canada and the U.S. Summarizing the information above, it can be stated that a sound basis has been created for the licensing process for SIP. The approach for using the regulatory base has been determined. It ensures the establishment of safety objectives and gives ChNPP the freedom of optimal choice of specific technical decisions. The License has been issued for OS-related activities and a number of documents have been developed to conduct an effective and high quality authorization process: the Licensing Process; Recommendations on single SSR, Licensing Plan for SIP. The Order of State Safety Supervision for SIP has been approved. Working groups are functioning, whose purposes are to coordinate actions of participants in authorization activities, including ChNPP, SNRCU, and other RA

  2. K Basins Spent Nuclear Fuel (SNF) Project Safety Analysis Report for Packaging (SARP) approval plan

    International Nuclear Information System (INIS)

    1995-01-01

    This document delineates the plan for preparation, review, and approval of the K Basins Spent Nuclear Fuel (SNF) Packaging Design Criteria (PDC) document and the on-site Safety Analysis Report for Packaging (SARP). The packaging addressed in these documents is used to transport SNF in a Multi- canister Overpack (MCO) configuration

  3. Evaluation of the effectiveness of the 360-credit National ...

    African Journals Online (AJOL)

    We investigated the effectiveness of the 360-credit National Professional Diploma (NPDE) as a programme that is aimed at the upgrading of currently serving unqualified and under-qualified educators, with a view to improving the quality of teaching and learning in schools and Further Education and Training colleges.

  4. Project W-314 specific test and evaluation plan 241-AN-B valve pit

    International Nuclear Information System (INIS)

    Hays, W.H.

    1998-01-01

    The purpose of this Specific Test and Evaluation Plan (STEP) is to provide a detailed written plan for the systematic testing of modifications made to the 241-AN-B Valve Pit by the W-314 Project. The STEP develops the outline for test procedures that verify the system's performance to the established Project design criteria. The STEP is a lower tier document based on the W-314 Test and Evaluation Plan (TEP)

  5. Final safety analysis report for the Ground Test Accelerator (GTA), Phase 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-10-01

    This document is the second volume of a 3 volume safety analysis report on the Ground Test Accelerator (GTA). The GTA program at the Los Alamos National Laboratory (LANL) is the major element of the national Neutral Particle Beam (NPB) program, which is supported by the Strategic Defense Initiative Office (SDIO). A principal goal of the national NPB program is to assess the feasibility of using hydrogen and deuterium neutral particle beams outside the Earth`s atmosphere. The main effort of the NPB program at Los Alamos concentrates on developing the GTA. The GTA is classified as a low-hazard facility, except for the cryogenic-cooling system, which is classified as a moderate-hazard facility. This volume consists of failure modes and effects analysis; accident analysis; operational safety requirements; quality assurance program; ES&H management program; environmental, safety, and health systems critical to safety; summary of waste-management program; environmental monitoring program; facility expansion, decontamination, and decommissioning; summary of emergency response plan; summary plan for employee training; summary plan for operating procedures; glossary; and appendices A and B.

  6. Narrow-band 1, 2, 3, 4, 8, 16 and 24 cycles/360o angular frequency filters

    Directory of Open Access Journals (Sweden)

    Simas M.L.B.

    2002-01-01

    Full Text Available We measured human frequency response functions for seven angular frequency filters whose test frequencies were centered at 1, 2, 3, 4, 8, 16 or 24 cycles/360º using a supra-threshold summation method. The seven functions of 17 experimental conditions each were measured nine times for five observers. For the arbitrarily selected filter phases, the maximum summation effect occurred at test frequency for filters at 1, 2, 3, 4 and 8 cycles/360º. For both 16 and 24 cycles/360º test frequencies, maximum summation occurred at the lower harmonics. These results allow us to conclude that there are narrow-band angular frequency filters operating somehow in the human visual system either through summation or inhibition of specific frequency ranges. Furthermore, as a general result, it appears that addition of higher angular frequencies to lower ones disturbs low angular frequency perception (i.e., 1, 2, 3 and 4 cycles/360º, whereas addition of lower harmonics to higher ones seems to improve detection of high angular frequency harmonics (i.e., 8, 16 and 24 cycles/360º. Finally, we discuss the possible involvement of coupled radial and angular frequency filters in face perception using an example where narrow-band low angular frequency filters could have a major role.

  7. Planning and preparing for emergency response to transport accidents involving radioactive material. Safety guide

    International Nuclear Information System (INIS)

    2005-01-01

    The objective of this Safety Guide is to provide guidance to the public authorities and others (including consignors, carriers and emergency response authorities) who are responsible for developing and establishing emergency arrangements for dealing effectively and safely with transport accidents involving radioactive material. It may assist those concerned with establishing the capability to respond to such transport emergencies. It provides guidance for those Member States whose involvement with radioactive material is just beginning. It also provides guidance for those Member States that have already developed their radioactive material industries and the attendant emergency plans but that may need to review and improve these plans

  8. Maximizing the Value of 360-Degree Feedback: A Process for Successful Individual and Organizational Development.

    Science.gov (United States)

    Tornow, Walter W.; London, Manuel

    Ways in which organizations can enhance their use of "360-degree feedback" are presented. The book begins with a review of the process itself, emphasizing that 360-degree feedback should be a core element of self-development. The book is divided into three parts. Part 1 describes how to maximize the value of the process for individual…

  9. Development of integrated D/B system for the safety-related structures in nuclear power plant

    International Nuclear Information System (INIS)

    Cho, M. S.; Song, Y. C.; Lee, J. S.; Choi, W. S.

    2002-01-01

    The integrated D/B system is developed for digitalizing the history of the safety-related structures of nuclear power plant. It have 5 database which are consist of Generals, Structural and Design, Materials, Construction, Aging and repair information D/B. For efficient operation of the system, we are to set up the outline of the system, find out data field for target structures, and develop utilities. Utilities will be the aging and repair data management program, the close examination management program, the data search engine with various options which help users to find the information quickly, and the data management program restoring, updating and exchanging input data. Development of the integrated D/B system of the safety-related structures will contribute to management of the structures of nuclear power plant with advanced technology

  10. European Counterpublics? DiEM25, Plan B and the Agonistic European Public Sphere

    DEFF Research Database (Denmark)

    Agustin, Oscar Garcia

    2017-01-01

    After the negotiations between the Syriza government and the European Union (EU), the European Left faced the dilemma of which kind of progressive Europe could be developed within the existing EU framework. Two initiatives were launched to foster an alternative Europe after the Greek crisis: ‘A...... Plan B in Europe’ (Plan B) and the Democracy in Europe Movement 2025 (DiEM25). These initiatives emerged to promote a new European project as a rejection of EU austerity policies and lack of democracy. The shaping of alternatives is understood within the framework of the public sphere...

  11. <90 day storage training plan for the 103-B, 1701-BA, AND 1714-C buildings

    International Nuclear Information System (INIS)

    Snider, P.M.

    1996-10-01

    The 103-B, 1701-BA, and 1714C < 90 Day Storage Area stores characteristic wastes generated in the demolition of the 103-B, 1701-BA, and 1714-C Complex. Wastes (lead-based painted components) are packaged and stored in vendor shipment containers. This is the Environmental Restoration Contractor team training plan for the 103-B, 1701-BA, and 1714-C subgrade demolition < 90 Day Storage of Hazardous Waste. This document is intended to meet the requirements of Washington Administrative Code 173-303-330 and the Hanford Dangerous Waste Permit. Training unrelated to compliance with WAC 173-303-330 is not addressed in this training plan. WAC 173-303-330(1)(d)(2, 5, 6) requires that personnel be familiarized, where applicable, with waste feed cut-off systems, response to ground-water contamination incidents, and shutdown of operations. These are not applicable to 103-B, 1701-BA, and 1714-C Subgrade Demolition < 90 Day Storage, and therefore are not covered in this training plan

  12. Planning the Unplanned Experiment: Towards Assessing the Efficacy of Standards for Safety-Critical Software

    Science.gov (United States)

    Graydon, Patrick J.; Holloway, C. M.

    2015-01-01

    Safe use of software in safety-critical applications requires well-founded means of determining whether software is fit for such use. While software in industries such as aviation has a good safety record, little is known about whether standards for software in safety-critical applications 'work' (or even what that means). It is often (implicitly) argued that software is fit for safety-critical use because it conforms to an appropriate standard. Without knowing whether a standard works, such reliance is an experiment; without carefully collecting assessment data, that experiment is unplanned. To help plan the experiment, we organized a workshop to develop practical ideas for assessing software safety standards. In this paper, we relate and elaborate on the workshop discussion, which revealed subtle but important study design considerations and practical barriers to collecting appropriate historical data and recruiting appropriate experimental subjects. We discuss assessing standards as written and as applied, several candidate definitions for what it means for a standard to 'work,' and key assessment strategies and study techniques and the pros and cons of each. Finally, we conclude with thoughts about the kinds of research that will be required and how academia, industry, and regulators might collaborate to overcome the noted barriers.

  13. ENHANCED PROACTIVE PLANNING APPROACH: A CRUCIAL TO AN IMPROVED WORKERS’ SAFETY IN WESTERN NIGERIA SMALL SCALE INDUSTRY

    Directory of Open Access Journals (Sweden)

    H.O. ADEYEMI

    2016-12-01

    Full Text Available This study evaluated managements’ proactive planning approach (PPA to enhance safety among workers in South-western Nigeria small scale industry (SSI. The main objective was to rate the managements’ efforts at eliminating risk among their employees. By worker participatory and psychological survey approach, three tools were used; workplace observation (visual, management safety culture (questionnaire and managers interviews (oral. The survey included 200 workers, 120 supervisors and 80 managers, in 82 SSI. Four steps to a safety proactive action plans (PAP, (looking for clues, prioritization of identified potential hazard, making improvements to eliminate the risk and follow up, were rated by employees on a scale from 0 to 5. Paired t-test was used to appraise the significant difference between the managers’ mean scores rated by the supervisors and other workers. 77.1% of workers and 64.2% supervisors rated their managers as either “not done at all” or “poorly done”. Workers’ scores for managers PPA had statistically significantly lower ratings (mean=1.09, SEM = 0.22 compared to that of the supervisors rating (mean= 1.55, SEM = 0.32, with t (14 = -1.185, p = 0.784. There is a closed poor performance perception gaps, of managers’ PPA, of the two groups of employees. It can be concluded that safety is not emphasized, by managers of SSI, as overriding priority and this may have contributed to high reported injuries among their workforce. Courses to enhance managements’ understanding for inclusion of safety among the leading priorities becomes necessary. This will reduce work-related risks and promotes occupational safety and health among the group of workers.

  14. Magnetic field control of 90°, 180°, and 360° domain wall resistance

    Science.gov (United States)

    Majidi, Roya

    2012-10-01

    In the present work, we have compared the resistance of the 90°, 180°, and 360° domain walls in the presence of external magnetic field. The calculations are based on the Boltzmann transport equation within the relaxation time approximation. One-dimensional Néel-type domain walls between two domains whose magnetization differs by angle of 90°, 180°, and 360° are considered. The results indicate that the resistance of the 360° DW is more considerable than that of the 90° and 180° DWs. It is also found that the domain wall resistance can be controlled by applying transverse magnetic field. Increasing the strength of the external magnetic field enhances the domain wall resistance. In providing spintronic devices based on magnetic nanomaterials, considering and controlling the effect of domain wall on resistivity are essential.

  15. Beat the Fear of Public Speaking: Mobile 360° Video Virtual Reality Exposure Training in Home Environment Reduces Public Speaking Anxiety.

    Science.gov (United States)

    Stupar-Rutenfrans, Snežana; Ketelaars, Loes E H; van Gisbergen, Marnix S

    2017-10-01

    With this article, we aim to increase our understanding of how mobile virtual reality exposure therapy (VRET) can help reduce speaking anxiety. Using the results of a longitudinal study, we examined the effect of a new VRET strategy (Public Speech Trainer, PST), that incorporates 360° live recorded VR environments, on the reduction of public speaking anxiety. The PST was developed as a 360° smartphone application for a VR head-mounted device that participants could use at home. Realistic anxiety experiences were created by means of live 360° video recordings of a lecture hall containing three training sessions based on graded exposure framework; empty classroom (a) and with a small (b) and large audience (c). Thirty-five students participated in all sessions using PST. Anxiety levels were measured before and after each session over a period of 4 weeks. As expected, speaking anxiety significantly decreased after the completion of all PST sessions, and the decrement was the strongest in participants with initially high speaking anxiety baseline levels. Results also revealed that participants with moderate and high speaking anxiety baseline level differ in the anxiety state pattern over time. Conclusively and in line with habituation theory, the results supported the notion that VRET is more effective when aimed at reducing high-state anxiety levels. Further implications for future research and improvement of current VRET strategies are discussed.

  16. 37 CFR 360.12 - Form and content of claims.

    Science.gov (United States)

    2010-07-01

    ... SUBMISSION OF ROYALTY CLAIMS FILING OF CLAIMS TO ROYALTY FEES COLLECTED UNDER COMPULSORY LICENSE Satellite Claims § 360.12 Form and content of claims. (a) Forms. (1) Each claim to compulsory license royalty fees... owner entitled to claim the royalty fees. (ii) A general statement of the nature of the copyright owner...

  17. 37 CFR 360.3 - Form and content of claims.

    Science.gov (United States)

    2010-07-01

    ... SUBMISSION OF ROYALTY CLAIMS FILING OF CLAIMS TO ROYALTY FEES COLLECTED UNDER COMPULSORY LICENSE Cable Claims § 360.3 Form and content of claims. (a) Forms. (1) Each claim to cable compulsory license royalty fees... copyright owner entitled to claim the royalty fees. (ii) A general statement of the nature of the copyright...

  18. Safety analysis report of the irradiation test of Type-B bundle

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Choong Sung; Lim, I. C.; Lee, B. C.; Ryu, J. S.; Kim, H. R

    2000-06-01

    The HANARO fuel, U{sub 3}Si-A1, has been developed by AECL and tested in NRU reactor. In the course of the fuel qualification tests, only one case was performed under the higher power condition than maximum linear power which was expected in the design stage. The Korea regulatory body, KINS imposed that HANARO shall be operated at the power level less than 24MW which is 80% of the design full power until HANARO shows the repetitive performance of the fuel at the power condition abov e 112.8KW/m. To resolve this imposition, KAERI designed two types of special test bundles: two non-instrumented(Type-A) and one instrumented(Type-B) test bundles. Two Type-A bundles were irradiated in HANARO: one of them has finished PIE and the other is under PIE. Type-B bundle was loaded in the core during 1.32 day at 1996, but outstanding FIV(flow induced vibration) was observed at the pool top because of long guide tube attached to the top of the bundle. The successful installation of the chimney fastener to fix the guide tube resulted in conducting the irradiation test of Type-B bundle again. The test will start at mid- July, 2000. In order to safely do the Type-B irradiation test, the safety analysis for the nuclear, mechanical and thermal-hydraulic aspects was performed. The reactivity worth and the maximum 1 near power predicted by VENTURE are 6.3mk/k and 121.6kW/m, respectively. Thermal margins for normal and transient conditions using MATRA-h, are assessed to satisfy the safety criteria.

  19. Survivorship Care Plan Information Needs: Perspectives of Safety-Net Breast Cancer Patients.

    Science.gov (United States)

    Burke, Nancy J; Napoles, Tessa M; Banks, Priscilla J; Orenstein, Fern S; Luce, Judith A; Joseph, Galen

    2016-01-01

    Despite the Institute of Medicine's (IOM) 2005 recommendation, few care organizations have instituted standard survivorship care plans (SCPs). Low health literacy and low English proficiency are important factors to consider in SCP development. Our study aimed to identify information needs and survivorship care plan preferences of low literacy, multi-lingual patients to support the transition from oncology to primary care and ongoing learning in survivorship. We conducted focus groups in five languages with African American, Latina, Russian, Filipina, White, and Chinese medically underserved breast cancer patients. Topics explored included the transition to primary care, access to information, knowledge of treatment history, and perspectives on SCPs. Analysis of focus group data identified three themes: 1) the need for information and education on the transition between "active treatment" and "survivorship"; 2) information needed (and often not obtained) from providers; and 3) perspectives on SCP content and delivery. Our data point to the need to develop a process as well as written information for medically underserved breast cancer patients. An SCP document will not replace direct communication with providers about treatment, symptom management and transition, a communication that is missing in participating safety-net patients' experiences of cancer care. Women turned to peer support and community-based organizations in the absence of information from providers. "Clear and effective" communication of survivorship care for safety-net patients requires dedicated staff trained to address wide-ranging information needs and uncertainties.

  20. 30 CFR 206.360 - What records must I keep to support my calculations of royalty or fees under this subpart?

    Science.gov (United States)

    2010-07-01

    ... calculations of royalty or fees under this subpart? 206.360 Section 206.360 Mineral Resources MINERALS... Resources § 206.360 What records must I keep to support my calculations of royalty or fees under this subpart? If you determine royalties or direct use fees for your geothermal resource under this subpart...

  1. National report of the Slovak Republic - proposal. Compiled in terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. Jun 2008

    International Nuclear Information System (INIS)

    Jurina, V.; Viktory, D.; Kobzova, D.; Petrik, T.; Sovcik, J.; Hekel, P.; Suess, J.; Tomek, J.; Lukacovic, J.; Hekel, P.; Ivan, J.; Ziakova, M.; Metke, E.; Pospisil, M.; Turner, M.; Homola, J.; Konecny, L.; Parimucha, F.; Vaclav, J.; Horvath, J.; Soos, F.; Betak, A.; Pospisil, P.; Mihaly, B.; Kubala, M.; Schmidtova, B.; Orihel, M.; Vasina, D.; Balaz, J.; Ehn, L.; Micovicova, D.; Vrtoch, M.; Mlcuch, L.; Granak, P.; Meleg, J.; Sedliak, D.; Bardy, M.; Gogoliak, J.; Prazska, M.; Burslova, J.

    2008-06-01

    A brief national safety report of the Slovak Republic compiled in terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management in 2008 is presented. This safety report consists of following chapters: (A) Introduction; (B) Spent nuclear fuel (SNF) and radioactive waste (RAW) management conception; (C) Scope of application; (D) Spent nuclear fuel (SNF) and radioactive waste (RAW) management; (E) Legislation and regulatory framework; (F) General safety provisions; (G) Safety of spent nuclear fuel management; (H) Safety of radioactive waste management; (I) Transboundary movement of spent nuclear fuel and radioactive waste; (J) Discussed sealed radioactive sources; (K) Planned measures to improve safety; (L) Annexes

  2. Seismic safety research program plan

    International Nuclear Information System (INIS)

    1987-05-01

    This document presents a plan for seismic research to be performed by the Structural and Seismic Engineering Branch in the Office of Nuclear Regulatory Research. The plan describes the regulatory needs and related research necessary to address the following issues: uncertainties in seismic hazard, earthquakes larger than the design basis, seismic vulnerabilities, shifts in building frequency, piping design, and the adequacy of current criteria and methods. In addition to presenting current and proposed research within the NRC, the plan discusses research sponsored by other domestic and foreign sources

  3. Criticality Safety Evaluation for 30B and 48X UF6 Cylinders for Transportation and Storage

    International Nuclear Information System (INIS)

    Mokhatri, Homami Zahra; Nematollahi, Mohammadreza; Kamyab, Shahabeddin

    2011-01-01

    30B and 48X cylinders are two standard containers have been used for transportation and storage of uranium hexafluoride with 21/2-ton and 10-ton loading capacity, respectively. For the sake of nuclear safety, the long-term safe storage and transportation of the cylinders are necessary to be concerned. Safe limits in handling and storage of 30B and 48X cylinders from the criticality safety considerations, has been investigated in this paper, by using the MCNP.4C code with ENDF/B-VI library data for the neutron cross sections. An infinite array model (with and without over pack) incorporating an internal H/U ratio of 0.088 was then developed to determine the optimal interstitial moderation. The maximum k eff value for the conditions of optimal interstitial moderation with the premise of no water leakage into the UF 6 cylinder has been shown to be 0.79209 ± 0.0011 for the 30B cylinder and 0.7625±0.0013 for 48X cylinder with 5 wt % 235 U enrichment. Based on this evaluation, the 30B and 48X UF 6 cylinders with 5 wt % 235 U enrichment meet the 10 CFR part 71 criteria for Fissile Class I packages, even in the worst case, and has a Transport Index (TI) of zero for criticality safety purposes

  4. Adaptation to safety measures : there is still a lot to do.

    NARCIS (Netherlands)

    Levelt, P.B.M.

    1992-01-01

    This paper considers how road safety measures can influence driving behaviour. Ajzen's `Model of Planned Behaviour' is applied to traffic behaviour and an extension to the model suggested. The `Theory of Reasoned Action' is outlined. The importance of a) subjective norms, b) weighing attitudes and

  5. 32 CFR Appendix D to Part 651 - Public Participation Plan

    Science.gov (United States)

    2010-07-01

    ... as news releases to local media, announcements to local citizens groups, and Commander's letters... included in the scoping process (AR 360-5). The plan must include the following: (1) Information..., announcements to local citizens groups, and Commander's letters at each phase or milestone (more frequently if...

  6. 10 CFR 32.101 - Schedule B-prototype tests for luminous safety devices for use in aircraft.

    Science.gov (United States)

    2010-01-01

    ....101 Schedule B—prototype tests for luminous safety devices for use in aircraft. An applicant for a... 10 Energy 1 2010-01-01 2010-01-01 false Schedule B-prototype tests for luminous safety devices for use in aircraft. 32.101 Section 32.101 Energy NUCLEAR REGULATORY COMMISSION SPECIFIC DOMESTIC LICENSES...

  7. Comparative sensitivity study of some criticality safety benchmark experiments using JEFF-3.1.2, JEFF-3.2T and ENDF/B-VII.1

    International Nuclear Information System (INIS)

    Kooyman, Timothee; Messaoudia, Nadia

    2014-01-01

    A sensitivity study on a set of evaluated criticality benchmarks with two versions of the JEFF nuclear data library, namely JEFF-3.1.2 and JEFF-3.2T, and ENDF/B-VII.1 was performed using MNCP(X) 2.6.0. As these benchmarks serve to estimate the upper safety limit for criticality risk analysis at SCK.CEN the sensitivity of their results to nuclear data is an important parameter to asses. Several nuclides were identified as being responsible for an evident change in the effective multiplication factor k eff : 235 U, 239 Pu, 240 Pu, 54 Fe, 56 Fe, 57 Fe and 208 Pb. A high sensitivity was found to the fission cross-section of all the fissile material in the study. Additionally, a smaller sensitivity to inelastic and capture cross-section of 235 U and 240 Pu was also found. Sensitivity to the scattering law for non-fissile material was postulated. The biggest change in the k eff due to non-fissile material was due to 208 Pb evaluation (±700 pcm), followed by 56 Fe (±360 pcm) for both versions of the JEFF library. Changes due to 235 U (±300 pcm) and Pu isotopes (±120 pcm for 239 Pu and ±80 pcm for 240 Pu) were found only with JEFF-3.1.2. 238 U was found to have no effect on the k eff . Significant improvements were identified between the two versions of the JEFF library. No further differences were found between the JEFF-3.2T and the ENDF/B-VII.1 calculations involving 235 U or Pu. (authors)

  8. Action plan in response to March 1981 report to NFPQT Committee

    International Nuclear Information System (INIS)

    1981-03-01

    This plan of action has been prepared at the direction of the Acting Under Secretary in response to the report of the Nuclear Facilities Personnel Qualifications and Training (NFPQT) Committee on A Safety Assessment of Department of Energy Nuclear Reactors. Senior Department officials with Headquarters responsibilities for the safety of nuclear facilities owned by and operated for the Department have developed this plan with input from the operations office managers having operational responsibility for such facilities. A summary of the plan's objectives and a cross-reference to the findings of the NFPQT Committee Report is attached to the plan. Appendix A contains implementing actions and Appendix B contains a summary of actions responsive to lessons learned from the TMI accident that have been completed or are well underway. Although the plan is written in definitive language, the specific actions (such as organization realignments and proposals) will be subject to appropriate review and approval. Also, other adjustments may be required as the actions are implemented

  9. DFT study on the isomerization and tautomerism in vitamins B3 (niacin), B5 (pantothenic acid) and B7 (biotin)

    Science.gov (United States)

    Valadbeigi, Younes; Farrokhpour, Hossein; Tabrizchi, Mahmoud

    2014-05-01

    Isomerization and tautomerism of the three water soluble vitamins including B3, B5 and B7 were studied applying density functional theory using B3LYP method in gas and aqueous phases. Activation energies (Ea), Gibbs free energies of activation (ΔG#), and imaginary frequencies of the transition state structures were calculated for all the isomerization and tautomerism reactions. Activation energies of the neutral → zwitterion (amine-enamine) tautomerism in vitamin B3 were 310-360 kJ/mol where these values for the keto-enol tautomerism were 100-130 kJ/mol. It was found that water molecule catalyzes the tautomerism and decreases the activation energies about 90-160 kJ/mol.

  10. Planning report for the safety assessment SR-Can

    International Nuclear Information System (INIS)

    2003-06-01

    This document is a planning report for SKB's next assessment of long-term safety for a KBS 3 repository. The assessment, SR-Can, is to be finished by the end of 2005 and will be used for SKB's application to build an Encapsulation plant for spent nuclear fuel. Apart from outlining the methodology, the report discusses the handling in SR-Can of a number of important issues regarding the near field, the geosphere, the biosphere, the climatic evolution etc. The Swedish nuclear safety and radiation protection authorities have recently issued regulations concerning the final disposal of nuclear waste. The principal compliance criterion states that the annual risk of harmful effects must not exceed 10 -6 for a representative individual in the group exposed to the greatest risk. There are also a number of requirements on methodological aspects of the safety assessment as well as on the contents of a safety report. The regulations are reproduced in an Appendix to this report. The primary safety function of the KBS 3 system is to completely isolate the spent nuclear fuel within copper canisters over the entire assessment period, which will be one million years in SR-Can. Should a canister be damaged, the secondary safety function is to retard any releases from the canisters. The main steps of the assessment are the following: 1. Qualitative system description, FEP processing: This step consists of defining a system boundary and of describing the system on a format suitable for the safety assessment. Databases of relevant features, events and processes influencing long-term safety are structured and used as one starting point for the assessment. 2. Initial state descriptions. 3. Process descriptions: In this step all identified processes within the system boundary involved in the long-term evolution of the system are described in detail. 4. Description of boundary conditions: This step is a broad description of the evolution of the boundaries of the system, focussing mainly

  11. Reliability and safety program plan outline for the operational phase of a waste isolation facility

    International Nuclear Information System (INIS)

    Ammer, H.G.; Wood, D.E.

    1977-01-01

    A Reliability and Safety Program plan outline has been prepared for the operational phase of a Waste Isolation Facility. The program includes major functions of risk assessment, technical support activities, quality assurance, operational safety, configuration monitoring, reliability analysis and support and coordination meetings. Detailed activity or task descriptions are included for each function. Activities are time-phased and presented in the PERT format for scheduling and interactions. Task descriptions include manloading, travel, and computer time estimates to provide data for future costing. The program outlined here will be used to provide guidance from a reliability and safety standpoint to design, procurement, construction, and operation of repositories for nuclear waste. These repositories are to be constructed under the National Waste Terminal Storage program under the direction of the Office of Waste Isolation, Union Carbide Corp. Nuclear Division

  12. Preliminary safety evaluation, based on initial site investigation data. Planning document

    International Nuclear Information System (INIS)

    Hedin, Allan

    2002-12-01

    This report is a planning document for the preliminary safety evaluations (PSE) to be carried out at the end of the initial stage of SKBs ongoing site investigations for a deep repository for spent nuclear fuel. The main purposes of the evaluations are to determine whether earlier judgements of the suitability of the candidate area for a deep repository with respect to long-term safety holds up in the light of borehole data and to provide feed-back to continued site investigations and site specific repository design. The preliminary safety evaluations will be carried out by a safety assessment group, based on a site model, being part of a site description, provided by a site modelling group and a repository layout within that model suggested by a repository engineering group. The site model contains the geometric features of the site as well as properties of the host rock. Several alternative interpretations of the site data will likely be suggested. Also the biosphere is included in the site model. A first task for the PSE will be to compare the rock properties described in the site model to previously established criteria for a suitable host rock. This report gives an example of such a comparison. In order to provide more detailed feedback, a number of thermal, hydrological, mechanical and chemical analyses of the site will also be included in the evaluation. The selection of analyses is derived from the set of geosphere and biosphere analyses preliminarily planned for the comprehensive safety assessment named SR-SITE, which will be based on a complete site investigation. The selection is dictated primarily by the expected feedback to continued site investigations and by the availability of data after the PSE. The repository engineering group will consider several safety related factors in suggesting a repository layout: Thermal calculations will be made to determine a minimum distance between canisters avoiding canister surface temperatures above 100 deg C

  13. IN10 data processing on the Rutherford Laboratory IBM 360

    International Nuclear Information System (INIS)

    Howells, W.S.; Anderson, I.S.

    1978-09-01

    This report described modifications made to some of the IN10 spectrometer data analysis programs in use at the Institut Laue-Langevin, Grenoble in order that they may be used on the IBM 360 system at the Rutherford Laboratory. Fuller descriptions of the programs are contained in the original manual (Users' Guide to Processing IN10 Data by W S Howells, ILL Internal Report (1977). Programs discussed are: a) FAST. A program for fitting Lorentzians to raw data. This is a modification of the ILL programs FAST and HAST. b) SUPER. A convolution program for fitting quasielastic peaks to corrected data. This program is based on the ILL program SUPER. c) SAND. A convolution program for fitting an elastic and a Quasielastic peak to data. This is similar to the ILL version of SAND. d) SWIFT. A program similar to SUPER but faster. It is based on the ILL program CONTTY. Before using these programs users must consult the NBRU in order to obtain an account number and a user identifier. (U.K.)

  14. Additional safety assessments, follow-up of stress tests of the French nuclear power stations. Action plan of the nuclear safety authority

    International Nuclear Information System (INIS)

    2012-01-01

    This document presents the French national action plan defined by the Nuclear Safety Authority (ASN) in compliance with the recommendations made by the ENSREG (European nuclear safety regulators group). It refers to decisions taken at the national level after the Fukushima accident, recommendations after European stress tests, and recommendations after the extraordinary meeting of contracting parties at the Convention on Nuclear Safety of August 2012. For different topics, this document recalls the recommendations made by the peer review, indicates the ASN's opinion and progress or ASN's requirements for different power stations. The first part addresses the recommendations made by peers and based on the European review. Topics concern natural hazards (effects, detection, inspections and controls related to earthquakes, margin assessment with respect to flooding and natural hazards), the loss of safety systems (cooling systems, electricity supplies, actions, instruments, training, and so on), the management of a severe accident (reference levels, measures, guides, exercises, training, management of contaminated water, radiation protection, premises). The second part deals with topics addressed within the frame of the Convention: national organisations, organisations in an emergency and post-accidental situation, international cooperation. A third part addresses the follow-up of additional measures issued by the ASN

  15. Intra prediction using face continuity in 360-degree video coding

    Science.gov (United States)

    Hanhart, Philippe; He, Yuwen; Ye, Yan

    2017-09-01

    This paper presents a new reference sample derivation method for intra prediction in 360-degree video coding. Unlike the conventional reference sample derivation method for 2D video coding, which uses the samples located directly above and on the left of the current block, the proposed method considers the spherical nature of 360-degree video when deriving reference samples located outside the current face to which the block belongs, and derives reference samples that are geometric neighbors on the sphere. The proposed reference sample derivation method was implemented in the Joint Exploration Model 3.0 (JEM-3.0) for the cubemap projection format. Simulation results for the all intra configuration show that, when compared with the conventional reference sample derivation method, the proposed method gives, on average, luma BD-rate reduction of 0.3% in terms of the weighted spherical PSNR (WS-PSNR) and spherical PSNR (SPSNR) metrics.

  16. EVALUATION OF 360 ° TO GET TO KNOW THE PERFORMANCE OF THE STUDENTS OF THE CyBENP

    Directory of Open Access Journals (Sweden)

    Ofelia Arzate-Ortiz

    2014-07-01

    Full Text Available The skills assessment in institutions of higher education today is a challenge, assess skills from a viewpoint that leads to the improvement and student growth and not just issuing a rating, is the challenge. The methodology of evaluation of 360 allowed for the case of the present investigation to determine the performance of students CyBENP regarding generic skills acquired in the course of a semester to use the educational coaching as a tool for achieving the same, the results allow us to objectively knowing the skills developed by students with a look at the performance review as an opportunity to express themselves and improve, while allowing generate an action plan to enhance the performance of students.

  17. Implementation of Water Safety Plans (WSPs): A Case Study in the Coastal Area in Semarang City, Indonesia

    Science.gov (United States)

    Budiyono; Ginandjar, P.; Saraswati, L. D.; Pangestuti, D. R.; Martini; Jati, S. P.

    2018-02-01

    An area of 508.28 hectares in North Semarang is flooded by tidal inundation, including Bandarharjo village, which could affect water quality in the area. People in Bandarharjo use safe water from deep groundwater, without disinfection process. More than 90% of water samples in the Bandaharjo village had poor bacteriological quality. The aimed of the research was to describe the implementation of Water Safety Plans (WSPs) program in Bandarharjo village. This was a descriptive study with steps for implementations adopted the guidelines and tools of the World Health Organization. The steps consist of introducing WSPs program, team building, training the team, examination of water safety before risk assessment, risk assessment, minor repair I, examination of water safety risk, minor repair II (after monitoring). Data were analyzed using descriptive methods. WSPs program has been introduced and formed WSPs team, and the training of the team has been conducted. The team was able to conduct risks assessment, planned the activities, examined water quality, conduct minor repair and monitoring at the source, distribution, and households connection. The WSPs program could be implemented in the coastal area in Semarang, however regularly supervision and some adjustment are needed.

  18. State Environmental Policy Act (SEPA) Environmental Checklist Form 216-B-3 Expansion Ponds Closure Plan

    International Nuclear Information System (INIS)

    1993-12-01

    The 216-B-3 Expansion Ponds Closure Plan (Revision 1) consists of a Part A Dangerous Waste Permit Application and a Resource Conservation and Recovery Act Closure Plan. An explanation of the Part A submitted with this document is provided at the beginning of the Part A Section. The closure plan consists of nine chapters and five appendices. The 216-B-3 Pond System consists of a series of four earthen, unlined, interconnected ponds and the 216-B-3-3 Ditch that receive waste water from various 200 East Area operating facilities. These four ponds, collectively. Waste water (primarily cooling water, steam condensate, and sanitary water) from various 200 East Area facilities is discharged to the 216-B-3-3 Ditch. Water discharged to the 216-8-3-3 Ditch flows directly into the 216-B-3 Pond. In the past, waste water discharges to B Pond and the 216-B-3-3 Ditch contained mixed waste (radioactive waste and dangerous waste). The radioactive portion of mixed waste has been interpreted by the US Department of Energy (DOE) to be regulated under the Atomic Energy Act of 1954; the nonradioactive dangerous portion of mixed waste is regulated under RCRA. Mixed waste also may be considered a hazardous substance under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) when considering remediation of waste sites

  19. Measuring the Impacts of Water Safety Plans in the Asia-Pacific Region

    Directory of Open Access Journals (Sweden)

    Emily Kumpel

    2018-06-01

    Full Text Available This study investigated the effectiveness of Water Safety Plans (WSP implemented in 99 water supply systems across 12 countries in the Asia-Pacific region. An impact assessment methodology including 36 indicators was developed based on a conceptual framework proposed by the Center for Disease Control (CDC and before/after data were collected between November 2014 and June 2016. WSPs were associated with infrastructure improvements at the vast majority (82 of participating sites and to increased financial support at 37 sites. In addition, significant changes were observed in operations and management practices, number of water safety-related meetings, unaccounted-for water, water quality testing activities, and monitoring of consumer satisfaction. However, the study also revealed challenges in the implementation of WSPs, including financial constraints and insufficient capacity. Finally, this study provided an opportunity to test the impact assessment methodology itself, and a series of recommendations are made to improve the approach (indicators, study design, data collection methods for evaluating WSPs.

  20. Type B liquid package technical issues -- Experience with LR-56 safety analysis

    International Nuclear Information System (INIS)

    Smith, A.C.; Alstine, M.N. van; Gromada, R.J.; Hensel, S.J.; Gupta, N.K.

    1997-01-01

    In the course of the development of nuclear industry in France, shipment of Type B quantities (i.e., quantities having significant radiological consequences) of radioactive liquids between different, sites became necessary. Based on the experience acquired at the Commissariat a l'Energie Atomique (CEA) nuclear centers, a series of tanker trailers has been developed to meet this need. Similarly, as part of the ongoing program to process wastes to stable end forms, a need exists to move radioactive liquids at several DOE sites. The LR-56, developed by CEA to transport liquids of medium to high activity, was selected for these US applications, based on its design features and successful operating experience in France. No comparable Type B liquid packages are certified in the US Packages employed in transport of Type B quantities of liquids are either only suitable for small volumes, or are used within site boundaries with extensive administrative controls employed to insure that an adequate level of safety is maintained. The requirement is to provide safety equivalent to the level established by federal regulations in 10 CFR 71. Type B radioactive materials packages (RAM packages) are typically simple, rugged containers which are designed and fabricated in accordance with the ASME Boiler and Pressure Vessel Code to provide containment under the normal conditions of transport (NCT) and hypothetical accident conditions (HAC) established by the regulations. Packages designed for liquid contents must address a number of technical issues which are not common to packages for solid contents. This paper reviews the technical issues associated with Type B liquid packages from the perspective of the experience gained from the evaluation of the LR-56 for use at DOE sites

  1. Developing Your 360-Degree Leadership Potential.

    Science.gov (United States)

    Verma, Nupur; Mohammed, Tan-Lucien; Bhargava, Puneet

    2017-09-01

    Radiologists serve in leadership roles throughout their career, making leadership education an integral part of their development. A maxim of leadership style is summarized by 360-Degree Leadership, which highlights the ability of a leader to lead from any position within the organization while relying on core characteristics to build confidence from within their team. The qualities of leadership discussed can be learned and applied by radiologists at any level. These traits can form a foundation for the leader when faced with unfavorable events, which themselves allow the leader an opportunity to build trust. Copyright © 2017 American College of Radiology. Published by Elsevier Inc. All rights reserved.

  2. Examination of cadmium safety rod thermal test specimens and failure mechanism evaluation

    International Nuclear Information System (INIS)

    Thomas, J.K.; Peacock, H.B.; Iyer, N.C.

    1992-01-01

    The reactor safety rods may be subjected to high temperatures due to gamma heating after the core coolant level has dropped during the ECS phase of a hypothetical LOCA event. Accordingly, an experimental cadmium safety rod testing subtask was established as part of a task to address the response of reactor core components to this accident. Companion reports describe the experiments and a structural evaluation (finite element analysis) of the safety rod. This report deals primarily with the examination of the test specimens, evaluation of possible failure mechanisms, and confirmatory separate effects experiments. It is concluded that the failures observed in the cadmium safety rod thermal tests which occurred at low temperature (T 800 degrees C) with fast thermal ramp rates are concluded to be mechanical in nature without significant environmental degradation. Based on these tests, tasks were initiated to design and manufacture B 4 C safety rods to replace the cadmium safety rods. The B 4 C safety rods have been manufactured at this time and it is currently planned to charge them to the reactor in the near future. 60 refs

  3. Water safety plan at the Saharawi refugee camps in Tindouf (Algeria

    Directory of Open Access Journals (Sweden)

    R. García

    2018-01-01

    Full Text Available Since 1975, about 165,000 people from Western Sahara are living as refugees in the Sahara Desert near Tindouf (Algeria. Available water resources come from deep boreholes located up to tens of kilometers away from the settlements of the population, bulk water is treated in reverse osmosis plants and by chlorination systems and, after, distributed through a network of taps and water tankers. Water supply system complexity and extreme conditions force the elaboration of a Water Safety Plan, aiming to guarantee appropriate provision and quality of water. The plan follows a risk assessment methodology and establishes control mechanisms to minimize risk impacts, which are compiled in six action protocols for infrastructures and water quality monitoring. As a novel contribution, the proposed methodology developed in the refugee camps incorporates besides the conventional water quality assessment concepts, the analysis of the volume of supplied water, linked with some water-washed diseases. Since the end of 2014, those protocols have begun to be applied obtaining results that have a positive effect on the life quality of refugees.

  4. Health and safety plan for the Molten Salt Reactor Experiment remediation project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Burman, S.N.; Uziel, M.S.

    1995-12-01

    The Lockheed Martin Energy Systems, Inc., (Energy Systems) policy is to provide a safe and healthful workplace for all employees and subcontractors. The accomplishment of the policy requires that operations at the Molten Salt Reactor Experiment (MSRE) facility at the Department of Energy (DOE) Oak Ridge National Laboratory (ORNL) are guided by an overall plan and consistent proactive approach to safety and health (S and H) issues. The policy and procedures in this plan apply to all MSRE operations. The provisions of this plan are to be carried out whenever activities are initiated at the MSRE that could be a threat to human health or the environment. This plan implements a policy and establishes criteria for the development of procedures for day-to-day operations to prevent or minimize any adverse impact to the environment and personnel safety and health and to meet standards that define acceptable management of hazardous and radioactive materials and wastes. The plan is written to utilize past experience and the best management practices to minimize hazards to human health or the environment from events such as fires, explosions, falls, mechanical hazards, or any unplanned release of hazardous or radioactive materials to the air.

  5. Health and safety plan for the Molten Salt Reactor Experiment remediation project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Burman, S.N.; Uziel, M.S.

    1995-12-01

    The Lockheed Martin Energy Systems, Inc., (Energy Systems) policy is to provide a safe and healthful workplace for all employees and subcontractors. The accomplishment of the policy requires that operations at the Molten Salt Reactor Experiment (MSRE) facility at the Department of Energy (DOE) Oak Ridge National Laboratory (ORNL) are guided by an overall plan and consistent proactive approach to safety and health (S and H) issues. The policy and procedures in this plan apply to all MSRE operations. The provisions of this plan are to be carried out whenever activities are initiated at the MSRE that could be a threat to human health or the environment. This plan implements a policy and establishes criteria for the development of procedures for day-to-day operations to prevent or minimize any adverse impact to the environment and personnel safety and health and to meet standards that define acceptable management of hazardous and radioactive materials and wastes. The plan is written to utilize past experience and the best management practices to minimize hazards to human health or the environment from events such as fires, explosions, falls, mechanical hazards, or any unplanned release of hazardous or radioactive materials to the air

  6. Inspection planning

    International Nuclear Information System (INIS)

    Korosec, D.; Levstek, M.F.

    2001-01-01

    Slovenian Nuclear Safety Administration (SNSA) division of nuclear and radiological safety inspection has developed systematic approach to their inspections. To be efficient in their efforts regarding regular and other types of inspections, in past years, the inspection plan has been developed. It is yearly based and organized on a such systematic way, that all areas of nuclear safety important activities of the licensee are covered. The inspection plan assures appropriate preparation for conducting the inspections, allows the overview of the progress regarding the areas to be covered during the year. Depending on the licensee activities and nature of facility (nuclear power plant, research reactor, radioactive waste storage, others), the plan has different levels of intensity of inspections and also their frequency. One of the basic approaches of the plan is to cover all nuclear and radiological important activities on such way, that all regulatory requests are fulfilled. In addition, the inspection plan is a good tool to improve inspection effectiveness based on previous experience and allows to have the oversight of the current status of fulfillment of planned inspections. Future improvement of the plan is necessary in the light of newest achievements on this field in the nuclear world, that means, new types of inspections are planned and will be incorporated into plan in next year.(author)

  7. Nuclear Safety Review for 2014

    International Nuclear Information System (INIS)

    2014-07-01

    The Nuclear Safety Review 2014 focuses on the dominant nuclear safety trends, issues and challenges in 2013. The Executive Overview provides general nuclear safety information along with a summary of the major issues covered in this report: strengthening safety in nuclear installations; improving radiation, transport and waste safety; enhancing emergency preparedness and response (EPR); improving regulatory infrastructure and effectiveness; and strengthening civil liability for nuclear damage. The Appendix provides details on the activities of the Commission on Safety Standards, and activities relevant to the Agency’s safety standards. The global nuclear community has made steady and continuous progress in strengthening nuclear safety in 2013, as promoted by the IAEA Action Plan on Nuclear Safety (hereinafter referred to as “the Action Plan”) and reported in Progress in the Implementation of the IAEA Action Plan on Nuclear Safety (document GOV/INF/2013/8-GC(57)/INF/5), and the Supplementary Information to that report and Progress in the Implementation of the IAEA Action Plan on Nuclear Safety (document GOV/INF/2014/2). • Significant progress continues to be made in several key areas, such as assessments of safety vulnerabilities of nuclear power plants (NPPs), strengthening of the Agency’s peer review services, improvements in EPR capabilities, strengthening and maintaining capacity building, and protecting people and the environment from ionizing radiation. The progress that has been made in these and other areas has contributed to the enhancement of the global nuclear safety framework. • Significant progress has also been made in reviewing the Agency’s safety standards, which continue to be widely applied by regulators, operators and the nuclear industry in general, with increased attention and focus on vitally important areas such as design and operation of NPPs, protection of NPPs against severe accidents, and EPR. • The Agency continued to

  8. Technical Safety Requirements for the B695 Segment of the Decontamination and Waste Treatment Facility

    International Nuclear Information System (INIS)

    Larson, H L

    2007-01-01

    This document contains Technical Safety Requirements (TSRs) for the Radioactive and Hazardous Waste Management (RHWM) Division's B695 Segment of the Decontamination and Waste Treatment Facility (DWTF) at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the B695 Segment of the DWTF. The TSRs are derived from the Documented Safety Analysis (DSA) for the B695 Segment of the DWTF (LLNL 2004). The analysis presented there determined that the B695 Segment of the DWTF is a low-chemical hazard, Hazard Category 3, nonreactor nuclear facility. The TSRs consist primarily of inventory limits as well as controls to preserve the underlying assumptions in the hazard analyses. Furthermore, appropriate commitments to safety programs are presented in the administrative controls section of the TSRs. The B695 Segment of the DWTF (B695 and the west portion of B696) is a waste treatment and storage facility located in the northeast quadrant of the LLNL main site. The approximate area and boundary of the B695 Segment of the DWTF are shown in the B695 Segment of the DWTF DSA. Activities typically conducted in the B695 Segment of the DWTF include container storage, lab-packing, repacking, overpacking, bulking, sampling, waste transfer, and waste treatment. B695 is used to store and treat radioactive, mixed, and hazardous waste, and it also contains equipment used in conjunction with waste processing operations to treat various liquid and solid wastes. The portion of the building called Building 696 Solid Waste Processing Area (SWPA), also referred to as B696S in this report, is used primarily to manage solid radioactive waste. Operations specific to the SWPA include sorting and segregating low-level waste (LLW) and transuranic (TRU) waste, lab-packing, sampling, and crushing empty drums that previously contained LLW. A permit modification for B696S was submitted to DTSC in January 2004 to store and treat hazardous and mixed

  9. Guidance for implementing an environmental, safety and health assurance program. Volume 2. A model plan for environmental, safety and health staff audits and appraisals

    International Nuclear Information System (INIS)

    Ellingson, A.C.

    1980-09-01

    This is 1 of 15 documents designed to illustrate how an Environmental, Safety and Health (ES and H) Assurance Program may be implemented. The generic definition of ES and H Assurance Programs is given in a companion document entitled An Environmental, Safety and Health Assurance Program Standard. This document is concerned with ES and H audit and appraisal activities of an ES and H Staff Organization as they might be performed in an institution whose ES and H program is based upon the ES and H Assurance Program Standard. An annotated model plan for ES and H Staff audits and appraisals is presented and discussed

  10. Immunogenicity, reactogenicity, and safety of a P1.7b,4 strain-specific serogroup B meningococcal vaccine given to preteens.

    Science.gov (United States)

    Hosking, Jamie; Rasanathan, Kumanan; Mow, Florina Chan; Jackson, Catherine; Martin, Diana; O'Hallahan, Jane; Oster, Philipp; Ypma, Ellen; Reid, Stewart; Aaberge, Ingeborg; Crengle, Sue; Stewart, Joanna; Lennon, Diana

    2007-11-01

    New Zealand (NZ) has experienced a Neisseria meningitidis serogroup B epidemic since 1991. MeNZB, a strain-specific outer membrane vesicle vaccine made using an NZ epidemic strain isolate, NZ98/254 (B:4:P1.7b,4), from two manufacturing sites, the Norwegian Institute of Public Health (NIPH) and Chiron Vaccines (CV; now Novartis), was evaluated for safety, immunogenicity, and reactogenicity in this observer-blind trial with 8- to 12-year-old children. In year 1, cohort A (n = 302) was randomized 4:1 for receipt of NIPH-MeNZB or MenBvac (Norwegian parent vaccine strain 44/76; B:15:P1.7,16). In year 2, cohort B (n = 313) was randomized 4:1 for receipt of CV-MeNZB or NIPH-MeNZB. Participants all received three vaccinations 6 weeks apart. Local and systemic reactions were monitored for 7 days. Seroresponse was defined as a fourfold or greater rise in the serum bactericidal antibody titer from the baseline titer as measured by a serum bactericidal assay. Those with baseline titers of /=1:8 to serorespond. Intention-to-treat (ITT) and per protocol (PP) analyses are presented. In cohort A, 74% (ITT) and 73% (PP) of NIPH-MeNZB recipients demonstrated seroresponses against NZ98/254 after three doses, versus 32% (ITT and PP) of MenBvac recipients. In cohort B, seroresponses against NZ98/254 after three doses occurred in 79% (ITT and PP) of CV-MeNZB versus 75% (ITT) and 76% (PP) of NIPH-MeNZB recipients. Vaccines were tolerable, with no vaccine-related serious adverse events. In conclusion, the NZ strain meningococcal B vaccine (MeNZB) from either manufacturing site was immunogenic against New Zealand epidemic vaccine strain meningococci with no safety concerns when given in three doses to these 8- to 12-year-old children.

  11. ALGORITMOS PARA CONSTRUÇÃO DE PANORAMA DE IMAGENS 360 E VISUALIZAÇÃO

    Directory of Open Access Journals (Sweden)

    Alan Kazuo Hiraga

    2013-07-01

    Full Text Available This paper presents a methodology for the construction of mosaic images to form 360 panorama and an application for viewing. We used the SIFT and RANSAC algorithms commonly found in the literature for matching images. The algorithms for projection, adjustment of images and Blend for smoothing the joints were implemented in this paper using the OpenCV Computer Vision library. The methodology of this research techniques were applied to reduce the distortions caused in the joints of successive images, as well as increase the quality of the final panorama and get better performance. The viewer application developed in C# shows the 360 image resulting from images stitching into a cylinder with the point of view inside. The results of the experiments performed using the proposed technique has proved satisfactory, the mosaic formed by the joining of multiple pictures suffers little distortion, however, these distortions do not interfere with the final formation of the panorama 360, which provides good visual quality.

  12. Development of a strategic plan for food security and safety in the Inuvialuit Settlement Region, Canada.

    Science.gov (United States)

    Fillion, Myriam; Laird, Brian; Douglas, Vasiliki; Van Pelt, Linda; Archie, Diane; Chan, Hing Man

    2014-01-01

    Current social and environmental changes in the Arctic challenge the health and well-being of its residents. Developing evidence-informed adaptive measures in response to these changes is a priority for communities, governments and researchers. To develop strategic planning to promote food security and food safety in the Inuvialuit Settlement Region (ISR), Northwest Territories (NWT), Canada. A qualitative study using group discussions during a workshop. A regional workshop gathered Inuit organizations and community representatives, university-based researchers from the Inuit Health Survey (IHS) and NWT governmental organizations. Discussions were structured around the findings from the IHS. For each key area, programs and activities were identified and prioritized by group discussion and voting. The working group developed a vision for future research and intervention, which is to empower communities to promote health, well-being and environmental sustainability in the ISR. The group elaborated missions for the region that address the following issues: (a) capacity building within communities; (b) promotion of the use of traditional foods to address food security; (c) research to better understand the linkages between diseases and contaminants in traditional foods, market foods and lifestyle choices; (d) and promotion of affordable housing. Five programs to address each key area were developed as follows: harvest support and traditional food sharing; education and promotion; governance and policy; research; and housing. Concrete activities were identified to guide future research and intervention projects. The results of the planning workshop provide a blueprint for future research and intervention projects.

  13. Planning for Campus Safety

    Science.gov (United States)

    Dessoff, Alan

    2009-01-01

    From natural disasters to criminal violence, facilities officers are often called on to address campus safety and security issues beyond their usual responsibilities. Their experiences in coping with unanticipated events have produced a catalogue of lessons learned that can help them and their peers at other institutions who might face the same…

  14. Efficacy, safety, and patient preference of monoamine oxidase B inhibitors in the treatment of Parkinson's disease

    Directory of Open Access Journals (Sweden)

    Bradley J Robottom

    2011-01-01

    Full Text Available Bradley J RobottomDepartment of Neurology, University of Maryland School of Medicine, Baltimore, MD, USAAbstract: Parkinson's disease (PD is the second most common neurodegenerative disease and the most treatable. Treatment of PD is symptomatic and generally focuses on the replacement or augmentation of levodopa. A number of options are available for treatment, both in monotherapy of early PD and to treat complications of advanced PD. This review focuses on rasagiline and selegiline, two medications that belong to a class of antiparkinsonian drugs called monoamine oxidase B (MAO-B inhibitors. Topics covered in the review include mechanism of action, efficacy in early and advanced PD, effects on disability, the controversy regarding disease modification, safety, and patient preference for MAO-B inhibitors.Keywords: monoamine oxidase inhibitors, rasagiline, selegiline, Parkinson's disease, efficacy, safety

  15. 12 CFR 563b.380 - May my employee stock ownership plan purchase conversion shares?

    Science.gov (United States)

    2010-01-01

    ... 12 Banks and Banking 5 2010-01-01 2010-01-01 false May my employee stock ownership plan purchase... THE TREASURY CONVERSIONS FROM MUTUAL TO STOCK FORM Standard Conversions Offers and Sales of Stock § 563b.380 May my employee stock ownership plan purchase conversion shares? (a) Your tax-qualified...

  16. 41 CFR 102-74.360 - What are the specific accident and fire prevention responsibilities of occupant agencies?

    Science.gov (United States)

    2010-07-01

    ... other hanging materials that are made of non-combustible or flame-resistant fabric; (f) Use only... resistant; (g) Cooperate with GSA to develop and maintain fire prevention programs that provide the maximum... accident and fire prevention responsibilities of occupant agencies? 102-74.360 Section 102-74.360 Public...

  17. Aerospace Safety Advisory Panel

    Science.gov (United States)

    1999-01-01

    little flexibility to begin long lead-time items for upgrades or contingency planning. For example, the section on computer hardware and software contains specific findings related to required longer range safety-related actions. NASA can be proud of its accomplishments this past year, but must remain ever vigilant, particularly as ISS assembly begins to accelerate. The Panel will continue to focus on both the short- and long-term aspects of risk management and safety planning. This task continues to be made manageable and productive by the excellent cooperation the Panel receives from both NASA and its contractors. Particular emphasis will continue to be directed to longer term workforce and program planning issues as well as the immediate risks associated with ISS assembly and the initial flights of the X-33 and X-34. Section 2 of this report presents specific findings and recommendations generated by ASAP activities during 1998. Section 3 contains more detailed information in support of these findings and recommendations. Appendix A is a current roster of Panel members, consultants, and staff. Appendix B contains NASA's response to the findings and recommendations from the 1997 ASAP Annual Report. Appendix C details the fact-finding activities of the Panel in 1998. During the year, Mr. Richard D. Blomberg was elected chair of the Panel and Vice Admiral (VADM) Robert F Dunn was elected deputy chair. VADM Bernard M. Kauderer moved from consultant to member. Mr. Charles J. Donlan retired from the Panel after many years of meritorious service. Ms. Shirley C. McCarty and Mr. Robert L. ('Hoot') Gibson joined the Panel as consultants.

  18. K Basin sludge packaging design criteria (PDC) and safety analysis report for packaging (SARP) approval plan

    International Nuclear Information System (INIS)

    Brisbin, S.A.

    1996-01-01

    This document delineates the plan for preparation, review, and approval of the Packaging Design Crieteria for the K Basin Sludge Transportation System and the Associated on-site Safety Analysis Report for Packaging. The transportation system addressed in the subject documents will be used to transport sludge from the K Basins using bulk packaging

  19. 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

  20. Quarterly report on the Ferrocyanide Safety Program for the period ending June 30, 1995

    International Nuclear Information System (INIS)

    Meacham, J.E.; Cash, R.J.; Dukelow, G.T.

    1995-07-01

    This is the seventeenth quarterly report on the progress of activities addressing the Ferrocyanide Safety Issue associated with Hanford Site high-level radioactive waste tanks. Progress in the Ferrocyanide Safety Program is reviewed, including work addressing the six pans of Defense Nuclear Facilities Safety Board Recommendation 90-7 (FR 1990). All work activities are described in the revised program plan (DOE 1994b), and this report follows the same format presented there. A summary of the key events occurring this quarter is presented