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.

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

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.

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

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

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.

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

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.

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...

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.)

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

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...

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

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

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

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 ...

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

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.

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

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...

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

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).

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)

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

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...

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.

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)

Tank farm health and safety plan. Revision 2

International Nuclear Information System (INIS)

Mickle, G.D.

1995-01-01

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

Tank farm health and safety plan. Revision 2

Energy Technology Data Exchange (ETDEWEB)

Mickle, G.D.

1995-03-29

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

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

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.

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)

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

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...

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...

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

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.)

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

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...

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...

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

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)

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.

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.)

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.

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

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

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.

[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.

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

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.

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.

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

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.

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…

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

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...

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

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

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.)

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

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

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

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.

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.)

Reducing risks and increasing safety in everyday life: the role of the public

International Nuclear Information System (INIS)

Enander, A.

1998-01-01

Full text of publication follows: in social science risk research more attention has been paid to examining how people in general perceive risks than to how they perceive possible measures to reduce risks and to increase their own safety. The latter area is, however, becoming increasingly important to understand, particularly in the light of current emphasis on individual responsibility in risk prevention and emergency preparedness. For example, in Sweden a major effort to increase safety awareness among the general public and to increase knowledge and skills in a number of safety-related areas is at present being planned. This effort is being undertaken as a cooperative effort between different authorities and institutions and is coordinated by the Swedish Rescue Services Agency. The intentions behind this and similar programmes raise a number of questions concerning how people view risks and safety measures in their own immediate environment. Knowledge of the factors affecting willingness to take precautions is important in the design of communication and information. The factors which are of significance may be risk-related and concern perceptions of personal risk, but may also be related to attitudes an beliefs concerning different precautionary measures, to perception of social norms and conventions as well as to personal experiences and values. This paper presents some data concerning views and actions among lay groups in relation to reducing risks and increasing safety. Factors affecting these views are discussed in the light of previous research and of empirical data from some recent studies. (author)

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

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...

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

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

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

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.

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

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…

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...

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.

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

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

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...

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)

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.

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)

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

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.

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

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

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''

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

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

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

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)

78 FR 11902 - Review of Gun Safety Technologies

Science.gov (United States)

2013-02-20

... DEPARTMENT OF JUSTICE Office of Justice Programs [OJP (NIJ) Docket No. 1615] Review of Gun Safety...'s Plan to reduce gun violence released on January 16, 2013, the U.S. Department of Justice, Office... emerging gun safety technologies and plans to issue a report on the availability and use of those...

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.

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...

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.

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...

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...

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

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

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.

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

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...

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.

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

Steam Pressure-Reducing Station Safety and Energy Efficiency Improvement Project

Energy Technology Data Exchange (ETDEWEB)

Lower, Mark D [ORNL; Christopher, Timothy W [ORNL; Oland, C Barry [ORNL

2011-06-01

The Facilities and Operations (F&O) Directorate is sponsoring a continuous process improvement (CPI) program. Its purpose is to stimulate, promote, and sustain a culture of improvement throughout all levels of the organization. The CPI program ensures that a scientific and repeatable process exists for improving the delivery of F&O products and services in support of Oak Ridge National Laboratory (ORNL) Management Systems. Strategic objectives of the CPI program include achieving excellence in laboratory operations in the areas of safety, health, and the environment. Identifying and promoting opportunities for achieving the following critical outcomes are important business goals of the CPI program: improved safety performance; process focused on consumer needs; modern and secure campus; flexibility to respond to changing laboratory needs; bench strength for the future; and elimination of legacy issues. The Steam Pressure-Reducing Station (SPRS) Safety and Energy Efficiency Improvement Project, which is under the CPI program, focuses on maintaining and upgrading SPRSs that are part of the ORNL steam distribution network. This steam pipe network transports steam produced at the ORNL steam plant to many buildings in the main campus site. The SPRS Safety and Energy Efficiency Improvement Project promotes excellence in laboratory operations by (1) improving personnel safety, (2) decreasing fuel consumption through improved steam system energy efficiency, and (3) achieving compliance with applicable worker health and safety requirements. The SPRS Safety and Energy Efficiency Improvement Project being performed by F&O is helping ORNL improve both energy efficiency and worker safety by modifying, maintaining, and repairing SPRSs. Since work began in 2006, numerous energy-wasting steam leaks have been eliminated, heat losses from uninsulated steam pipe surfaces have been reduced, and deficient pressure retaining components have been replaced. These improvements helped ORNL

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

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

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

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)

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.)

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

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

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

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.

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

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.

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

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.

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...

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...

Midwife-assisted planned home birth: an essential component of improving the safety of childbirth in Sub-Saharan Africa.

Science.gov (United States)

Dayyabu, Aliyu Labaran; Murtala, Yusuf; Grünebaum, Amos; McCullough, Laurence B; Arabin, Birgit; Levene, Malcolm I; Brent, Robert L; Monni, Giovanni; Sen, Cihat; Makatsariya, Alexander; Chervenak, Frank A

2018-05-29

Hospital births, when compared to out-of-hospital births, have generally led to not only a significantly reduced maternal and perinatal mortality and morbidity but also an increase in certain interventions. A trend seems to be emerging, especially in the US where some women are requesting home births, which creates ethical challenges for obstetricians and the health care organizations and policy makers. In the developing world, a completely different reality exists. Home births constitute the majority of deliveries in the developing world. There are severe limitations in terms of facilities, health personnel and deeply entrenched cultural and socio-economic conditions militating against hospital births. As a consequence, maternal and perinatal mortality and morbidity remain the highest, especially in Sub-Saharan Africa (SSA). Midwife-assisted planned home birth therefore has a major role to play in increasing the safety of childbirth in SSA. The objective of this paper is to propose a model that can be used to improve the safety of childbirth in low resource countries and to outline why midwife assisted planned home birth with coordination of hospitals is the preferred alternative to unassisted or inadequately assisted planned home birth in SSA.

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.)

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.

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

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

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

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.

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

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.

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

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)

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)

Use of the Home Safety Self-Assessment Tool (HSSAT) within Community Health Education to Improve Home Safety.

Science.gov (United States)

Horowitz, Beverly P; Almonte, Tiffany; Vasil, Andrea

2016-10-01

This exploratory research examined the benefits of a health education program utilizing the Home Safety Self-Assessment Tool (HSSAT) to increase perceived knowledge of home safety, recognition of unsafe activities, ability to safely perform activities, and develop home safety plans of 47 older adults. Focus groups in two senior centers explored social workers' perspectives on use of the HSSAT in community practice. Results for the health education program found significant differences between reported knowledge of home safety (p = .02), ability to recognize unsafe activities (p = .01), safely perform activities (p = .04), and develop a safety plan (p = .002). Social workers identified home safety as a major concern and the HSSAT a promising assessment tool. Research has implications for reducing environmental fall risks.

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.

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

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

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

Reducing health care hazards: lessons from the commercial aviation safety team.

Science.gov (United States)

Pronovost, Peter J; Goeschel, Christine A; Olsen, Kyle L; Pham, Julius C; Miller, Marlene R; Berenholtz, Sean M; Sexton, J Bryan; Marsteller, Jill A; Morlock, Laura L; Wu, Albert W; Loeb, Jerod M; Clancy, Carolyn M

2009-01-01

The movement to improve quality of care and patient safety has grown, but examples of measurable and sustained progress are rare. The slow progress made in health care contrasts with the success of aviation safety. After a tragic 1995 plane crash, the aviation industry and government created the Commercial Aviation Safety Team to reduce fatal accidents. This public-private partnership of safety officials and technical experts is responsible for the decreased average rate of fatal aviation accidents. We propose a similar partnership in the health care community to coordinate national efforts and move patient safety and quality forward.

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.

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

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.

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

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

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

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...

Reducing the sensitivity of IMPT treatment plans to setup errors and range uncertainties via probabilistic treatment planning

International Nuclear Information System (INIS)

Unkelbach, Jan; Bortfeld, Thomas; Martin, Benjamin C.; Soukup, Martin

2009-01-01

Treatment plans optimized for intensity modulated proton therapy (IMPT) may be very sensitive to setup errors and range uncertainties. If these errors are not accounted for during treatment planning, the dose distribution realized in the patient may by strongly degraded compared to the planned dose distribution. The authors implemented the probabilistic approach to incorporate uncertainties directly into the optimization of an intensity modulated treatment plan. Following this approach, the dose distribution depends on a set of random variables which parameterize the uncertainty, as does the objective function used to optimize the treatment plan. The authors optimize the expected value of the objective function. They investigate IMPT treatment planning regarding range uncertainties and setup errors. They demonstrate that incorporating these uncertainties into the optimization yields qualitatively different treatment plans compared to conventional plans which do not account for uncertainty. The sensitivity of an IMPT plan depends on the dose contributions of individual beam directions. Roughly speaking, steep dose gradients in beam direction make treatment plans sensitive to range errors. Steep lateral dose gradients make plans sensitive to setup errors. More robust treatment plans are obtained by redistributing dose among different beam directions. This can be achieved by the probabilistic approach. In contrast, the safety margin approach as widely applied in photon therapy fails in IMPT and is neither suitable for handling range variations nor setup errors.

Reduced scale PWR passive safety system designing by genetic algorithms

International Nuclear Information System (INIS)

Cunha, Joao J. da; Alvim, Antonio Carlos M.; Lapa, Celso Marcelo Franklin

2007-01-01

This paper presents the concept of 'Design by Genetic Algorithms (DbyGA)', applied to a new reduced scale system problem. The design problem of a passive thermal-hydraulic safety system, considering dimensional and operational constraints, has been solved. Taking into account the passive safety characteristics of the last nuclear reactor generation, a PWR core under natural circulation is used in order to demonstrate the methodology applicability. The results revealed that some solutions (reduced scale system DbyGA) are capable of reproducing, both accurately and simultaneously, much of the physical phenomena that occur in real scale and operating conditions. However, some aspects, revealed by studies of cases, pointed important possibilities to DbyGA methodological performance improvement

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

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

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

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

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...

Implementation of a safety action plan: reduction of the dose limits in a research centre

International Nuclear Information System (INIS)

Deworm, J.P.

1992-01-01

The Belgian Regulations require an annual Action Plan to improve the Safety and health conditions of works. Taking into consideration the preliminary versions of the new ICRP-recommendations, the 1990 Action Plan of the Belgian research Centre aimed to reduce the personal dose limit to 20 mSv/year and the annual collective dose by 10%. Major means used in the campaign were sensibility through information, consultation between hierarchy and executors and the application of a policy of discouragement at certain limits. As a result, the maximum level reaches was 16.5 mSv, while only 7 people received a dose above 10 mSv (of 219 who received a measurable dose, mean value 3,4 mSv). This success is due to the commitment at all levels of responsibilities. In 1991, the 20 mSv-limit is imposed as an obligation by the management, and a feasibility study to impose 10 mSv in near future is being undertaken. (author)

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.

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

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...

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.

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

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

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)

Process and device for reducing the presence in the safety containment of a nuclear reactor

International Nuclear Information System (INIS)

Stiefel, M.

1981-01-01

If faults occur, the excess pressure in the safety containment has to be reduced. Part of the gas contents of the safety containment is drawn off for this purpose. Hydrogen up to a maximum of 3.5% by volume is added to the drawn-off gas. The gas enriched with hydrogen is taken through a recombiner, where part of the oxygen content of the gas burns with the hydrogen, producing water. The gas with reduced oxygen content is returned to the safety containment via the free end of an annular pipe. The pressure existing in the safety containment is reduced according to the reduction in oxygen content. (orig./HP) [de

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.

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)

Closed medical negligence claims can drive patient safety and reduce litigation.

Science.gov (United States)

Pegalis, Steven E; Bal, B Sonny

2012-05-01

Medical liability reform is viewed by many physician groups as a means of reducing medical malpractice litigation and lowering healthcare costs. However, alternative approaches such as closed medical negligence claims data may also achieve these goals. We asked whether information gleaned from closed claims related to medical negligence could promote patient safety and reduce costs related to medical liability. Specifically, we investigated whether physician groups have examined such data to identify error patterns and to then institute specific patient treatment protocols. We searched for medical societies that have systematically examined closed medical negligence claims in their specialty to develop specific standards of physician conduct. We then searched the medical literature for published evidence of the efficacy, if any, related to the patient safety measures thus developed. Anesthesia and obstetric physician societies have successfully targeted costs and related concerns arising from medical malpractice lawsuits by using data from closed claims to develop patient safety and treatment guidelines. In both specialties, after institution of safety measures derived from closed medical negligence claims, the incidence and costs related to medical malpractice decreased and physician satisfaction improved. Tort reform, in the form of legislatively prescribed limits on damages arising from lawsuits, is not the only means of addressing the incidence and costs related to medical malpractice litigation. As the experience of anesthesia and obstetric physicians has demonstrated, safety guidelines derived from analyzing past medical malpractice litigation can achieve the same goals while also promoting patient safety.

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...

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.

Reducing the Probability of Incidents Through Behavior-Based Safety -- An Anomaly or Not?

International Nuclear Information System (INIS)

Turek, John A

2002-01-01

Reducing the probability of incidents through Behavior-Based Safety--an anomaly or not? Can a Behavior-Based Safety (BBS) process reduce the probability of an employee sustaining a work-related injury or illness? This presentation describes the actions taken to implement a sustainable BBS process and evaluates its effectiveness. The BBS process at the Stanford Linear Accelerator Center used a pilot population of national laboratory employees to: Achieve employee and management support; Reduce the probability of employees' sustaining work-related injuries and illnesses; and Provide support for additional funding to expand within the laboratory

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

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.

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)

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

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

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

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)

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.

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

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.

Regional cooperation to reduce the safety and security risks of Orphan radioactive sources

International Nuclear Information System (INIS)

Howard, Geoffrey; Hacker, Celia; Murray, Allan; Romallosa, Kristine; Caseria, Estrella; Africa del Castillo, Lorena

2008-01-01

ANSTO's Regional Security of Radioactive Sources (RSRS) Project, in cooperation with the Philippine Nuclear Research Institute (PNRI), has initiated a program to reduce the safety and security risks of orphan radioactive sources in the Philippines. Collaborative work commenced in February 2006 during the Regional Orphan Source Search and Methods Workshop, co-hosted by ANSTO and the US National Nuclear Security Administration. Further professional development activities have occurred following requests by PNRI to ANSTO to support improvements in PNRI's capability and training programs to use a range of radiation survey equipment and on the planning and methods for conducting orphan source searches. The activities, methods and outcomes of the PNRI-ANSTO cooperative program are described, including: i.) Delivering a training workshop which incorporates use of source search and nuclide identification equipment and search methodology; and train-the-trainer techniques for effective development and delivery of custom designed training in the Philippines; ii.) Support and peer review of course work on Orphan Source Search Equipment and Methodology developed by PNRI Fellows; iii.) Supporting the delivery of the inaugural National Training Workshop on Orphan Source Search hosted by PNRI in the Philippines; iv.) Partnering in searching for orphan sources in Luzon, Philippines, in May 2007. The methods employed during these international cooperation activities are establishing a new model of regional engagement that emphasises sustainability of outcomes for safety and security of radioactive sources. (author)

Shift work: health, performance and safety problems, traditional countermeasures, and innovative management strategies to reduce circadian misalignment

Science.gov (United States)

Smith, Mark R; Eastman, Charmane I

2012-01-01

There are three mechanisms that may contribute to the health, performance, and safety problems associated with night-shift work: (1) circadian misalignment between the internal circadian clock and activities such as work, sleep, and eating, (2) chronic, partial sleep deprivation, and (3) melatonin suppression by light at night. The typical countermeasures, such as caffeine, naps, and melatonin (for its sleep-promoting effect), along with education about sleep and circadian rhythms, are the components of most fatigue risk-management plans. We contend that these, while better than nothing, are not enough because they do not address the underlying cause of the problems, which is circadian misalignment. We explain how to reset (phase-shift) the circadian clock to partially align with the night-work, day-sleep schedule, and thus reduce circadian misalignment while preserving sleep and functioning on days off. This involves controlling light and dark using outdoor light exposure, sunglasses, sleep in the dark, and a little bright light during night work. We present a diagram of a sleep-and-light schedule to reduce circadian misalignment in permanent night work, or a rotation between evenings and nights, and give practical advice on how to implement this type of plan. PMID:23620685

Safer Systems: A NextGen Aviation Safety Strategic Goal

Science.gov (United States)

Darr, Stephen T.; Ricks, Wendell R.; Lemos, Katherine A.

2008-01-01

The Joint Planning and Development Office (JPDO), is charged by Congress with developing the concepts and plans for the Next Generation Air Transportation System (NextGen). The National Aviation Safety Strategic Plan (NASSP), developed by the Safety Working Group of the JPDO, focuses on establishing the goals, objectives, and strategies needed to realize the safety objectives of the NextGen Integrated Plan. The three goal areas of the NASSP are Safer Practices, Safer Systems, and Safer Worldwide. Safer Practices emphasizes an integrated, systematic approach to safety risk management through implementation of formalized Safety Management Systems (SMS) that incorporate safety data analysis processes, and the enhancement of methods for ensuring safety is an inherent characteristic of NextGen. Safer Systems emphasizes implementation of safety-enhancing technologies, which will improve safety for human-centered interfaces and enhance the safety of airborne and ground-based systems. Safer Worldwide encourages coordinating the adoption of the safer practices and safer systems technologies, policies and procedures worldwide, such that the maximum level of safety is achieved across air transportation system boundaries. This paper introduces the NASSP and its development, and focuses on the Safer Systems elements of the NASSP, which incorporates three objectives for NextGen systems: 1) provide risk reducing system interfaces, 2) provide safety enhancements for airborne systems, and 3) provide safety enhancements for ground-based systems. The goal of this paper is to expose avionics and air traffic management system developers to NASSP objectives and Safer Systems strategies.

Prioritization of generic safety issues

International Nuclear Information System (INIS)

Emrit, R.; Minners, W.; VanderMolen, H.

1983-12-01

This report presents the priority rankings for generic safety issues related to nuclear power plants. The purpose of these rankings is to assist in the timely and efficient allocation of NRC resources for the resolution of those safety issues that have a significant potential for reducing risk. The report focuses on the prioritization of generic safety issues. Issues primarily concerned with the licensing process or environmental protection and not directly related to safety have been excluded from prioritization. The prioritized issues include: TMI Action Plan items under development; previously proposed issues covered by Task Action Plans, except issues designated at Unresolved Safety Issues (USIs) which had already been assigned high priority; and newly-proposed issues. Future supplements to this report will include the prioritization of additional issues. The safety priority rankings are HIGH, MEDIUM, LOW, and DROP and have been assigned on the basis of risk significance estimates, the ratio of risk to costs and other impacts estimated to result if resolutions of the safety issues were implemented, and the consideration of uncertainties and other quantitative or qualitative factors. To the extent practical, estimates are quantitative

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)

Cyber Safety and Security for Reduced Crew Operations (RCO)

Science.gov (United States)

Driscoll, Kevin

2017-01-01

NASA and the Aviation Industry is looking into reduced crew operations (RCO) that would cut today's required two-person flight crews down to a single pilot with support from ground-based crews. Shared responsibility across air and ground personnel will require highly reliable and secure data communication and supporting automation, which will be safety-critical for passenger and cargo aircraft. This paper looks at the different types and degrees of authority delegation given from the air to the ground and the ramifications of each, including the safety and security hazards introduced, the mitigation mechanisms for these hazards, and other demands on an RCO system architecture which would be highly invasive into (almost) all safety-critical avionics. The adjacent fields of unmanned aerial systems and autonomous ground vehicles are viewed to find problems that RCO may face and related aviation accident scenarios are described. The paper explores possible data communication architectures to meet stringent performance and information security (INFOSEC) requirements of RCO. Subsequently, potential challenges for RCO data communication authentication, encryption and non-repudiation are identified. The approach includes a comprehensive safety-hazard analysis of the RCO system to determine top level INFOSEC requirements for RCO and proposes an option for effective RCO implementation. This paper concludes with questioning the economic viability of RCO in light of the expense of overcoming the operational safety and security hazards it would introduce.

Campus Capability Plan

Energy Technology Data Exchange (ETDEWEB)

Adams, C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Arsenlis, T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Bailey, A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Bergman, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Brase, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Brenner, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Camara, L. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Carlton, H. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Cheng, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Chrzanowski, P. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Colson, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); East, D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Farrell, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Ferranti, L. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Gursahani, A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Hansen, R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Helms, L. L. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Hernandez, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Jeffries, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Larson, D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Lu, K. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); McNabb, D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Mercer, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Skeate, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Sueksdorf, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Zucca, B. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Le, D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Ancria, R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Scott, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Leininger, L. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Gagliardi, F. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Gash, A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Bronson, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Chung, B. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Hobson, B. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Meeker, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Sanchez, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Zagar, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Quivey, B. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Sommer, S. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Atherton, J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2017-06-06

Lawrence Livermore National Laboratory Campus Capability Plan for 2018-2028. Lawrence Livermore National Laboratory (LLNL) is one of three national laboratories that are part of the National Nuclear Security Administration. LLNL provides critical expertise to strengthen U.S. security through development and application of world-class science and technology that: Ensures the safety, reliability, and performance of the U.S. nuclear weapons stockpile; Promotes international nuclear safety and nonproliferation; Reduces global danger from weapons of mass destruction; Supports U.S. leadership in science and technology. Essential to the execution and continued advancement of these mission areas are responsive infrastructure capabilities. This report showcases each LLNL capability area and describes the mission, science, and technology efforts enabled by LLNL infrastructure, as well as future infrastructure plans.

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

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

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.

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

Reducing nuclear danger through intergovernmental technical exchanges on nuclear materials safety management

International Nuclear Information System (INIS)

Jardine, L.J.; Peddicord, K.L.; Witmer, F.E.; Krumpe, P.F.; Lazarev, L.; Moshkov, M.

1997-01-01

The United States and Russia are dismantling nuclear weapons and generating hundreds of tons of excess plutonium and high enriched uranium fissile nuclear materials that require disposition. The U.S. Department of Energy and Russian Minatom organizations.are planning and implementing safe, secure storage and disposition operations for these materials in numerous facilities. This provides a new opportunity for technical exchanges between Russian and Western scientists that can establish an improved and sustained common safety culture for handling these materials. An initiative that develops and uses personal relationships and joint projects among Russian and Western participants involved in fissile nuclear materials safety management contributes to improving nuclear materials nonproliferation and to making a safer world. Technical exchanges and workshops are being used to systematically identify opportunities in the nuclear fissile materials facilities to improve and ensure the safety of workers, the public, and the environment

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

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.

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

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)

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.

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

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. 

Forward treatment planning techniques to reduce the normalization effect in Gamma Knife radiosurgery.

Science.gov (United States)

Cheng, Hao-Wen; Lo, Wei-Lun; Kuo, Chun-Yuan; Su, Yu-Kai; Tsai, Jo-Ting; Lin, Jia-Wei; Wang, Yu-Jen; Pan, David Hung-Chi

2017-11-01

In Gamma Knife forward treatment planning, normalization effect may be observed when multiple shots are used for treating large lesions. This effect can reduce the proportion of coverage of high-value isodose lines within targets. The aim of this study was to evaluate the performance of forward treatment planning techniques using the Leksell Gamma Knife for the normalization effect reduction. We adjusted the shot positions and weightings to optimize the dose distribution and reduce the overlap of high-value isodose lines from each shot, thereby mitigating the normalization effect during treatment planning. The new collimation system, Leksell Gamma Knife Perfexion, which contains eight movable sectors, provides an additional means to reduce the normalization effect by using composite shots. We propose different techniques in forward treatment planning that can reduce the normalization effect. Reducing the normalization effect increases the coverage proportion of higher isodose lines within targets, making the high-dose region within targets more uniform and increasing the mean dose to targets. Because of the increase in the mean dose to the target after reducing the normalization effect, we can set the prescribed marginal dose at a higher isodose level and reduce the maximum dose, thereby lowering the risk of complications. © 2017 Shuang Ho Hospital-Taipei Medical University. Journal of Applied Clinical Medical Physics published by Wiley Periodicals, Inc. on behalf of American Association of Physicists in Medicine.

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

Treatment Planning for Pulsed Reduced Dose-Rate Radiotherapy in Helical Tomotherapy

International Nuclear Information System (INIS)

Rong Yi; Paliwal, Bhudatt; Howard, Steven P.; Welsh, James

2011-01-01

Purpose: Pulsed reduced dose-rate radiotherapy (PRDR) is a valuable method of reirradiation because of its potential to reduce late normal tissue toxicity while still yielding significant tumoricidal effect. A typical method using a conventional linear accelerator (linac) is to deliver a series of 20-cGy pulses separated by 3-min intervals to give an effective dose-rate of just under 7 cGy/min. Such a strategy is fraught with difficulties when attempted on a helical tomotherapy unit. We investigated various means to overcome this limitation. Methods and Materials: Phantom and patient cases were studied. Plans were generated with varying combinations of field width (FW), pitch, and modulation factor (MF) to administer 200 cGy per fraction to the planning target in eight subfractions, thereby mimicking the technique used on conventional linacs. Plans were compared using dose-volume histograms, homogeneity indices, conformation numbers, and treatment time. Plan delivery quality assurance was performed to assess deliverability. Results: It was observed that for helical tomotherapy, intrinsic limitations in leaf open time in the multileaf collimator deteriorate plan quality and deliverability substantially when attempting to deliver very low doses such as 20-40 cGy. The various permutations evaluated revealed that the combination of small FW (1.0 cm), small MF (1.3-1.5), and large pitch (∼0.86), along with the half-gantry-angle-blocked scheme, can generate clinically acceptable plans with acceptable delivery accuracy (±3%). Conclusion: Pulsed reduced dose-rate radiotherapy can be accurately delivered using helical tomotherapy for tumor reirradiation when the appropriate combination of FW, MF, and pitch is used.

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

A prioritization of generic safety issues

International Nuclear Information System (INIS)

Emrit, R.; Riggs, R.; Milstead, W.; Pittman, J.

1991-07-01

This report presents the priority rankings for generic safety issues and related to nuclear power plants. The purpose of these rankings is to assist in the timely and efficient allocation of NRC resources for the resolution of those safety issues that have a significant potential for reducing risk. The report focuses on the prioritization of generic safety issues. Issues primarily concerned with the licensing process or environmental protection and not directly related to safety have been excluded from prioritization. The prioritized issues include: TMI Action Plan items under development; previously proposed issues covered by Task Action Plans, except issues designated as Un-resolved Safety Issues (USIs) which had already been assigned high priority; and newly-proposed issues. Future supplements to this report will include the prioritization of additional issues. The safety priority rankings are High, Medium, Low, and Drop and have been assigned on the basis of risk significance estimates, the ratio of risk to costs and other impacts estimated to result if resolutions of the safety issues were implemented, and the consideration of uncertainties and other quantitative or qualitative factors. To the extent practical, estimates are quantitative. 1310 refs

Multiyear Program Plan: Reducing Friction and Wear in Heavy Vehicles

Energy Technology Data Exchange (ETDEWEB)

R.R. Fessler; G.R. Fenske

1999-12-13

As described in its multiyear program plan for 1998-2000, the Office of Heavy Vehicle Technologies (OHVT) envisions the development of a fuel-flexible, energy-efficient, near-zero-emissions, heavy-duty U.S. diesel engine technology devolving into all truck classes as a real and viable strategy for reducing energy requirements for commercial transport services and the rapidly growing multipurpose vehicle market (pickups, vans, and sport utility vehicles). Implementation of the OHVT program plan will have significant national benefits in energy savings, cleaner air, more jobs, and increased gross domestic product (GDP). Successful implementation will reduce the petroleum consumption of Class 1-8 trucks by 1.4 million barrels of oil per day by 2020 and over 1.8 million by 2030, amounting to a reduction in highway petroleum consumption of 13.2% and 18.6%, respectively. All types of regulated emissions will be reduced, that is, 20% drop in PM10 emissions (41,000 metric tons per year) by 203 0, 17% reduction in CO2 greenhouse gases (205 million metric tons per year), 7% reduction in NOx, 20% reduction in NMHC, and 30% reduction in CO. An increase of 15,000 jobs by 2020 is expected, as is an increase of $24 billion in GDP. The strategy of OHVT is to focus primarily on the diesel engine since it has numerous advantages. It has the highest efficiency of any engine today, 45% versus 30% for production gasoline engines; and it can be made more efficient at least to 55% and possibly up to 63%. It is the engine of choice for heavy vehicles (trucks), because it offers power, efficiency, durability, and reliability and is used extensively in rail, marine, and off-road applications. Its emission can be ultra-low to near zero, and the production infrastructure is already in place. The primary goals of OHVT are as follows: (1) Develop by 2002 the diesel-engine enabling technologies to support large-scale industry dieselization of light trucks, achieving a 35% fuel efficiency

Shift work: health, performance and safety problems, traditional countermeasures, and innovative management strategies to reduce circadian misalignment

Directory of Open Access Journals (Sweden)

Smith MR

2012-09-01

Full Text Available Mark R Smith, Charmane I EastmanBiological Rhythms Research Laboratory, Rush University Medical Center, Chicago, IL, USAAbstract: There are three mechanisms that may contribute to the health, performance, and safety problems associated with night-shift work: (1 circadian misalignment between the internal circadian clock and activities such as work, sleep, and eating, (2 chronic, partial sleep deprivation, and (3 melatonin suppression by light at night. The typical countermeasures, such as caffeine, naps, and melatonin (for its sleep-promoting effect, along with education about sleep and circadian rhythms, are the components of most fatigue risk-management plans. We contend that these, while better than nothing, are not enough because they do not address the underlying cause of the problems, which is circadian misalignment. We explain how to reset (phase-shift the circadian clock to partially align with the night-work, day-sleep schedule, and thus reduce circadian misalignment while preserving sleep and functioning on days off. This involves controlling light and dark using outdoor light exposure, sunglasses, sleep in the dark, and a little bright light during night work. We present a diagram of a sleep-and-light schedule to reduce circadian misalignment in permanent night work, or a rotation between evenings and nights, and give practical advice on how to implement this type of plan.Keywords: circadian rhythms, night work, bright light, phase-shifting, sleep, melatonin

Water Safety Plan for drinking water risk management: the case study of Mortara (Pavia, Italy

Directory of Open Access Journals (Sweden)

Sabrina Sorlini

2017-08-01

Full Text Available The Water Safety Plan (WSP approach is an iterative method focused on analyzing the risks of water contamination in a drinking water supply system, from catchment to consumer, in order to protect human health. This approach is aimed at identifying and drastically reducing water contamination in the entire drinking water system, through the identification and mitigation or, if possible, elimination of all factors that may cause a chemical, physical, microbiological and radiological risk for water. This study developed a proposal of WSP for the drinking water supply system (DWSS of Mortara, Italy, in order to understand which are the preliminary evaluation aspects to be considered in the elaboration of a WSP. The DWSS of Mortara (a town of 15,500 inhabitants, located in northern Italy consists of three drinking water treatment plants (DWTPs, considering the following main contaminants: arsenic, iron, manganese and ammonia. Potential hazardous events and associated hazards were identified in each part of the water supply system. The risk assessment was carried out following the semi quantitative approach. The WSP proposal for Mortara was very useful not only as a risk mitigation approach, but also as a cost-effective tool for water suppliers. Furthermore, this approach will reduce public health risk, ensure a better compliance of water quality parameters with regulatory requirements, increase confidence of consumers and municipal authorities, and improve resource management due to intervention planning. Further, some new control measures are proposed by the WSP team within this work.

Increase plant safety and reduce cost by implementing risk-informed in-service inspection programs

International Nuclear Information System (INIS)

Billington, A.; Monette, P.

2001-01-01

The idea behind the program is that it is possible to 'inspect less, but inspect better'. In other words, the risk-informed In-Service Inspection (ISI) process is used to improve the effectiveness of examination of piping components, i.e. concentrate inspection resources and enhance inspection strategies on high safety significant locations, and reduce inspection requirements on others. The Westinghouse Owners Group (WOG) risk-informed ISI process has already been applied for full scope (Millstone 3, Surry 1) and limited scope (Beznau, Ringhals 4, Asco, Turkey Point 3). By examining the high safety significant piping segments for the different fluid piping systems, the total piping core damage frequency is reduced. In addition, more than 80% of the risk associated with potential pressure boundary failures is addressed with the WOG risk-informed ISI process, while typically less that 50% of this same risk is addressed by the current inspection programs. The risk-informed ISI processes are used to improve the effectiveness of inspecting safety-significant piping components, to reduce inspection requirements on other piping components, to evaluate improvements to plant availability and enhanced safety measures, including reduction of personnel radiation exposure, and to reduce overall Operation and Maintenance (O and M) costs while maintaining regulatory compliance. A description of the process as well as benefits from past projects is presented, since the methodology is applicable for WWER plant design. (author)

Increase plant safety and reduce cost by implementing risk-informed In-Service Inspection programs

International Nuclear Information System (INIS)

Billington, A.; Monette, P.; Doumont, C.

2000-01-01

The idea behind the program is that it is possible to 'inspect less, but inspect better'. In other words, the risk-informed In-Service Inspection (ISI) process is used to improve the effectiveness of examination of piping components, i.e. concentrate inspection resources and enhance inspection strategies on high safety significant locations, and reduce inspection requirements on others. The Westinghouse Owners Group (WOG) risk-informed ISI process has already been applied for full scope (Millstone 3, Surry 1) and limited scope (Beznau, Ringhals 4, Asco, Turkey Point 3). By examining the high safety significant piping segments for the different fluid piping systems, the total piping core damage frequency is reduced. In addition, more than 80% of the risk associated with potential pressure boundary failures is addressed with the WOG risk-informed ISI process, while typically less than 50% of this same risk is addressed by the current inspection programs. The risk-informed ISI processes are used: to improve the effectiveness of inspecting safety-significant piping components; to reduce inspection requirements on other piping components; to evaluate improvements to plant availability and enhanced safety measures, including reduction of personnel radiation exposure; and to reduce overall Operation and Maintenance (O and M) costs while maintaining regulatory compliance. A description of the process as well as benefits of past projects is presented, since the methodology is applicable for VVER plant design. (author)

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

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

Randomized Trial of Reducing Ambulatory Malpractice and Safety Risk: Results of the Massachusetts PROMISES Project.

Science.gov (United States)

Schiff, Gordon D; Reyes Nieva, Harry; Griswold, Paula; Leydon, Nicholas; Ling, Judy; Federico, Frank; Keohane, Carol; Ellis, Bonnie R; Foskett, Cathy; Orav, E John; Yoon, Catherine; Goldmann, Don; Weissman, Joel S; Bates, David W; Biondolillo, Madeleine; Singer, Sara J

2017-08-01

Evaluate application of quality improvement approaches to key ambulatory malpractice risk and safety areas. In total, 25 small-to-medium-sized primary care practices (16 intervention; 9 control) in Massachusetts. Controlled trial of a 15-month intervention including exposure to a learning network, webinars, face-to-face meetings, and coaching by improvement advisors targeting "3+1" high-risk domains: test result, referral, and medication management plus culture/communication issues evaluated by survey and chart review tools. Chart reviews conducted at baseline and postintervention for intervention sites. Staff and patient survey data collected at baseline and postintervention for intervention and control sites. Chart reviews demonstrated significant improvements in documentation of abnormal results, patient notification, documentation of an action or treatment plan, and evidence of a completed plan (all Pcoaches, and learning network decreased selected ambulatory safety risks often seen in malpractice claims.

Development of a statewide motorcycle safety plan for Texas : technical report.

Science.gov (United States)

2013-02-01

The objective of this research project was to develop a statewide plan to reduce motorcycle crashes and : injuries in the state of Texas. The project included a review of published literature on current and proposed : countermeasures for reducing the...

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.

Enhancing the Safety Climate and Reducing Violence Against Staff in Closed Hospital Wards.

Science.gov (United States)

Isaak, Valerie; Vashdi, Dana; Bar-Noy, Dor; Kostisky, Hava; Hirschmann, Shmuel; Grinshpoon, Alexander

2017-09-01

This study examined the effectiveness of an intervention program to enhance unit safety climate and minimize employee risk of injury from patient violence. The intervention program, including a 3-day workshop, was offered to personnel on maximum security units of an Israeli psychiatric hospital. Safety climate was examined before and after the implementation of the intervention, and incidents of patient violence were investigated. Six months after the intervention, a significant improvement in employees' perceptions of management's commitment to safety as well as a marginally significant improvement in communication about safety issues were found. This study demonstrated that an intervention program to enhance safety climate was associated with a decrease in the number of aggressive incidents. The researchers concluded that this intervention program is likely to return a sense of safety to workers and reduce workplace violence.

Directly acting spring loaded safety valves as shock reducing measure

International Nuclear Information System (INIS)

Ismaier, A.; Schluecker, E.

2010-01-01

Hydraulic shocks as induced by fast closure of armatures or by sudden pump failures are massive impacts in piping systems and require extensive measures to absorb the generated load. Basically the avoidance of water hammers are preferable but in case of emergency shutdowns unavoidable hydraulic shocks have to be reduced by appropriate measures. The authors describe experiments with spring loaded safety valves as shock reducing measures. It was shown that the vale dimensions is essential for the efficacy. A realistic modeling is possible using the one-dimensional fluid mechanics code ROLAST.

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.

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)

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...

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...

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

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

Efficacy and Safety of Alirocumab in Reducing Lipids and Cardiovascular Events

NARCIS (Netherlands)

Robinson, Jennifer G.; Farnier, Michel; Krempf, Michel; Bergeron, Jean; Luc, Gérald; Averna, Maurizio; Stroes, Erik S.; Langslet, Gisle; Raal, Frederick J.; El Shahawy, Mahfouz; Koren, Michael J.; Lepor, Norman E.; Lorenzato, Christelle; Pordy, Robert; Chaudhari, Umesh; Kastelein, John J. P.; Caccavo, Alberto; Codutti, Oscar; Gelersztein, Elisabeth; Vico, Marisa; Zaidman, Cesar; Majul, Claudio; Balthazar, Yohan; Capiau, Luc; Vrolix, Mathias; Vermeersch, Paul; Gotchev, Dobromir; Todorov, Georgi; Tumbev, Haralin; Tzekova, Maria; Gronkova, Naydenka; Dimov, Bojidar; Nikolaeva, Antonoaneta; Devedzhiev, Tsvetan; Mincheva, Valentina; D'Ignazio, Giuseppe; Dzongowski, Peter; Elliott, Thomas; Hart, Randy; Hoag, Gordon; Martinho, Valdemar; O'Mahony, Michael; Tellier, Guy; Pandey, Shekhar; Heaton, Kenneth; Constance, Christian; Phaneuf, Denis-Carl; Shu, Daniel; Narvaez, Nancy Cardenas; Cañon, Claudia Olivares

2015-01-01

BACKGROUND Alirocumab, a monoclonal antibody that inhibits proprotein convertase subtilisin-kexin type 9 (PCSK9), has been shown to reduce low-density lipoprotein (LDL) cholesterol levels in patients who are receiving statin therapy. Larger and longer-term studies are needed to establish safety and

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.

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)

OPERATIONAL RESTRICTIONS FOR REDUCING NOISE AND THE SAFETY OF AIR OPERATIONS

Directory of Open Access Journals (Sweden)

Anna KWASIBORSKA

2017-03-01

Full Text Available Many European airports are located in close proximity to residential or protected areas. Aircraft noise emissions caused by the landing and taking off of aircraft are a big problem in these areas. From an operational point of view, the method for reducing noise is to reduce traffic volume or change its organization, especially during the night. Some procedures and tools have been developed to support air traffic management in the implementation of operational constraints necessary to maintain noise at an acceptable level. The objective of this paper is to analyse the effectiveness of these tools. For this purpose, we have analysed existing methods of operational noise reduction, taking into account their influence on the structure, smoothness, punctuality and, especially, the safety of air traffic. As a result, existing risks have been identified, while methods have been proposed to combine two important air traffic service tasks: ensuring safety, while taking into account the environmental constraints, especially in relation to the acoustic climate.

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...

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

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...

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

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.

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.

Transportation Safety Excellence in Operations Through Improved Transportation Safety Document

International Nuclear Information System (INIS)

Dr. Michael A. Lehto; MAL

2007-01-01

A recent accomplishment of the Idaho National Laboratory (INL) Materials and Fuels Complex (MFC) Nuclear Safety analysis group was to obtain DOE-ID approval for the inter-facility transfer of greater-than-Hazard-Category-3 quantity radioactive/fissionable waste in Department of Transportation (DOT) Type A drums at MFC. This accomplishment supported excellence in operations through safety analysis by better integrating nuclear safety requirements with waste requirements in the Transportation Safety Document (TSD); reducing container and transport costs; and making facility operations more efficient. The MFC TSD governs and controls the inter-facility transfer of greater-than-Hazard-Category-3 radioactive and/or fissionable materials in non-DOT approved containers. Previously, the TSD did not include the capability to transfer payloads of greater-than-Hazard-Category-3 radioactive and/or fissionable materials using DOT Type A drums. Previous practice was to package the waste materials to less-than-Hazard-Category-3 quantities when loading DOT Type A drums for transfer out of facilities to reduce facility waste accumulations. This practice allowed operations to proceed, but resulted in drums being loaded to less than the Waste Isolation Pilot Plant (WIPP) waste acceptance criteria (WAC) waste limits, which was not cost effective or operations friendly. An improved and revised safety analysis was used to gain DOE-ID approval for adding this container configuration to the MFC TSD safety basis. In the process of obtaining approval of the revised safety basis, safety analysis practices were used effectively to directly support excellence in operations. Several factors contributed to the success of MFC's effort to obtain approval for the use of DOT Type A drums, including two practices that could help in future safety basis changes at other facilities. (1) The process of incorporating the DOT Type A drums into the TSD at MFC helped to better integrate nuclear safety

Multiyear Program Plan: Reducing Friction and Wear in Heavy Vehicles; FINAL

International Nuclear Information System (INIS)

R.R. Fessler; G.R. Fenske

1999-01-01

As described in its multiyear program plan for 1998-2000, the Office of Heavy Vehicle Technologies (OHVT) envisions the development of a fuel-flexible, energy-efficient, near-zero-emissions, heavy-duty U.S. diesel engine technology devolving into all truck classes as a real and viable strategy for reducing energy requirements for commercial transport services and the rapidly growing multipurpose vehicle market (pickups, vans, and sport utility vehicles). Implementation of the OHVT program plan will have significant national benefits in energy savings, cleaner air, more jobs, and increased gross domestic product (GDP). Successful implementation will reduce the petroleum consumption of Class 1-8 trucks by 1.4 million barrels of oil per day by 2020 and over 1.8 million by 2030, amounting to a reduction in highway petroleum consumption of 13.2% and 18.6%, respectively. All types of regulated emissions will be reduced, that is, 20% drop in PM10 emissions (41,000 metric tons per year) by 2030, 17% reduction in CO2 greenhouse gases (205 million metric tons per year), 7% reduction in NOx, 20% reduction in NMHC, and 30% reduction in CO. An increase of 15,000 jobs by 2020 is expected, as is an increase of$24 billion in GDP. The strategy of OHVT is to focus primarily on the diesel engine since it has numerous advantages. It has the highest efficiency of any engine today, 45% versus 30% for production gasoline engines; and it can be made more efficient at least to 55% and possibly up to 63%. It is the engine of choice for heavy vehicles (trucks), because it offers power, efficiency, durability, and reliability and is used extensively in rail, marine, and off-road applications. Its emission can be ultra-low to near zero, and the production infrastructure is already in place. The primary goals of OHVT are as follows: (1) Develop by 2002 the diesel-engine enabling technologies to support large-scale industry dieselization of light trucks, achieving a 35% fuel efficiency

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

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.

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

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

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...

The role of color sorting machine in reducing food safety risks

Directory of Open Access Journals (Sweden)

Eleonora Kecskes-Nagy

2016-07-01

Full Text Available It is the very difficult problem how we can decrease food safety risks in the product, which was polluted in process of cropping. According to professional literature almost the prevention is considered as an exclusive method to keep below safe level the content of DON toxin. The source of food safety in food chain is that the primary products suit the food safety requirements. It is a very difficult or sometimes it is not possible to correct food safety risk factors - which got into the products during cultivation - in the course of processing. Such factor is fusariotoxin in fodder and bread wheat. DON toxin is the most frequent toxin in cereals. The objective of the searching was to investigate, if it is possible to decrease DON toxin content of durum wheat and to minimize the food safety risk by application milling technology with good production practice and technological conditions. The samples were taken in the first phase of milling technology just before and after color sorting. According to measuring results Sortex Z+ optical sorting decreased DON toxin content of wheat. This mean that the food safety risks can be reduced by Sortex Z+ optical sorting machine. Our experiments proved if there is color sorting in the cleaning process preceding the milling of wheat then a part of the grain of wheat infected by Fusarium sp. can be selected. This improves the food safety parameters of given lot of wheat and decrease the toxin content. The flour made from contaminated grains of wheat can be a serious food safety risk. We would like to support scientifically the technical development of milling technology with our experimental data. Normal 0 21 false false false HU X-NONE X-NONE MicrosoftInternetExplorer4

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...

A new smoothing procedure to reduce delivery segments for static MLC-based IMRT planning

International Nuclear Information System (INIS)

Sun Xuepeng; Xia Ping

2004-01-01

In the application of pixel-based intensity-modulated radiation therapy (IMRT) using the step-and-shoot delivery method, one major difficulty is the prolonged delivery time. In this study, we present an integrated IMRT planning system that involves a simple smoothing method to reduce the complexity of the beam profiles. The system consists of three main steps: (a) an inverse planning process based on a least-square dose-based cost function; (b) smoothing of the intensity maps; (c) reoptimization of the segment weights. Step (a) obtains the best plan with the lowest cost value using a simulated annealing optimization algorithm with discrete intensity levels. Step (b) takes the intensity maps obtained from (a) and reduces the complexity of the maps by smoothing the adjacent beamlet intensities. During this process each beamlet is assigned a structure index based on anatomical information. A smoothing update is applied to average adjacent beamlets with the same index. To control the quality of the plan, a predefined clinical protocol is used as an acceptance criterion. The smoothing updates that violate the criterion are rejected. After the smoothing process, the segment weights are reoptimized in step (c) to further improve the plan quality. Three clinical cases were studied using this system: a medulloblastoma, a prostate cancer, and an oropharyngeal carcinoma. While the final plans demonstrate a degradation of the original plan quality, they still meet the plan acceptance criterion. On the other hand, the segment numbers or delivery times are reduced by 40%, 20%, and 20% for the three cases, respectively

Health and safety plan for the removal action at the former YS-860 Firing Ranges, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-04-28

This health and safety plan sets forth the requirements and procedures to protect the personnel involved in the Lead Source Removal Project at the Former YS-86O Firing Ranges. This project will be conducted in a manner that ensures the protection of the safety and health of workers, the public, and the environment. The purpose of this removal action is to address lead contaminated soil and reduce a potential risk to human health and the environment. This site is an operable unit within the Upper East Fork Poplar Creek watershed. The removal action will contribute to early source actions within the watershed. The project will accomplish this through the removal of lead-contaminated soil in the target areas of the two small arms firing ranges. This plan covers the removal actions at the Former YS-86O Firing Ranges. These actions involve the excavation of lead-contaminated soils, the removal of the concrete trench and macadam (asphalt) paths, verification/confirmation sampling, grading and revegetation. The primary hazards include temperature extremes, equipment operation, noise, potential lead exposure, uneven and slippery working surfaces, and insects.

Health and safety plan for the removal action at the former YS-860 Firing Ranges, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1998-01-01

This health and safety plan sets forth the requirements and procedures to protect the personnel involved in the Lead Source Removal Project at the Former YS-86O Firing Ranges. This project will be conducted in a manner that ensures the protection of the safety and health of workers, the public, and the environment. The purpose of this removal action is to address lead contaminated soil and reduce a potential risk to human health and the environment. This site is an operable unit within the Upper East Fork Poplar Creek watershed. The removal action will contribute to early source actions within the watershed. The project will accomplish this through the removal of lead-contaminated soil in the target areas of the two small arms firing ranges. This plan covers the removal actions at the Former YS-86O Firing Ranges. These actions involve the excavation of lead-contaminated soils, the removal of the concrete trench and macadam (asphalt) paths, verification/confirmation sampling, grading and revegetation. The primary hazards include temperature extremes, equipment operation, noise, potential lead exposure, uneven and slippery working surfaces, and insects

The RERTR [Reduced Enrichment Research and Test Reactor] Program: Progress and plans

International Nuclear Information System (INIS)

Travelli, A.

1987-01-01

The progress of the Reduced Enrichment Research and Test Reactor (RERTR) Program is described. After a brief summary of the results which the RERTR Program, in collaboration with its many international partners, had achieved by the end of 1986, the activities, results, and new developments which occurred in 1987 are reviewed. Irradiation of the second miniplate series, concentrating on U 3 Si 2 -Al and U 3 Si-Al fuels, was completed and postirradiation examinations were performed on many of its miniplates. The whole-core ORR demonstration with U 3 Si 2 -Al fuel at 4.8 g U/cm 3 was completed at the end of March with excellent results and with 29 elements estimated to have reached at least 40% average burnup. Good progress was made in the area of LEU usage for the production of fission 99 Mo, and in the coordination of safety evaluations related to LEU conversions of US university reactors. Planned activities include testing and demonstrating advanced fuels intended to allow use of reduced enrichment uranium in very-high-performance reactors. Two candidate fuels are U 3 Si-Al with 19.75% enrichment and U 3 Si 2 -Al with 45% enrichment. Demonstration of these fuels will include irradiation of full-size elements and, possibly, a full-core demonstration. Achievement of the final program goals is still projected for 1990. This progress could not have been possible without the close international cooperation which has existed from the beginning, and which is essential to the ultimate success of the RERTR Program

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.

Outage time reduction in GKN II without loss of safety

International Nuclear Information System (INIS)

Sturm, J.

1999-01-01

GKN II is a 1340 MWE 4-loop pressurised water reactor from Siemens KONVOI type, located in the south of Germany. It was originally connected to the grid at the end of 1988. Commercial operation under utility responsibility started at the second half of 1989. The first outage was performed in 1990. Beginning from this date, the outage duration was contiguously reduced from 33 days to 15 days in 1996. In 1998, two refueling and maintenance outages were performed, each with a duration of 7 days. Key planning factors to achieve these results are: A well adapted planning organisation with an outage manager and an outage planning team. An effective long term planning. This means the combination of work with a long duration every 4 or 8 years. No longlasting work in the years in between. Main work only on one safety train per year. Optimisation and standardisation of the shutdown and the startup sequence. The real change of reactor states have been modified, compared to the vendor recommendations. An tests are assigned to plant conditions, where they are most effective and are less time critical. Small modifications in the plant, mainly on the auxiliary systems, to speedup some sequences. Extreme detailed planning of maintenance and periodic tests. Each work/test can be found in a detailed schedule with a dedicated time widow. Optimized tools to perform the detailed planning and to implement the feedback of experience from former outages. Optimized tools for maintenance and handlings of heavy equipment on the critical path. Optimized tools to perform periodic tests. Key factors during outage are: Permanent control of the schedules with an updated 3-day program. Best and permanent information with this 3-day program of all people that are involved. Fast reaction on delays. Outage managers permanent on site. Gain in safety during shutdown states, with reduced outage duration: It has to be proven, that short outages don't lead to faster and less accurate work. It can be

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)

Variable Speed Limits: Strategies to Improve Safety and Traffic Parameters for a Bottleneck

Directory of Open Access Journals (Sweden)

M. Z. Hasanpour

2017-04-01

Full Text Available The primary purpose of the speed limit system is to enforce reasonable and safe speed. To reduce secondary problems such as accidents and queuing, Variable Speed Limits (VSL has been suggested. In this paper VSL is used to better safety and traffic parameters. Traffic parameters including speed, queue length and stopping time have been pondering. For VLS, an optimization decision tree algorithm with the function of microscopic simulation was used. The results in case of sub saturated, saturated and supersaturated at a bottleneck are examined and compared with the Allaby logic tree. The results show that the proposed decision tree shows an improved performance in terms of safety and comfort along the highway. The VSL pilot project is part of the Road Safety Improvement Program included in Iran’s road safety action plan that is in the research process in the BHRC Research Institute, Road and Housing & Urban Development Research that is planned for next 10-year Transportation safety view Plan.

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.

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)

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

Health and safety plan for the removal action at the former YS-860 Firing Ranges, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-03-24

This health and safety plan sets forth the requirements and procedures to protect the personnel involved in the removal action project at the former YS-860 Firing Ranges. This project will be conducted in a manner that ensures the protection of the safety and health of workers, the public, and the environment. The purpose of this removal action is to address lead-contaminated soil and reduce a potential risk to human health and the environment. This site is an operable unit within the Upper East Fork Poplar Creek watershed. The removal action will contribute to early source actions within the watershed. The project will accomplish this through the removal of lead-contaminated soil in the target areas of the two small arms firing ranges. The primary hazards include temperature extremes, equipment operation, noise, potential lead exposure, uneven and slippery working surfaces, and insects.

Health and safety plan for the removal action at the former YS-860 Firing Ranges, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1998-01-01

This health and safety plan sets forth the requirements and procedures to protect the personnel involved in the removal action project at the former YS-860 Firing Ranges. This project will be conducted in a manner that ensures the protection of the safety and health of workers, the public, and the environment. The purpose of this removal action is to address lead-contaminated soil and reduce a potential risk to human health and the environment. This site is an operable unit within the Upper East Fork Poplar Creek watershed. The removal action will contribute to early source actions within the watershed. The project will accomplish this through the removal of lead-contaminated soil in the target areas of the two small arms firing ranges. The primary hazards include temperature extremes, equipment operation, noise, potential lead exposure, uneven and slippery working surfaces, and insects

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

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...

Reducing dose calculation time for accurate iterative IMRT planning

International Nuclear Information System (INIS)

Siebers, Jeffrey V.; Lauterbach, Marc; Tong, Shidong; Wu Qiuwen; Mohan, Radhe

2002-01-01

A time-consuming component of IMRT optimization is the dose computation required in each iteration for the evaluation of the objective function. Accurate superposition/convolution (SC) and Monte Carlo (MC) dose calculations are currently considered too time-consuming for iterative IMRT dose calculation. Thus, fast, but less accurate algorithms such as pencil beam (PB) algorithms are typically used in most current IMRT systems. This paper describes two hybrid methods that utilize the speed of fast PB algorithms yet achieve the accuracy of optimizing based upon SC algorithms via the application of dose correction matrices. In one method, the ratio method, an infrequently computed voxel-by-voxel dose ratio matrix (R=D SC /D PB ) is applied for each beam to the dose distributions calculated with the PB method during the optimization. That is, D PB xR is used for the dose calculation during the optimization. The optimization proceeds until both the IMRT beam intensities and the dose correction ratio matrix converge. In the second method, the correction method, a periodically computed voxel-by-voxel correction matrix for each beam, defined to be the difference between the SC and PB dose computations, is used to correct PB dose distributions. To validate the methods, IMRT treatment plans developed with the hybrid methods are compared with those obtained when the SC algorithm is used for all optimization iterations and with those obtained when PB-based optimization is followed by SC-based optimization. In the 12 patient cases studied, no clinically significant differences exist in the final treatment plans developed with each of the dose computation methodologies. However, the number of time-consuming SC iterations is reduced from 6-32 for pure SC optimization to four or less for the ratio matrix method and five or less for the correction method. Because the PB algorithm is faster at computing dose, this reduces the inverse planning optimization time for our implementation

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.

Governance of Land Use Planning to Reduce Fire Risk to Homes Mediterranean France and California

Directory of Open Access Journals (Sweden)

Susan D. Kocher

2017-03-01

Full Text Available Wildfire is a natural part of forested Mediterranean systems. As humans continue to live and build housing in these areas, wildfire is a constant threat to homes and lives. The goal of this paper is to describe aspects of land-use planning that are used to reduce wildfire risk in institutionally divergent regions; southern France and California. By reviewing relevant legislation and planning documents and conducting in person interviews with fire and planning professionals, we identify the institutions which participate in land use planning to reduce fire risk and the key laws and regulations that guide planning decisions. Our results indicate that France has a more centralized system for planning for fire, with national level entities heavily involved in local land use planning. California, on the other hand sees almost no federal oversite, and, while state law requires local plans to include wildfire risk, most fine grain decisions are left to local planners and decision makers. In both regions, however, we see a reliance on technical support provided from outside local jurisdictions. Increased coordination between local, regional, and national governments could improve land use planning in both locations.

Food safety of cereals: a chain wide approach to reduce Fusarium mycotoxins

NARCIS (Netherlands)

Scholten, O.E.; Ruckenbauer, P.; Visconti, A.; Osenburggen, W.A.; Nijs, den A.P.M.

2002-01-01

Fusarium head blight (FHB) in wheat and barley and Fusarium ear rot in maize is caused by several Fusarium species. The disease reduces the quality of the seed since several of these fungi produce mycotoxins. From a food safety point of view, consumption of mycotoxin-infected cereals is dangerous as

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

Research and development on reduced-moderation light water reactor with passive safety features (Contract research)

International Nuclear Information System (INIS)

Iwamura, Takamichi; Okubo, Tsutomu; Akie, Hiroshi; Kugo, Teruhiko; Yonomoto, Taisuke; Kureta, Masatoshi; Ishikawa, Nobuyuki; Nagaya, Yasunobu; Araya, Fumimasa; Okajima, Shigeaki; Okumura, Keisuke; Suzuki, Motoe; Mineo, Hideaki; Nakatsuka, Toru

2004-06-01

The present report contains the achievement of 'Research and Development on Reduced-moderation Light Water Reactor with Passive Safety Features', which was performed by Japan Atomic Energy Research Institute (JAERI), Hitachi Ltd., Japan Atomic Power Company and Tokyo Institute of Technology in FY2000-2002 as the innovative and viable nuclear energy technology (IVNET) development project operated by the Institute of Applied Energy (IAE). In the present project, the reduced-moderation water reactor (RMWR) has been developed to ensure sustainable energy supply and to solve the recent problems of nuclear power and nuclear fuel cycle, such as economical competitiveness, effective use of plutonium and reduction of spent fuel storage. The RMWR can attain the favorable characteristics such as high burnup, long operation cycle, multiple recycling of plutonium (Pu) and effective utilization of uranium resources based on accumulated LWR technologies. Our development target is 'Reduced-moderation Light Water Reactor with Passive Safety Features' with innovative technologies to achieve above mentioned requirement. Electric power is selected as 300 MWe considering anticipated size required for future deployment. The reactor core consists of MOX fuel assemblies with tight lattice arrangement to increase the conversion ratio. Design targets of the core specification are conversion ratio more than unity, negative void reactivity feedback coefficient to assure safety, discharged burnup more than 60 GWd/t and operation cycle more than 2 years. As for the reactor system, a small size natural circulation BWR with passive safety systems is adopted to increase safety and reduce construction cost. The results obtained are as follows: As regards core design study, core design was performed to meet the goal. Sequence of startup operation was constructed for the RMWR. As the plant design, plant system was designed to achieve enhanced economy using passive safety system effectively. In

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.

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

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

DESIGN PACKAGE 1E SYSTEM SAFETY ANALYSIS

Energy Technology Data Exchange (ETDEWEB)

M. Salem

1995-06-23

The purpose of this analysis is to systematically identify and evaluate hazards related to the Yucca Mountain Project Exploratory Studies Facility (ESF) Design Package 1E, Surface Facilities, (for a list of design items included in the package 1E system safety analysis see section 3). This process is an integral part of the systems engineering process; whereby safety is considered during planning, design, testing, and construction. A largely qualitative approach was used since a radiological System Safety Analysis is not required. The risk assessment in this analysis characterizes the accident scenarios associated with the Design Package 1E structures/systems/components(S/S/Cs) in terms of relative risk and includes recommendations for mitigating all identified risks. The priority for recommending and implementing mitigation control features is: (1) Incorporate measures to reduce risks and hazards into the structure/system/component design, (2) add safety devices and capabilities to the designs that reduce risk, (3) provide devices that detect and warn personnel of hazardous conditions, and (4) develop procedures and conduct training to increase worker awareness of potential hazards, on methods to reduce exposure to hazards, and on the actions required to avoid accidents or correct hazardous conditions.

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

Public safety for BC Hydro's dams and powerhouse

Energy Technology Data Exchange (ETDEWEB)

Cattanach, D. [BC Hydro, Burnaby, BC (Canada). Emergency Preparedness Security and Public Safety

2009-07-01

This presentation reviewed public safety and historical practices at British Columbia (BC) Hydro. Historically, visitors were guided to safe locations at their facilities by visitor centres and public use management areas. Fences and booms were used to protect visitors from the more dangerous areas around the facility. This presentation also described the features of the safety management plans that BC Hydro has in place for each of its 41 facilities. The safety management plans are approved by the plant managers; they have common controls such as fences and signs; and there are excellent maps defining the danger areas. New risks that were identified were also presented. The next steps for BC Hydro include test driving the draft Canadian Dam Association guidelines for the Aberfeldie Dam; a new powerhouse to reduce overtopping of the dam during the spring; and continuing with public safety hazards and controls such as bow-ties. figs.

Identification of Behavior Based Safety by Using Traffic Light Analysis to Reduce Accidents

Science.gov (United States)

Mansur, A.; Nasution, M. I.

2016-01-01

This work present the safety assessment of a case study and describes an important area within the field production in oil and gas industry, namely behavior based safety (BBS). The company set a rigorous BBS and its intervention program that implemented and deployed continually. In this case, observers requested to have discussion and spread a number of determined questions related with work behavior to the workers during observation. Appraisal of Traffic Light Analysis (TLA) as one tools of risk assessment used to determine the estimated score of BBS questionnaire. Standardization of TLA appraisal in this study are based on Regulation of Minister of Labor and Occupational Safety and Health No:PER.05/MEN/1996. The result shown that there are some points under 84%, which categorized in yellow category and should corrected immediately by company to prevent existing bad behavior of workers. The application of BBS expected to increase the safety performance at work time-by-time and effective in reducing accidents.

Preliminary safety evaluation for 241-C-106 waste retrieval, project W-320

International Nuclear Information System (INIS)

Conner, J.C.

1994-01-01

This document presents the Preliminary Safety Evaluation for Project W-320, Tank 241-C-106 Waste Retrieval Sluicing System (WRSS). The US DOE has been mandated to develop plans for response to safety issues associated with the waste storage tanks at the Hanford Site, and to report the progress of implementing those plans to Congress. The objectives of Project W-230 are to design, fabricate, develop, test, and operate a new retrieval system capable of removing a minimum of about 75% of the high-heat waste contained in C-106. It is anticipated that sluicing operations can remove enough waste to reduce the remaining radiogenic heat load to levels low enough to resolve the high-heat safety issue as well as allow closure of the tank safety issue

Advances in safety related maintenance

International Nuclear Information System (INIS)

2000-03-01

The maintenance of systems, structures and components in nuclear power plants (NPPs) plays an important role in assuring their safe and reliable operation. Worldwide, NPP maintenance managers are seeking to reduce overall maintenance costs while maintaining or improving the levels of safety and reliability. Thus, the issue of NPP maintenance is one of the most challenging aspects of nuclear power generation. There is a direct relation between safety and maintenance. While maintenance alone (apart from modifications) will not make a plant safer than its original design, deficient maintenance may result in either an increased number of transients and challenges to safety systems or reduced reliability and availability of safety systems. The confidence that NPP structures, systems and components will function as designed is ultimately based on programmes which monitor both their reliability and availability to perform their intended safety function. Because of this, approaches to monitor the effectiveness of maintenance are also necessary. An effective maintenance programme ensures that there is a balance between the improvement in component reliability to be achieved and the loss of component function due to maintenance downtime. This implies that the safety level of an NPP should not be adversely affected by maintenance performed during operation. The nuclear industry widely acknowledges the importance of maintenance in NPP safety and operation and therefore devotes great efforts to develop techniques, methods and tools to aid in maintenance planning, follow-up and optimization, and in assuring the effectiveness of maintenance

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.

Potential effects of organizational uncertainty on safety

Energy Technology Data Exchange (ETDEWEB)

Durbin, N.E. [MPD Consulting Group, Kirkland, WA (United States); Lekberg, A. [Swedish Nuclear Power Inspectorate, Stockholm (Sweden); Melber, B.D. [Melber Consulting, Seattle WA (United States)

2001-12-01

When organizations face significant change - reorganization, mergers, acquisitions, down sizing, plant closures or decommissioning - both the organizations and the workers in those organizations experience significant uncertainty about the future. This uncertainty affects the organization and the people working in the organization - adversely affecting morale, reducing concentration on safe operations, and resulting in the loss of key staff. Hence, organizations, particularly those using high risk technologies, which are facing significant change need to consider and plan for the effects of organizational uncertainty on safety - as well as planning for other consequences of change - technical, economic, emotional, and productivity related. This paper reviews some of what is known about the effects of uncertainty on organizations and individuals, discusses the potential consequences of uncertainty on organizational and individual behavior, and presents some of the implications for safety professionals.

Potential effects of organizational uncertainty on safety

International Nuclear Information System (INIS)

Durbin, N.E.; Lekberg, A.; Melber, B.D.

2001-12-01

When organizations face significant change - reorganization, mergers, acquisitions, down sizing, plant closures or decommissioning - both the organizations and the workers in those organizations experience significant uncertainty about the future. This uncertainty affects the organization and the people working in the organization - adversely affecting morale, reducing concentration on safe operations, and resulting in the loss of key staff. Hence, organizations, particularly those using high risk technologies, which are facing significant change need to consider and plan for the effects of organizational uncertainty on safety - as well as planning for other consequences of change - technical, economic, emotional, and productivity related. This paper reviews some of what is known about the effects of uncertainty on organizations and individuals, discusses the potential consequences of uncertainty on organizational and individual behavior, and presents some of the implications for safety professionals

A Study of the Traffic Safety at Reduced Conflict Intersections In Minnesota

Science.gov (United States)

2017-05-23

In 2010, the Minnesota Department of Transportation installed the first Reduced Conflict Intersection (RCI) in the City of Willmar. Since 2010, seven more were constructed, with more planned. The RCI concept is gaining popularity in several states, i...

Reducing the risk, managing safety.

Science.gov (United States)

Aldridge, Peter

2016-02-01

Fire safety in healthcare premises has always been a challenge to those that discharge this duty. Statutory compliance should be a matter of course, but in an ever increasingly challenged NHS, even this is not a given. While the NHS is driven by managing very complex risk to deliver cutting edge healthcare, providers cannot be risk averse. Which risk, however, takes priority? Here Peter Aldridge, fire and corporate services manager at Leeds Teaching Hospitals NHS Trust, and Secretary to the National Association of Healthcare Fire Officers (NAHFO)--which will this month and next jointly stage fire safety seminars with IHEEM; see page 8--considers the key issues, with input from a fire officer at a leading mental health and community Trust.

Graded Approach to the Development of a Contingency Plan for On-Line Maintenance

International Nuclear Information System (INIS)

Chang, Hee Seung; Kim, Jung Wun; Song, Tae Young

2012-01-01

Many utilities perform preventive maintenance for safety systems during power operation to improve equipment reliability so as to focus on the work activities more easily and improve the quality of maintenance. Such a strategy can also reduce outage work activities, thus allowing resources to be utilized effectively. Preventive maintenance during power operation, known as on-line maintenance (OLM), requires an assessment and mitigation of risk, which can increase owing to out-of-service safety systems. One of the mitigation action plans is a contingency plan. EPRI recommends the development of a contingency plan for all planned system outages which include factors that strongly affect safety. The Korea Hydro and Nuclear Power Company (KHNP) undertook the preventive maintenance of the Essential Chilled Water System (ECWS) of a Westinghouse plant as a pilot OLM implementation. During the preparation of the work activities, a contingency plan was a pertinent issue during the discussions with regulators, especially regarding the scope and depth of the plan. This paper discusses the purpose of a contingency plan, including as examples some cases of US utilities, and proposes a graded approach to develop a contingency plan for OLM in consideration of the risks

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.

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

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

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

Exploiting Science: Enhancing the Safety Training of Pilots to Reduce the Risk of Bird Strikes

Science.gov (United States)

Mendonca, Flavio A. C.

Analysis of bird strikes to aviation in the U.S. from 1990 to 2015 indicate that the successful mitigation efforts at airports, which must be sustained, have reduced incidents with damage and a negative effect-on-flight since 2000. However, such efforts have done little to reduce strikes outside the airport jurisdiction, such as occurred with US Airways Flight 1549 in 2009. There are basically three strategies to mitigate the risk of bird strikes: standards set by aviation authorities, technology, and actions by crewmembers. Pilots play an important role as stakeholders in the prevention of bird strikes, especially outside the airport environment. Thus, safety efforts require enhanced risk management and aeronautical decision-making training for flight crews. The purpose of this study was to determine if a safety training protocol could effectively enhance CFR Part 141 general aviation pilots' knowledge and skills to reduce the risk of bird strikes to aviation. Participants were recruited from the Purdue University professional flight program and from Purdue Aviation. The researcher of this study used a pretest posttest experimental design. Additionally, qualitative data were collected through open-ended questions in the pretest, posttest, and a follow-up survey questionnaire. The participants' pretest and posttest scores were analyzed using parametric and nonparametric tests. Results indicated a significant increase in the posttest scores of the experimental group. An investigation of qualitative data showed that the topic "safety management of bird hazards by pilots" is barely covered during the ground and flight training of pilots. Furthermore, qualitative data suggest a misperception of the safety culture tenets and a poor familiarity with the safety risk management process regarding bird hazards. Finally, the researcher presented recommendations for practice and future research.

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

Strategies to reduce safety violations for working from heights in construction companies: study protocol for a randomized controlled trial

NARCIS (Netherlands)

van der Molen, Henk F.; Frings-Dresen, Monique H. W.

2014-01-01

Safety measures should be applied to reduce work-related fatal and non-fatal fall injuries. However, according to the labor inspectorate, more than 80% of Dutch construction sites violate safety regulations for working from heights. To increase compliance with safety regulations, employers and

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

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

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.

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.

Safety culture improvements in a nuclear laboratory setting

International Nuclear Information System (INIS)

Smith, K.L.; McKenna, J.

2014-01-01

In 2008, AECL performed a comprehensive safety culture assessment using recognized, industry-proven methodologies. Main observations were grouped into several key areas including standards, procedures, error-free work, and leadership fundamentals. Shortly thereafter, in 2009 May, the National Research Universal (NRU) reactor was shut down following discovery of a small leak of heavy water. Extensive repairs were required to return the reactor to service and a root cause investigation was conducted to determine the organizational and programmatic causes that led to the event. Taken together, these presented management with insights into common areas of weaknesses in performance and behaviours. A Corrective Action Plan (CAP) to address both the findings of the root cause analysis and safety culture assessment was captured in a comprehensive improvement plan issued in 2010 March, entitled the Voyageur Program Phase II (Voyageur II). The CAP addresses six key areas: Improve equipment reliability; Drive desired behaviours; Improve problem identification and resolution; Improve use of industry Operating Experience (OPEX) and reduce isolationism; Improve standards of operation; and, Improve management oversight. AECL's safety culture has been monitored regularly using quarterly surveys. A detailed safety culture assessment was executed in 2012 September. Compared with previous results, improvements for AECL were noted in the following areas: Use of Operating Experience, specifically in work planning, pre job briefs and training; Procedure quality; Availability of safety equipment; Control of temporary changes; and, Improved operational standards. (author)

Safety culture improvements in a nuclear laboratory setting

Energy Technology Data Exchange (ETDEWEB)

Smith, K.L.; McKenna, J. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

2014-07-01

In 2008, AECL performed a comprehensive safety culture assessment using recognized, industry-proven methodologies. Main observations were grouped into several key areas including standards, procedures, error-free work, and leadership fundamentals. Shortly thereafter, in 2009 May, the National Research Universal (NRU) reactor was shut down following discovery of a small leak of heavy water. Extensive repairs were required to return the reactor to service and a root cause investigation was conducted to determine the organizational and programmatic causes that led to the event. Taken together, these presented management with insights into common areas of weaknesses in performance and behaviours. A Corrective Action Plan (CAP) to address both the findings of the root cause analysis and safety culture assessment was captured in a comprehensive improvement plan issued in 2010 March, entitled the Voyageur Program Phase II (Voyageur II). The CAP addresses six key areas: Improve equipment reliability; Drive desired behaviours; Improve problem identification and resolution; Improve use of industry Operating Experience (OPEX) and reduce isolationism; Improve standards of operation; and, Improve management oversight. AECL's safety culture has been monitored regularly using quarterly surveys. A detailed safety culture assessment was executed in 2012 September. Compared with previous results, improvements for AECL were noted in the following areas: Use of Operating Experience, specifically in work planning, pre job briefs and training; Procedure quality; Availability of safety equipment; Control of temporary changes; and, Improved operational standards. (author)

Light Water Reactor Sustainability Program: Risk-Informed Safety Margins Characterization (RISMC) Pathway Technical Program Plan

International Nuclear Information System (INIS)

Smith, Curtis; Rabiti, Cristian; Martineau, Richard; Szilard, Ronaldo

2016-01-01

Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). As the current Light Water Reactor (LWR) NPPs age beyond 60 years, there are possibilities for increased frequency of Systems, Structures, and Components (SSCs) degradations or failures that initiate safety-significant events, reduce existing accident mitigation capabilities, or create new failure modes. Plant designers commonly ''over-design'' portions of NPPs and provide robustness in the form of redundant and diverse engineered safety features to ensure that, even in the case of well-beyond design basis scenarios, public health and safety will be protected with a very high degree of assurance. This form of defense-in-depth is a reasoned response to uncertainties and is often referred to generically as ''safety margin.'' Historically, specific safety margin provisions have been formulated, primarily based on ''engineering judgment.''

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.

Efficacy of virtual block objects in reducing the lung dose in helical tomotherapy planning for cervical oesophageal cancer: a planning study.

Science.gov (United States)

Ito, Makoto; Shimizu, Hidetoshi; Aoyama, Takahiro; Tachibana, Hiroyuki; Tomita, Natsuo; Makita, Chiyoko; Koide, Yutaro; Kato, Daiki; Ishiguchi, Tsuneo; Kodaira, Takeshi

2018-04-04

Intensity-modulated radiotherapy is useful for cervical oesophageal carcinoma (CEC); however, increasing low-dose exposure to the lung may lead to radiation pneumonitis. Nevertheless, an irradiation technique that avoids the lungs has never been examined due to the high difficulty of dose optimization. In this study, we examined the efficacy of helical tomotherapy that can restrict beamlets passing virtual blocks during dose optimization computing (block plan) in reducing the lung dose. Fifteen patients with CEC were analysed. The primary/nodal lesion and prophylactic nodal region with adequate margins were defined as the planning target volume (PTV)-60 Gy and PTV-48 Gy, respectively. Nineteen plans per patient were made and compared (total: 285 plans), including non-block and block plans with several shapes and sizes. The most appropriate block model was semi-circular, 8 cm outside of the tracheal bifurcation, with a significantly lower lung dose compared to that of non-block plans; the mean lung volumes receiving 5 Gy, 10 Gy, 20 Gy, and the mean lung dose were 31.3% vs. 48.0% (p block and non-block plans were comparable in terms of the homogeneity and conformity indexes of PTV-60 Gy: 0.05 vs. 0.04 (p = 0.100) and 0.82 vs. 0.85 (p = 0.616), respectively. The maximum dose of the spinal cord planning risk volume increased slightly (49.4 Gy vs. 47.9 Gy, p = 0.002). There was no significant difference in the mean doses to the heart and the thyroid gland. Prolongation of the delivery time was less than 1 min (5.6 min vs. 4.9 min, p = 0.010). The block plan for CEC could significantly reduce the lung dose, with acceptable increment in the spinal dose and a slightly prolonged delivery time.

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.

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

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)

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

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…

A Risk Assessment Model for Reduced Aircraft Separation: A Quantitative Method to Evaluate the Safety of Free Flight

Science.gov (United States)

Cassell, Rick; Smith, Alex; Connors, Mary; Wojciech, Jack; Rosekind, Mark R. (Technical Monitor)

1996-01-01

As new technologies and procedures are introduced into the National Airspace System, whether they are intended to improve efficiency, capacity, or safety level, the quantification of potential changes in safety levels is of vital concern. Applications of technology can improve safety levels and allow the reduction of separation standards. An excellent example is the Precision Runway Monitor (PRM). By taking advantage of the surveillance and display advances of PRM, airports can run instrument parallel approaches to runways separated by 3400 feet with the same level of safety as parallel approaches to runways separated by 4300 feet using the standard technology. Despite a wealth of information from flight operations and testing programs, there is no readily quantifiable relationship between numerical safety levels and the separation standards that apply to aircraft on final approach. This paper presents a modeling approach to quantify the risk associated with reducing separation on final approach. Reducing aircraft separation, both laterally and longitudinally, has been the goal of several aviation R&D programs over the past several years. Many of these programs have focused on technological solutions to improve navigation accuracy, surveillance accuracy, aircraft situational awareness, controller situational awareness, and other technical and operational factors that are vital to maintaining flight safety. The risk assessment model relates different types of potential aircraft accidents and incidents and their contribution to overall accident risk. The framework links accident risks to a hierarchy of failsafe mechanisms characterized by procedures and interventions. The model will be used to assess the overall level of safety associated with reducing separation standards and the introduction of new technology and procedures, as envisaged under the Free Flight concept. The model framework can be applied to various aircraft scenarios, including parallel and in

Light Water Reactor Sustainability Program Risk-Informed Safety Margins Characterization (RISMC) PathwayTechnical Program Plan

Energy Technology Data Exchange (ETDEWEB)

Curtis Smith; Cristian Rabiti; Richard Martineau

2012-11-01

Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). As the current Light Water Reactor (LWR) NPPs age beyond 60 years, there are possibilities for increased frequency of Systems, Structures, and Components (SSCs) degradations or failures that initiate safety-significant events, reduce existing accident mitigation capabilities, or create new failure modes. Plant designers commonly “over-design” portions of NPPs and provide robustness in the form of redundant and diverse engineered safety features to ensure that, even in the case of well-beyond design basis scenarios, public health and safety will be protected with a very high degree of assurance. This form of defense-in-depth is a reasoned response to uncertainties and is often referred to generically as “safety margin.” Historically, specific safety margin provisions have been formulated, primarily based on “engineering judgment.”

Light Water Reactor Sustainability Program: Risk-Informed Safety Margins Characterization (RISMC) Pathway Technical Program Plan

Energy Technology Data Exchange (ETDEWEB)

Smith, Curtis [Idaho National Lab. (INL), Idaho Falls, ID (United States); Rabiti, Cristian [Idaho National Lab. (INL), Idaho Falls, ID (United States); Martineau, Richard [Idaho National Lab. (INL), Idaho Falls, ID (United States); Szilard, Ronaldo [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2016-09-01

Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). As the current Light Water Reactor (LWR) NPPs age beyond 60 years, there are possibilities for increased frequency of Systems, Structures, and Components (SSCs) degradations or failures that initiate safety-significant events, reduce existing accident mitigation capabilities, or create new failure modes. Plant designers commonly “over-design” portions of NPPs and provide robustness in the form of redundant and diverse engineered safety features to ensure that, even in the case of well-beyond design basis scenarios, public health and safety will be protected with a very high degree of assurance. This form of defense-in-depth is a reasoned response to uncertainties and is often referred to generically as “safety margin.” Historically, specific safety margin provisions have been formulated, primarily based on “engineering judgment.”

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

Speech Recognition Interfaces Improve Flight Safety

Science.gov (United States)

2013-01-01

"Alpha, Golf, November, Echo, Zulu." "Sierra, Alpha, Golf, Echo, Sierra." "Lima, Hotel, Yankee." It looks like some strange word game, but the combinations of words above actually communicate the first three points of a flight plan from Albany, New York to Florence, South Carolina. Spoken by air traffic controllers and pilots, the aviation industry s standard International Civil Aviation Organization phonetic alphabet uses words to represent letters. The first letter of each word in the series is combined to spell waypoints, or reference points, used in flight navigation. The first waypoint above is AGNEZ (alpha for A, golf for G, etc.). The second is SAGES, and the third is LHY. For pilots of general aviation aircraft, the traditional method of entering the letters of each waypoint into a GPS device is a time-consuming process. For each of the 16 waypoints required for the complete flight plan from Albany to Florence, the pilot uses a knob to scroll through each letter of the alphabet. It takes approximately 5 minutes of the pilot s focused attention to complete this particular plan. Entering such a long flight plan into a GPS can pose a safety hazard because it can take the pilot s attention from other critical tasks like scanning gauges or avoiding other aircraft. For more than five decades, NASA has supported research and development in aviation safety, including through its Vehicle Systems Safety Technology (VSST) program, which works to advance safer and more capable flight decks (cockpits) in aircraft. Randy Bailey, a lead aerospace engineer in the VSST program at Langley Research Center, says the technology in cockpits is directly related to flight safety. For example, "GPS navigation systems are wonderful as far as improving a pilot s ability to navigate, but if you can find ways to reduce the draw of the pilot s attention into the cockpit while using the GPS, it could potentially improve safety," he says.

Addendum to the health and safety plan for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program

International Nuclear Information System (INIS)

Clark, C. Jr.; Burman, S.N.; Wilson, K.A.

1995-08-01

There are three purposes for this addendum to the health and safety plan for Waste Area Grouping 6. The first purpose is to provide record of a corrective action response concerning an occurrence on WAG 6 in October 1994 (ORO-MMES-ENVRES-1994-0016.) This occurrence involved a precautionary evacuation of subcontractor field crews due to malfunctioning monitor alarms for organic vapors. The corrective action is to revise the WAG 6 Site health and safety plan to improve communications during emergency events. The second purpose is to incorporate any outstanding health and safety issues not addressed in the original health and safety plan for WAG 6 document (ORNL/ER-183). The only variance of note is tritium air monitoring in the Tumulus building. The tritium air monitor is added in this addendum as monitoring equipment for WAG 6 with description of action level and calibration. The third purpose of this addendum is to satisfy a condition of approval for the pending Nuclear Criticality Safety Assessment (NCSA) pertaining to KEMA fuel storage at WAG 6. This approval condition requires the following: ''The location of the KEMA burial shall be recorded and maintained in a controlled document that identifies the quantity and the general physical conditions at the time of the entombment with an admonishment to obtain nuclear criticality safety guidance before altering the burial condition.'' In order to satisfy the approval, this document must be controlled. The predecessor to the pending NCSA is NSR No. 0002WM22001

Factors in Decisions to Make, Purchase, and Use On-board Safety Technologies

Science.gov (United States)

2005-12-01

In support of its goal to reduce large truck-related fatalities and crashes, FMCSA plans to facilitate the deployment of Intelligent Vehicle Initiative (IVI) technologies that have shown a potential to improve the safety of commercial vehicle operati...

Water Safety Plan on cruise ships: A promising tool to prevent waterborne diseases

Energy Technology Data Exchange (ETDEWEB)

Mouchtouri, Varvara A., E-mail: mouchtourib@med.uth.gr [Department of Hygiene and Epidemiology, Faculty of Medicine, University of Thessaly, Larissa (Greece); Bartlett, Christopher L.R. [University College London, Centre for Infectious Disease Epidemiology Department of Primary Care and Population Sciences Royal Free and University College Medical School, London (United Kingdom); Diskin, Arthur [Royal Caribbean Cruise Line, Miami (United States); Hadjichristodoulou, Christos [Department of Hygiene and Epidemiology, Faculty of Medicine, University of Thessaly, Larissa (Greece)

2012-07-01

Background: 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. Objectives: To develop WSP on a cruise ship and discuss challenges, perspectives and key issues to success. Methods: 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. Results: 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. Conclusions: 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. - Highlights: Black-Right-Pointing-Pointer We conducted risk assessment and developed a Water Safety Plan on a cruise ship. Black-Right-Pointing-Pointer 53 hazards and hazardous events were

Water Safety Plan on cruise ships: A promising tool to prevent waterborne diseases

International Nuclear Information System (INIS)

Mouchtouri, Varvara A.; Bartlett, Christopher L.R.; Diskin, Arthur; Hadjichristodoulou, Christos

2012-01-01

Background: 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. Objectives: To develop WSP on a cruise ship and discuss challenges, perspectives and key issues to success. Methods: 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. Results: 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. Conclusions: 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. - Highlights: ► We conducted risk assessment and developed a Water Safety Plan on a cruise ship. ► 53 hazards and hazardous events were taken into consideration for the risk assessment. �

Planning of development strategy for establishment of advanced simulation of nuclear system

International Nuclear Information System (INIS)

Chung, Bubdong; Ko, Wonil; Kwon Junhyun

2013-12-01

In this product, the long term development plan in each technical area has been prosed with the plan of coupled code system. The consolidated code system for safety analysis has been proposing for future needs. The computing hardware needed for te advanced simulation is also proposing. The best approach for future safety analysis simulation capabilities may be a dual-path program. i. e. the development programs for an integrated analysis tool and multi-scale/multi-physic analysis tools, where the former aims at reducing uncertainty and the latter at enhancing accuracy. Integrated analysis tool with risk informed safety margin quantification It requires a significant extension of the phenomenological and geometric capabilities of existing reactor safety analysis software, capable of detailed simulations that reduce the uncertainties. Multi-scale, multi-physics analysis tools. Simplifications of complex phenomenological models and dependencies have been made in current safety analyses to accommodate computer hardware limitations. With the advent of modern computer hardware, these limitations may be removed to permit greater accuracy in representation of physical behavior of materials in design basis and beyond design basis conditions, and hence more accurate assessment of the true safety margins based on first principle methodology. The proposals can be utilized to develop the advanced simulation project and formulation of organization and establishment of high performance computing system in KAERI

Westinghouse Hanford Company safety analysis reports and technical safety requirements upgrade program

International Nuclear Information System (INIS)

Busche, D.M.

1995-09-01

During Fiscal Year 1992, the US Department of Energy, Richland Operations Office (RL) separately transmitted the following US Department of Energy (DOE) Orders to Westinghouse Hanford Company (WHC) for compliance: DOE 5480.21, ''Unreviewed Safety Questions,'' DOE 5480.22, ''Technical Safety Requirements,'' and DOE 5480.23, ''Nuclear Safety Analysis Reports.'' WHC has proceeded with its impact assessment and implementation process for the Orders. The Orders are closely-related and contain some requirements that are either identical, similar, or logically-related. Consequently, WHC has developed a strategy calling for an integrated implementation of the three Orders. The strategy is comprised of three primary objectives, namely: Obtain DOE approval of a single list of DOE-owned and WHC-managed Nuclear Facilities, Establish and/or upgrade the ''Safety Basis'' for each Nuclear Facility, and Establish a functional Unreviewed Safety Question (USQ) process to govern the management and preservation of the Safety Basis for each Nuclear Facility. WHC has developed policy-revision and facility-specific implementation plans to accomplish near-term tasks associated with the above strategic objectives. This plan, which as originally submitted in August 1993 and approved, provided an interpretation of the new DOE Nuclear Facility definition and an initial list of WHC-managed Nuclear Facilities. For each current existing Nuclear Facility, existing Safety Basis documents are identified and the plan/status is provided for the ISB. Plans for upgrading SARs and developing TSRs will be provided after issuance of the corresponding Rules

Interactive software automates personalized radiation safety plans for Na131I therapy.

Science.gov (United States)

Friedman, Marvin I; Ghesani, Munir

2002-11-01

NRC regulations have liberalized the criteria for release from control of patients administered radioactive materials but require written radiation safety instruction if another individual is expected to receive more than 1 mSv. This necessitates calculation of expected doses, even when the calculated maximum likely dose is well below the 5 mSv release criterion. NRC interpretations of the regulation provide the biokinetic model to be used to evaluate the release criterion for patients administered Na131I, but do not provide guidance as to either the specifics of minimizing the dose of others or the length of time restrictions should remain in effect. Interactive software has been developed to facilitate creation of radiation safety plans tailored to patients' expected interactions. Day-by-day and cumulative effective exposures at several separation distances, including sleeping, are presented in grid format in a graphic interface. In an interview session, the patient proposes daily contacts, which are entered separately for each individual by point-and-click operation. Total dose estimates are accumulated and modified while negotiating contact schedules, guided by suggested age-specific limits. The software produces printed radiation safety recommendations specific to the clinical, dosing, and social situations and reflective of the patient's choice of combinations of close contact with others. It has been used in treating more than 100 patients and has been found to be very useful and well received.

Standard review plan for reviewing safety analysis reports for dry metallic spent fuel storage casks

International Nuclear Information System (INIS)

1988-01-01

The Cask Standard Review Plan (CSRP) has been prepared as guidance to be used in the review of Cask Safety Analysis Reports (CSARs) for storage packages. The principal purpose of the CSRP is to assure the quality and uniformity of storage cask reviews and to present a well-defined base from which to evaluate proposed changes in the scope and requirements of reviews. The CSRP also sets forth solutions and approaches determined to be acceptable in the past by the NRC staff in dealing with a specific safety issue or safety-related design area. These solutions and approaches are presented in this form so that reviewers can take consistent and well-understood positions as the same safety issues arise in future cases. An applicant submitting a CSAR does not have to follow the solutions or approaches presented in the CSRP. However, applicants should recognize that the NRC staff has spent substantial time and effort in reviewing and developing their positions for the issues. A corresponding amount of time and effort will probably be required to review and accept new or different solutions and approaches

Safety of mechanical devices. Safety of automation systems

International Nuclear Information System (INIS)

Pahl, G.; Schweizer, G.; Kapp, K.

1985-01-01

The paper deals with the classic procedures of safety engineering in the sectors mechanical engineering, electrical and energy engineering, construction and transport, medicine technology and process technology. Particular stress is laid on the safety of automation systems, control technology, protection of mechanical devices, reactor safety, mechanical constructions, transport systems, railway signalling devices, road traffic and protection at work in chemical plans. (DG) [de

Intersection planning in Safer Transportation Network Planning : safety principles, planning framework, and library information.

NARCIS (Netherlands)

Hummel, T.

2001-01-01

This report is one in a series of publications, used in the development of the network planning tool ‘Safer Transportation Network Planning’ (Safer-TNP). The publications were used to guide the development of planning structures, diagnostic tools, planning recommendations, and research information

[Patient safety culture in hospitals: experiences in planning, organising and conducting a survey among hospital staff].

Science.gov (United States)

van Vegten, Amanda; Pfeiffer, Yvonne; Giuliani, Francesca; Manser, Tanja

2011-01-01

This article presents the first hospital-wide survey on patient safety climate, involving all staff (medical and non-medical), in the German-speaking area. Its aim is to share our experiences with planning, organising and conducting this survey. The study was performed at the university hospital in Zurich and had a response rate of 46.8% (2,897 valid questionnaires). The survey instrument ("Patientensicherheitsklimainventar") was based on the Hospital Survey on Patient Safety Culture (AHRQ). Primarily it allowed for assessing the current patient safety climate as well as identifying specific areas for improvement and creating a hospital-wide awareness and acceptance for patient safety issues and interventions (e.g., the introduction of a Critical Incident Reporting System [CIRS]). We discuss the basic principles and the feedback concept guiding the organisation of the overall project. Critical to the success of this project were the guaranteed anonymity of the respondents, adequate communication through well-established channels within the organisation and the commitment of the management across all project phases. Copyright © 2011. Published by Elsevier GmbH.

Reducing risk where tectonic plates collide—U.S. Geological Survey subduction zone science plan

Science.gov (United States)

Gomberg, Joan S.; Ludwig, Kristin A.; Bekins, Barbara; Brocher, Thomas M.; Brock, John C.; Brothers, Daniel; Chaytor, Jason D.; Frankel, Arthur; Geist, Eric L.; Haney, Matt; Hickman, Stephen H.; Leith, William S.; Roeloffs, Evelyn A.; Schulz, William H.; Sisson, Thomas W.; Wallace, Kristi; Watt, Janet; Wein, Anne M.

2017-06-19

The U.S. Geological Survey (USGS) serves the Nation by providing reliable scientific information and tools to build resilience in communities exposed to subduction zone earthquakes, tsunamis, landslides, and volcanic eruptions. Improving the application of USGS science to successfully reduce risk from these events relies on whole community efforts, with continuing partnerships among scientists and stakeholders, including researchers from universities, other government labs and private industry, land-use planners, engineers, policy-makers, emergency managers and responders, business owners, insurance providers, the media, and the general public.Motivated by recent technological advances and increased awareness of our growing vulnerability to subduction-zone hazards, the USGS is uniquely positioned to take a major step forward in the science it conducts and products it provides, building on its tradition of using long-term monitoring and research to develop effective products for hazard mitigation. This science plan provides a blueprint both for prioritizing USGS science activities and for delineating USGS interests and potential participation in subduction zone science supported by its partners.The activities in this plan address many USGS stakeholder needs:High-fidelity tools and user-tailored information that facilitate increasingly more targeted, neighborhood-scale decisions to mitigate risks more cost-effectively and ensure post-event operability. Such tools may include maps, tables, and simulated earthquake ground-motion records conveying shaking intensity and frequency. These facilitate the prioritization of retrofitting of vulnerable infrastructure;Information to guide local land-use and response planning to minimize development in likely hazardous zones (for example, databases, maps, and scenario documents to guide evacuation route planning in communities near volcanoes, along coastlines vulnerable to tsunamis, and built on landslide-prone terrain);New tools

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

Energy Technology Data Exchange (ETDEWEB)

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

1993-05-01

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

Evolution of a holistic systems approach to planning and managing road safety: the Victorian case study, 1970-2015.

Science.gov (United States)

Muir, Carlyn; Johnston, Ian R; Howard, Eric

2018-06-01

The Victorian Safe System approach to road safety slowly evolved from a combination of the Swedish Vision Zero philosophy and the Sustainable Safety model developed by the Dutch. The Safe System approach reframes the way in which road safety is viewed and managed. This paper presents a case study of the institutional change required to underpin the transformation to a holistic approach to planning and managing road safety in Victoria, Australia. The adoption and implementation of a Safe System approach require strong institutional leadership and close cooperation among all the key agencies involved, and Victoria was fortunate in that it had a long history of strong interagency mechanisms in place. However, the challenges in the implementation of the Safe System strategy in Victoria are generally neither technical nor scientific; they are predominantly social and political. While many governments purport to develop strategies based on Safe System thinking, on-the-ground action still very much depends on what politicians perceive to be publicly acceptable, and Victoria is no exception. This is a case study of the complexity of institutional change and is presented in the hope that the lessons may prove useful for others seeking to adopt more holistic planning and management of road safety. There is still much work to be done in Victoria, but the institutional cultural shift has taken root. Ongoing efforts must be continued to achieve alert and compliant road users; however, major underpinning benefits will be achieved through focusing on road network safety improvements (achieving forgiving infrastructure, such as wire rope barriers) in conjunction with reviews of posted speed limits (to be set in response to the level of protection offered by the road infrastructure) and by the progressive introduction into the fleet of modern vehicle safety features. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2018. All rights

Site Safety and Health Plan (Phase 3) for the treatability study for in situ vitrification at Seepage Pit 1 in Waste Area Grouping 7, Oak Ridge National Laboratory, Oak Ridge, TN

International Nuclear Information System (INIS)

Spalding, B.P.; Naney, M.T.

1995-06-01

This plan is to be implemented for Phase III ISV operations and post operations sampling. Two previous project phases involving site characterization have been completed and required their own site specific health and safety plans. Project activities will take place at Seepage Pit 1 in Waste Area Grouping 7 at ORNL, Oak Ridge, Tennessee. Purpose of this document is to establish standard health and safety procedures for ORNL project personnel and contractor employees in performance of this work. Site activities shall be performed in accordance with Energy Systems safety and health policies and procedures, DOE orders, Occupational Safety and Health Administration Standards 29 CFR Part 1910 and 1926; applicable United States Environmental Protection Agency requirements; and consensus standards. Where the word ''shall'' is used, the provisions of this plan are mandatory. Specific requirements of regulations and orders have been incorporated into this plan in accordance with applicability. Included from 29 CFR are 1910.120 Hazardous Waste Operations and Emergency Response; 1910.146, Permit Required - Confined Space; 1910.1200, Hazard Communication; DOE Orders requirements of 5480.4, Environmental Protection, Safety and Health Protection Standards; 5480.11, Radiation Protection; and N5480.6, Radiological Control Manual. In addition, guidance and policy will be followed as described in the Environmental Restoration Program Health and Safety Plan. The levels of personal protection and the procedures specified in this plan are based on the best information available from reference documents and site characterization data. Therefore, these recommendations represent the minimum health and safety requirements to be observed by all personnel engaged in this project

Site Safety and Health Plan (Phase 3) for the treatability study for in situ vitrification at Seepage Pit 1 in Waste Area Grouping 7, Oak Ridge National Laboratory, Oak Ridge, TN

Energy Technology Data Exchange (ETDEWEB)

Spalding, B.P.; Naney, M.T.

1995-06-01

This plan is to be implemented for Phase III ISV operations and post operations sampling. Two previous project phases involving site characterization have been completed and required their own site specific health and safety plans. Project activities will take place at Seepage Pit 1 in Waste Area Grouping 7 at ORNL, Oak Ridge, Tennessee. Purpose of this document is to establish standard health and safety procedures for ORNL project personnel and contractor employees in performance of this work. Site activities shall be performed in accordance with Energy Systems safety and health policies and procedures, DOE orders, Occupational Safety and Health Administration Standards 29 CFR Part 1910 and 1926; applicable United States Environmental Protection Agency requirements; and consensus standards. Where the word ``shall`` is used, the provisions of this plan are mandatory. Specific requirements of regulations and orders have been incorporated into this plan in accordance with applicability. Included from 29 CFR are 1910.120 Hazardous Waste Operations and Emergency Response; 1910.146, Permit Required - Confined Space; 1910.1200, Hazard Communication; DOE Orders requirements of 5480.4, Environmental Protection, Safety and Health Protection Standards; 5480.11, Radiation Protection; and N5480.6, Radiological Control Manual. In addition, guidance and policy will be followed as described in the Environmental Restoration Program Health and Safety Plan. The levels of personal protection and the procedures specified in this plan are based on the best information available from reference documents and site characterization data. Therefore, these recommendations represent the minimum health and safety requirements to be observed by all personnel engaged in this project.

RISMC advanced safety analysis project plan: FY2015 - FY2019. Light Water Reactor Sustainability Program

International Nuclear Information System (INIS)

Szilard, Ronaldo H; Smith, Curtis L; Youngblood, Robert

2014-01-01

In this report, the Advanced Safety Analysis Program (ASAP) objectives and value proposition is described. ASAP 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. The set of tools will also benefit the design of new reactors, enhancing safety per unit cost of a nuclear plant. As part of the discussion, we have identified three sets of stakeholders, the nuclear industry, the Department of Energy (DOE), and associated oversight organizations. These three groups would benefit from ASAP in different ways. For example, within the DOE complex, the possible applications that are seen include the safety of experimental reactors, facility life extension, safety-by-design in future generation advanced reactors, and managing security for the storage of nuclear material. This report provides information in five areas: (1) A value proposition (@@@why is this important?@@@) that will make the case for stakeholder's use of the ASAP research and development (R&D) products; (2) An identification of likely end users and pathway to adoption of enhanced tools by the end-users; (3) A proposed set of practical and achievable @@use case@@@ demonstrations; (4) A proposed plan to address ASAP verification and validation (V&V) needs; and (5) A proposed schedule for the multi-year ASAP.

Reducing variability of workforce as a tool to improve plan reliability

DEFF Research Database (Denmark)

Wandahl, Søren; Yicheng, S.; Zygmunt, K. J.

Variability of flow is recognized as the greatest obstacle to production management. Since the work flow and labour flow are two dominators of work performance, it is important to manage them simultaneously. The objective of this paper is to examine whether by reducing the variance of a labour flow......, a plan reliability can be improved, therefore, three different construction labour data sets have been examined by utilizing Monte Carlo Simulation, to analyze the probability to finish simulated projects within a certain time. The research findings revealed that reducing variance in the workforce flow...... does not necessarily shorten the project length, nevertheless it increases probability to finish the tasks within a critical path duration. Additionally, it was concluded, that reducing the variance of crew allocation can improve the productivity....

Reducing Variability of Workforce as a Tool to Improve Plan Reliability

DEFF Research Database (Denmark)

Shen, Yicheng; Zygmunt, Katarzyna Julia; Wandahl, Søren

2017-01-01

Variability of flow is recognized as one of the greatest obstacles to production management. Since the work flow and labour flow are two dominators of work performance, it is important to manage them simultaneously. The objective of this paper is to examine if an increased plan reliability could...... of the workforce flow does not necessarily shorten the project length, nevertheless it increases probability to finish the tasks within a critical path duration. Additionally, it was concluded, that reducing the variance of crew allocation can improve the productivity....... be reached by reducing the variance of a labour flow. Therefore, three different construction labour data sets have been examined by utilizing Monte Carlo Simulation, to analyze the probability to finish simulated projects within a certain time. The research findings revealed that reducing variance...

75 FR 36773 - Pipeline Safety: Updating Facility Response Plans in Light of the Deepwater Horizon Oil Spill

Science.gov (United States)

2010-06-28

... have been, or are subsequently relocated to the Gulf to respond to the Deepwater Horizon event should.... PHMSA-2010-0175] Pipeline Safety: Updating Facility Response Plans in Light of the Deepwater Horizon Oil... 194. In light of the Deepwater Horizon oil spill in the Gulf of Mexico, which has resulted in the...

Sodium fast reactor safety and licensing research plan - Volume II

International Nuclear Information System (INIS)

Ludewig, H.; Powers, D.A.; Hewson, John C.; LaChance, Jeffrey L.; Wright, A.; Phillips, J.; Zeyen, R.; Clement, B.; Garner, Frank; Walters, Leon; Wright, Steve; Ott, Larry J.; Suo-Anttila, Ahti Jorma; Denning, Richard; Ohshima, Hiroyuki; Ohno, S.; Miyhara, S.; Yacout, Abdellatif; Farmer, M.; Wade, D.; Grandy, C.; Schmidt, R.; Cahalen, J.; Olivier, Tara Jean; Budnitz, R.; Tobita, Yoshiharu; Serre, Frederic; Natesan, Ken; Carbajo, Juan J.; Jeong, Hae-Yong; Wigeland, Roald; Corradini, Michael; Thomas, Justin; Wei, Tom; Sofu, Tanju; Flanagan, George F.; Bari, R.; Porter D.

2012-01-01

Expert panels comprised of subject matter experts identified at the U.S. National Laboratories (SNL, ANL, INL, ORNL, LBL, and BNL), universities (University of Wisconsin and Ohio State University), international agencies (IRSN, CEA, JAEA, KAERI, and JRC-IE) and private consultation companies (Radiation Effects Consulting) were assembled to perform a gap analysis for sodium fast reactor licensing. Expert-opinion elicitation was performed to qualitatively assess the current state of sodium fast reactor technologies. Five independent gap analyses were performed resulting in the following topical reports: (1) Accident Initiators and Sequences (i.e., Initiators/Sequences Technology Gap Analysis), (2) Sodium Technology Phenomena (i.e., Advanced Burner Reactor Sodium Technology Gap Analysis), (3) Fuels and Materials (i.e., Sodium Fast Reactor Fuels and Materials: Research Needs), (4) Source Term Characterization (i.e., Advanced Sodium Fast Reactor Accident Source Terms: Research Needs), and (5) Computer Codes and Models (i.e., Sodium Fast Reactor Gaps Analysis of Computer Codes and Models for Accident Analysis and Reactor Safety). Volume II of the Sodium Research Plan consolidates the five gap analysis reports produced by each expert panel, wherein the importance of the identified phenomena and necessities of further experimental research and code development were addressed. The findings from these five reports comprised the basis for the analysis in Sodium Fast Reactor Research Plan Volume I.

Sodium fast reactor safety and licensing research plan. Volume II.

Energy Technology Data Exchange (ETDEWEB)

Ludewig, H. (Brokhaven National Laboratory, Upton, NY); Powers, D. A.; Hewson, John C.; LaChance, Jeffrey L.; Wright, A. (Argonne National Laboratory, Argonne, IL); Phillips, J.; Zeyen, R. (Institute for Energy Petten, Saint-Paul-lez-Durance, France); Clement, B. (IRSN/DPAM.SEMIC Bt 702, Saint-Paul-lez-Durance, France); Garner, Frank (Radiation Effects Consulting, Richland, WA); Walters, Leon (Advanced Reactor Concepts, Los Alamos, NM); Wright, Steve; Ott, Larry J. (Oak Ridge National Laboratory, Oak Ridge, TN); Suo-Anttila, Ahti Jorma; Denning, Richard (Ohio State University, Columbus, OH); Ohshima, Hiroyuki (Japan Atomic Energy Agency, Ibaraki, Japan); Ohno, S. (Japan Atomic Energy Agency, Ibaraki, Japan); Miyhara, S. (Japan Atomic Energy Agency, Ibaraki, Japan); Yacout, Abdellatif (Argonne National Laboratory, Argonne, IL); Farmer, M. (Argonne National Laboratory, Argonne, IL); Wade, D. (Argonne National Laboratory, Argonne, IL); Grandy, C. (Argonne National Laboratory, Argonne, IL); Schmidt, R.; Cahalen, J. (Argonne National Laboratory, Argonne, IL); Olivier, Tara Jean; Budnitz, R. (Lawrence Berkeley National Laboratory, Berkeley, CA); Tobita, Yoshiharu (Japan Atomic Energy Agency, Ibaraki, Japan); Serre, Frederic (Centre d' %C3%94etudes nucl%C3%94eaires de Cadarache, Cea, France); Natesan, Ken (Argonne National Laboratory, Argonne, IL); Carbajo, Juan J. (Oak Ridge National Laboratory, Oak Ridge, TN); Jeong, Hae-Yong (Korea Atomic Energy Research Institute, Daejeon, Korea); Wigeland, Roald (Idaho National Laboratory, Idaho Falls, ID); Corradini, Michael (University of Wisconsin-Madison, Madison, WI); Thomas, Justin (Argonne National Laboratory, Argonne, IL); Wei, Tom (Argonne National Laboratory, Argonne, IL); Sofu, Tanju (Argonne National Laboratory, Argonne, IL); Flanagan, George F. (Oak Ridge National Laboratory, Oak Ridge, TN); Bari, R. (Brokhaven National Laboratory, Upton, NY); Porter D. (Idaho National Laboratory, Idaho Falls, ID); Lambert, J. (Argonne National Laboratory, Argonne, IL); Hayes, S. (Idaho National Laboratory, Idaho Falls, ID); Sackett, J. (Idaho National Laboratory, Idaho Falls, ID); Denman, Matthew R.

2012-05-01

Expert panels comprised of subject matter experts identified at the U.S. National Laboratories (SNL, ANL, INL, ORNL, LBL, and BNL), universities (University of Wisconsin and Ohio State University), international agencies (IRSN, CEA, JAEA, KAERI, and JRC-IE) and private consultation companies (Radiation Effects Consulting) were assembled to perform a gap analysis for sodium fast reactor licensing. Expert-opinion elicitation was performed to qualitatively assess the current state of sodium fast reactor technologies. Five independent gap analyses were performed resulting in the following topical reports: (1) Accident Initiators and Sequences (i.e., Initiators/Sequences Technology Gap Analysis), (2) Sodium Technology Phenomena (i.e., Advanced Burner Reactor Sodium Technology Gap Analysis), (3) Fuels and Materials (i.e., Sodium Fast Reactor Fuels and Materials: Research Needs), (4) Source Term Characterization (i.e., Advanced Sodium Fast Reactor Accident Source Terms: Research Needs), and (5) Computer Codes and Models (i.e., Sodium Fast Reactor Gaps Analysis of Computer Codes and Models for Accident Analysis and Reactor Safety). Volume II of the Sodium Research Plan consolidates the five gap analysis reports produced by each expert panel, wherein the importance of the identified phenomena and necessities of further experimental research and code development were addressed. The findings from these five reports comprised the basis for the analysis in Sodium Fast Reactor Research Plan Volume I.

Progress of nuclear safety research. 2001

Energy Technology Data Exchange (ETDEWEB)

Anoda, Yoshinari; Sasajima, Hideo; Nishiyama, Yutaka (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [and others

2001-10-01

JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy or the Safety Research Annual Plan issued by the Japanese government. The safety research at JAERI concerns the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety. This report summarizes the nuclear safety research activities of JAERI from April 1999 through March 2001. (author)

Planning report for the safety assessment SR-Can

Energy Technology Data Exchange (ETDEWEB)

NONE

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{sup -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

Health and safety plan for phase II of the Bear Creek Valley treatability study Oak Ridge Y-12 plant, Oak Ridge, Tennessee

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-05-01

This Health and Safety Plan (HASP) addresses the health and safety (H&S) concerns and requirements for the Bear Creek Valley (BCV) Treatability Study at the Oak Ridge Y-12 Plant. Samples will be collected from effluent following treatment tests of extraction columns, algal mats, and mature wetlands supplied by surface water locations and existing groundwater monitoring well locations. The project Sampling and Analysis Plan addresses the project description, technical objectives, procedures, and planned work activities in greater detail. It is the responsibility of the project managers, field manager, and site health and safety officer (SHSO) to determine that the requirements of this HASP are sufficiently protective. If it is determined that the requirements of this HASP are not sufficiently protective, a field change order(s) (FCO) will be prepared. FCOs will include a completed job hazard analysis or similar worksheet to ensure complete hazard assessment. FCOs must be approved by the Environmental Management and Enrichment Facilities (EMEF) project manager, EMEF H&S manager, subcontractor project or field manager, and subcontractor H&S representative. As a minimum, FCOs will be prepared if additional tasks will be performed or if contaminant exposure is anticipated.

Health and safety plan for phase II of the Bear Creek Valley treatability study Oak Ridge Y-12 plant, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1997-05-01

This Health and Safety Plan (HASP) addresses the health and safety (H ampersand S) concerns and requirements for the Bear Creek Valley (BCV) Treatability Study at the Oak Ridge Y-12 Plant. Samples will be collected from effluent following treatment tests of extraction columns, algal mats, and mature wetlands supplied by surface water locations and existing groundwater monitoring well locations. The project Sampling and Analysis Plan addresses the project description, technical objectives, procedures, and planned work activities in greater detail. It is the responsibility of the project managers, field manager, and site health and safety officer (SHSO) to determine that the requirements of this HASP are sufficiently protective. If it is determined that the requirements of this HASP are not sufficiently protective, a field change order(s) (FCO) will be prepared. FCOs will include a completed job hazard analysis or similar worksheet to ensure complete hazard assessment. FCOs must be approved by the Environmental Management and Enrichment Facilities (EMEF) project manager, EMEF H ampersand S manager, subcontractor project or field manager, and subcontractor H ampersand S representative. As a minimum, FCOs will be prepared if additional tasks will be performed or if contaminant exposure is anticipated

Safety managements of the linear IFMIF/EVEDA prototype accelerator

International Nuclear Information System (INIS)

Takahashi, Hiroki; Maebara, Sunao; Kojima, Toshiyuki; Narita, Takahiro; Tsutsumi, Kazuyoshi; Sakaki, Hironao; Suzuki, Hiromitsu; Sugimoto, Masayoshi

2014-01-01

Highlights: •Safety management is needed to secure the personnel safety from high dose rate. •The management of access to the accelerator vault is mainly performed by PPS. •The operation management is needed for safety during Injector and RFQ commissioning. •Pulse Duty Management system is newly developed for Injector commissioning for operation management. •PDM system is useful to reduce the radioactivation of equipment and the radiation exposure during and after beam operation. -- Abstract: On the Linear IFMIF/EVEDA Prototype Accelerator (LIPAc), the validation up to 9 MeV deuteron beam with 125 mA continuous wave is planned in Rokkasho, Aomori, Japan. Since the deuteron beam power exceeds 1 MW, safety issue related to γ-ray and neutron production is critical. To establish the safety management indispensable to reduce radiation exposure for personnel and activation of accelerator equipment, Personnel Protection System (PPS) of LIPAc control system, which works together with Radiation Monitoring System and Access Control System, was developed for LIPAc. The management of access to the accelerator vault by PPS and the beam duty management of PPS are presented in details

Environmental 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.; Tiner, P.F.; Gosslee, R.C.

1998-01-01

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 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 environmental protection and 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

Environmental 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.; Tiner, P.F.; Gosslee, R.C.

1998-01-01

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 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 environmental protection and 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.

A change management approach to improving safety and preventing needle stick injuries.

Science.gov (United States)

Aziz, Ann-Marie

2017-09-01

Key drivers for preventing healthcare-associated infection (HCAI) include evidence-based practices and procedures that prevent infection. Among the current guidance for preventing HCAIs is evidence and mandatory requirements for reducing needle stick injuries (NSIs). This article highlights how John Kotter's model for change could help healthcare workers plan for successful and sustained deployment of needle safety devices (NSDs) and ultimately reduce the risk of a NSI.

Emergency response plan for accidents in Saudi Arabia

International Nuclear Information System (INIS)

Al-Solaiman, K.M.; Al-Arfaj, A.M.; Farouk, M.A.

2000-01-01

This paper presents a brief description of the general emergency plan for accidents involving radioactive materials in the Kingdom of Saudi Arabia. Uses of radioactive materials and radiation sources and their associated potential accident are specified. Most general accident scenarios of various levels have been determined. Protective measures have been specified to reduce individual and collective doses arising during accident situations. Intervention levels for temporary exposure situations, as established in the IAEA's basic safety standards for protection against ionising radiation and for the safety of radiation sources, are adopted as national intervention levels. General procedures for implementation of the response plan, including notification and radiological monitoring instrumentation and equipment, are described and radiation monitoring teams are nominated. Training programs for the different parties which may be called upon to respond are studied and will be started. (author)

In–Service Road Safety Audits

Directory of Open Access Journals (Sweden)

A. Mendoza–Díaz

2009-04-01

Full Text Available A road safety audit is a formal analysis that seeks to guarantee that an existing or future road fulfills optimal safety criteria, conducted by a team of experts who se members are independent of the road project. It can be carried out in one, several or all of the stages of the project (planning, design, construction, before opening the road to traffic, and operation. The development and implementation of a road safety audit process is one of the strategies that have been applied in Mexico in recent years to reduce road accidents and their associated consequences. The objective of this work is to present the procedures that have been developed and applied in Mexico, as well as the benefits and problems that have been encountered. The application of those procedures to a specific case is also shown. Emphasis is made in the audit of high ways in the operation stage, which is the type that greater application and development has had in Mexico.

Strategic planning to reduce conflicts for offshore wind development in Taiwan: A social marketing perspective.

Science.gov (United States)

Chen, Jyun-Long; Liu, Hsiang-Hsi; Chuang, Ching-Ta

2015-10-15

This study aims to improve the current inefficiency and ineffectiveness of communications among stakeholders when planning and constructing offshore wind farms (OWFs). An analysis using a social marketing approach with segmentation techniques is used to identify the target market based on stakeholders' perceptions. The empirical results identify three stakeholder segments: (1) impact-attend group; (2) comprehensive group; and (3) benefit-attend group. The results suggest that communication should be implemented to alter stakeholders' attitudes toward the construction of OWFs. Furthermore, based on the results of segmentation, target markets are identified to plan the communication strategies for reducing the conflicts among stakeholders of OWF construction. The results also indicated that in the planning phase of construction for OWFs, effective stakeholder participation and policy communication can enhance the perception of benefits to reduce conflict with local communities and ocean users. Copyright © 2015 Elsevier Ltd. All rights reserved.

Modification of JRR-4 based on safety evaluation

Energy Technology Data Exchange (ETDEWEB)

Izumo, Hironobu; Nakajima, Teruo; Funayama, Yoshiro [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1998-10-01

Since the first criticality was achieved on January 28, 1965, JRR-4 has been operated safely until on January 12, 1996. The modification of JRR-4 was planned according to the framework of reduced enrichment on research reactor program. The modification was designed based on the several national safety guides. JRR-4 has some modifications of facilities to satisfy the guides and guides criteria. (author)

Seismic Safety Guide

International Nuclear Information System (INIS)

Eagling, D.G.

1985-01-01

The Seismic Safety Guide provides facilities managers with practical guidelines for administering a comprehensive earthquake safety program. Most facilities managers, unfamiliar with earthquake engineering, tend to look for answers in techniques more sophisticated than required to solve the actual problems in earthquake safety. Often the approach to solutions to these problems is so academic, legalistic, and financially overwhelming that mitigation of actual seismic hazards simply does not get done in a timely, cost-effective way. The objective of the Guide is to provide practical advice about earthquake safety so that managers and engineers can get the job done without falling into common pitfalls, prolonged diagnosis, and unnecessary costs. It is comprehensive with respect to earthquakes in that it covers the most important aspects of natural hazards, site planning, rehabilitation of existing buildings, design of new facilities, operational safety, emergency planning, non-structural elements, life lines, and risk management. 5 references

Putting the puzzle together: Reducing vulnerability through people-focused planning

International Nuclear Information System (INIS)

Hutton, D.

2009-01-01

Supporting and integrating vulnerable persons into emergency management has emerged as an increasing priority in emergency management in Canada. Events such as the 2003 European heat wave and Hurricane Katrina have shown that disasters almost always have the harshest affects on the frail elderly, people with disabilities, the disadvantaged and the least able. While it is neither possible-nor the role of emergency management-to eliminate or reduce many factors that make people vulnerable to hazards, it is important that emergency managers work closely with communities to not only identify risks and vulnerabilities, but also to build on the resources and capacities that enable people to effectively prepare for, respond to and recover from threats of all types. To this end, emergency management must take into account the level of capacities and resources that a community has to prepare for emergencies and disasters, in addition to people's vulnerabilities to extreme events. To be successful, people must be viewed not as a part of the problem to be solved or managed during an emergency, but rather a part of the solution to building more resilient and disaster-resistant societies. This requires 'people-focused' planning methodologies that move beyond planning for to planning with all segments of society, including the most vulnerable and marginalised groups that are more readily overlooked. This not only begins to ensure that emergency planning and response capacities can effectively address the diverse needs of all people, but is also an important step to empowering the most vulnerable to prepare themselves for emergencies and other critical events. (authors)

Requirements on the provisional safety analyses and technical comparison of safety measures

International Nuclear Information System (INIS)

2010-04-01

The concept of a Geological Underground Repository (SGT) was adopted by the Swiss Federal Council on April 2 nd , 2008. It fixes the goals and the safety technical criteria as well as the procedures for the choice of the site for an underground repository. Those responsible for waste management evaluate possible site regions according to the present status of geological knowledge and based on the safety criteria defined in SGT as well as on technical feasibility. In a first step, they propose geological repository sites for high level (HAA) and for low and intermediate level (SMA) radioactive wastes and justify their choice in a report delivered to the Swiss Federal Office of Energy. The Swiss Federal Council reviews the choices presented and, in the case of positive evaluation, approves them and considers them as an initial orientation. In a second step, based on the possible sites according to step 1, the waste management institution responsible has to reduce the repositories chosen for HAA and SMA by taking into account safety aspects, technical feasibility as well as space planning and socio-economical aspects. In making this choice, safety aspects have the highest priority. The criteria used for the evaluation in the first step have to be defined using provisional quantitative safety analyses. On the basis of the whole appraisal, including space planning and socio-economical aspects, those responsible for waste management propose at least two repository sites for HAA- and SMA-waste. Their selection is then reviewed by the authorities and, in the case of a positive assesment, the selection is taken as an intermediate result. The remaining sites are further studied to examine site choice and the delivery of a request for a design license. If necessary, the requested geological knowledge has to be confirmed by new investigations. Based on the results of the choosing process and a positive evaluation by the safety authorities, the Swiss Federal Council has to

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

International Nuclear Information System (INIS)

BOGER, R.M.

1999-01-01

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

The Event Chain of Survival in the Context of Music Festivals: A Framework for Improving Outcomes at Major Planned Events.

Science.gov (United States)

Lund, Adam; Turris, Sheila

2017-08-01

Despite the best efforts of event producers and on-site medical teams, there are sometimes serious illnesses, life-threatening injuries, and fatalities related to music festival attendance. Producers, clinicians, and researchers are actively seeking ways to reduce the mortality and morbidity associated with these events. After analyzing the available literature on music festival health and safety, several major themes emerged. Principally, stakeholder groups planning in isolation from one another (ie, in silos) create fragmentation, gaps, and overlap in plans for major planned events (MPEs). The authors hypothesized that one approach to minimizing this fragmentation may be to create a framework to "connect the dots," or join together the many silos of professionals responsible for safety, security, health, and emergency planning at MPEs. Adapted from the well-established literature regarding the management of cardiac arrests, both in and out of hospital, the "chain of survival" concept is applied to the disparate groups providing services that support event safety in the context of music festivals. The authors propose this framework for describing, understanding, coordinating and planning around the integration of safety, security, health, and emergency service for events. The adapted Event Chain of Survival contains six interdependent links, including: (1) event producers; (2) police and security; (3) festival health; (4) on-site medical services; (5) ambulance services; and (6) off-site medical services. The authors argue that adapting and applying this framework in the context of MPEs in general, and music festivals specifically, has the potential to break down the current disconnected approach to event safety, security, health, and emergency planning. It offers a means of shifting the focus from a purely reactive stance to a more proactive, collaborative, and integrated approach. Improving health outcomes for music festival attendees, reducing gaps in planning

Evaluation of the probabilistic safety assessment portfolio for NSD. Plan of work

International Nuclear Information System (INIS)

Gould, J.

1999-01-01

The aim is to use the research portfolio evaluation protocol developed by HSL to evaluate the Probabilistic Safety Assessment (PSA) portfolio, both to draw conclusions about the PSA portfolio and as a pilot study to show the suitability of the evaluation protocol. The objectives of the work are: (1) To collect sufficient information to carry out a preliminary review of the portfolio; (2) o produce a plan of work detailing the time and costs to carry out a full evaluation of the PSA portfolio; (3) to evaluate the PSA portfolio of research; (4) to produce a report of the evaluation of the PSA portfolio; (5) if necessary, to make changes to the methodology in light of the experience gained in the evaluation of the PSA research portfolio. This report completes objectives 1 and 2. It details the plan of work for the evaluation of the PSA research portfolio. The plan has shown that the evaluation of the PSA research portfolio has many difficulties to overcome. It is suitable as a pilot study to show the suitability of the portfolio evaluation protocol and will provide valuable information that can be used to improve it. The evaluation of the PSA portfolio will require a considerable amount of time and effort to complete. The task analysis has shown it to be of the order of Pound Sterling 25k and to take two months to complete after this preliminary data collection. The plan to evaluate the PSA research portfolio detailed in this report should be carried out and the lessons learned by carrying out this pilot study should be used to improve the evaluation protocol

A business planning model to identify new safety net clinic locations.

Science.gov (United States)

Langabeer, James; Helton, Jeffrey; DelliFraine, Jami; Dotson, Ebbin; Watts, Carolyn; Love, Karen

2014-01-01

Community health clinics serving the poor and underserved are geographically expanding due to changes in U.S. health care policy. This paper describes the experience of a collaborative alliance of health care providers in a large metropolitan area who develop a conceptual and mathematical decision model to guide decisions on expanding its network of community health clinics. Community stakeholders participated in a collaborative process that defined constructs they deemed important in guiding decisions on the location of community health clinics. This collaboration also defined key variables within each construct. Scores for variables within each construct were then totaled and weighted into a community-specific optimal space planning equation. This analysis relied entirely on secondary data available from published sources. The model built from this collaboration revolved around the constructs of demand, sustainability, and competition. It used publicly available data defining variables within each construct to arrive at an optimal location that maximized demand and sustainability and minimized competition. This is a model that safety net clinic planners and community stakeholders can use to analyze demographic and utilization data to optimize capacity expansion to serve uninsured and Medicaid populations. Communities can use this innovative model to develop a locally relevant clinic location-planning framework.

Safety upgrades to the NRU research reactor

International Nuclear Information System (INIS)

DeAbreu, B.; Mark, J.M.; Mutterback, E.J.

1998-01-01

The NRU (National Research Universal) Reactor is a 135 MW thermal research facility located at Chalk River Laboratories, and is owned and operated by Atomic Energy of Canada Limited. One of the largest and most versatile research reactors in the world, it serves as the R and D workhorse for Canada's CANDU business while at the same time filling the role as one of the world's major producers of medical radioisotopes. AECL plans to extend operation of the NRU reactor to approximately the year 2005 when a new replacement, the Irradiation Research Facility (IRF) will be available. To achieve this, AECL has undertaken a program of safety reassessment and upgrades to enhance the level of safety consistent with modem requirements. An engineering assessment/inspection of critical systems, equipment and components was completed and seven major safety upgrades are being designed and installed. These upgrades will significantly reduce the reactor's vulnerability to common mode failures and external hazards, with particular emphasis on seismic protection. The scheduled completion date for the project is 1999 December at a cost approximately twice the annual operating cost. All work on the NRU upgrade project is planned and integrated into the regular operating cycles of the reactor; no major outages are anticipated. This paper describes the safety upgrades and discusses the technical and managerial challenges involved in extending the operating life of the NRU reactor. (author)

Land use planning in Safer Transportation Network Planning : safety principles, planning framework, and library information.

NARCIS (Netherlands)

Hummel, T.

2001-01-01

This report is one in a series of publications, used in the development of the network planning tool ‘Safer Transportation Network Planning’ (Safer-TNP). The publications were used to guide the development of planning structures, diagnostic tools, planning recommendations, and research information

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.

The safety of risk or the risk of safety?

NARCIS (Netherlands)

Suddle, S.I.; Waarts, P.H.

2003-01-01

Safety is nowadays one of the main items on the agenda during the planning, realisation and management of most large-scale projects, particularly in infrastructure and building projects in intensively used areas such as multiple use of land projects. It is vital that safety aspects are properly

Segurança e produção: um modelo para o planejamento e controle integrado Safety and production: an integrated planning and control model

Directory of Open Access Journals (Sweden)

Tarcisio A. Saurin

2002-01-01

Full Text Available Este artigo apresenta um modelo de planejamento e controle da segurança no trabalho (PCS integrado ao processo de planejamento e controle da produção (PCP. O modelo foi desenvolvido por meio de dois estudos empíricos em obras industriais, adotando-se a pesquisa ação como estratégia de pesquisa. Os requisitos de segurança são integrados ao PCP em três níveis hierárquicos deste processo. No nível de longo prazo, o planejamento da segurança é configurado pelo desenvolvimento de análises preliminares de risco dos processos construtivos. A atualização e detalhamento da implantação destes planos é então feita por meio de sua integração aos níveis de médio e curto prazo do PCP.This paper presents a safety planning and control model (SPC that has been integrated to the production planning and control process. The model was developed through two action research empirical studies in industrial construction projects. Safety requirements are integrated into three hierarchical levels of planning and control process. At the long-term level, safety planning is featured by preliminary hazard analysis of construction processes. These plans are updated and detailed through its integration into both medium-term and short-term planning levels.

A comprehensive conceptual framework for road safety strategies.

Science.gov (United States)

Hughes, B P; Anund, A; Falkmer, T

2016-05-01

Road safety strategies (generally called Strategic Highway Safety Plans in the USA) provide essential guidance for actions to improve road safety, but often lack a conceptual framework that is comprehensive, systems theory based, and underpinned by evidence from research and practice. This paper aims to incorporate all components, policy tools by which they are changed, and the general interactions between them. A framework of nine mutually interacting components that contribute to crashes and ten generic policy tools which can be applied to reduce the outcomes of these crashes was developed and used to assess 58 road safety strategies from 22 countries across 15 years. The work identifies the policy tools that are most and least widely applied to components, highlighting the potential for improvements to any individual road safety strategy, and the potential strengths and weaknesses of road safety strategies in general. The framework also provides guidance for the development of new road safety strategies, identifying potential consequences of policy tool based measures with regard to exposure and risk, useful for both mobility and safety objectives. Copyright © 2016 Elsevier Ltd. All rights reserved.

Health and safety manual

International Nuclear Information System (INIS)

1980-02-01

The manual consists of the following chapters: general policies and administration; the Environmental Health and Safety Department; the Medical Services Department: biological hazards; chemical safety; confined space entry; cryogenic safety; electrical safety; emergency plans; engineering and construction; evacuations, trenching, and shoring; fire safety; gases, flammable and compressed; guarding, mechanical; ladders and scaffolds, work surfaces; laser safety; materials handling and storage; noise; personal protective equipment; pressure safety; radiation safety, ionizing and non-ionizing; sanitation; seismic safety; training, environmental health and safety; tools, power and hand-operated; traffic and transportation; and warning signs and devices

75 FR 13294 - National Boating Safety Advisory Council

Science.gov (United States)

2010-03-19

... the strategic planning process and any new issues or factors that could impact, or contribute to, the...) Recreational Boating Safety Strategic Planning Subcommittee meeting. Saturday, April 17, 2010: (12) Recreational Boating Safety Strategic Planning Subcommittee meeting (Cont.). (13) Prevention through People...

Planning Document for an NBSR Conversion Safety Analysis Report

Energy Technology Data Exchange (ETDEWEB)

Diamond D. J.; Baek J.; Hanson, A.L.; Cheng, L-Y.; Brown, N.; Cuadra, A.

2013-09-25

The NIST Center for Neutron Research (NCNR) is a reactor-laboratory complex providing the National Institute of Standards and Technology (NIST) and the nation with a world-class facility for the performance of neutron-based research. The heart of this facility is the National Bureau of Standards Reactor (NBSR). The NBSR is a heavy water moderated and cooled reactor operating at 20 MW. It is fueled with high-enriched uranium (HEU) fuel elements. A Global Threat Reduction Initiative (GTRI) program is underway to convert the reactor to low-enriched uranium (LEU) fuel. This program includes the qualification of the proposed fuel, uranium and molybdenum alloy foil clad in an aluminum alloy, and the development of the fabrication techniques. This report is a planning document for the conversion Safety Analysis Report (SAR) that would be submitted to, and approved by, the Nuclear Regulatory Commission (NRC) before the reactor could be converted.This report follows the recommended format and content from the NRC codified in NUREG-1537, “Guidelines for Preparing and Reviewing Applications for the Licensing of Non-power Reactors,” Chapter 18, “Highly Enriched to Low-Enriched Uranium Conversions.” The emphasis herein is on the SAR chapters that require significant changes as a result of conversion, primarily Chapter 4, Reactor Description, and Chapter 13, Safety Analysis. The document provides information on the proposed design for the LEU fuel elements and identifies what information is still missing. This document is intended to assist ongoing fuel development efforts, and to provide a platform for the development of the final conversion SAR. This report contributes directly to the reactor conversion pillar of the GTRI program, but also acts as a boundary condition for the fuel development and fuel fabrication pillars.

IAEA Concludes Safety Review at Gravelines Nuclear Power Plant, France

International Nuclear Information System (INIS)

2012-01-01

Full text: An IAEA-led international team of nuclear safety experts noted a series of good practices and made recommendations to reinforce some safety measures during a review of operational safety at France's Gravelines Nuclear Power Plant (NPP) that concluded today. The Operational Safety Review Team (OSART) was assembled at the French Government's request. The in-depth review, which began 12 November 2012, focused on aspects essential to the safe operation of the NPP. The team was composed of experts from Bulgaria, China, Germany, Hungary, Japan, Romania, Slovakia, South Africa, Spain, Ukraine and the IAEA. The review covered the areas of management, organization and administration; training and qualification; operations; maintenance; technical support; operating experience; radiation protection; chemistry; emergency planning and preparedness; and severe accident management. The conclusions of the review are based on the IAEA's Safety Standards. The OSART team has identified good plant practices, which will be shared with the rest of the nuclear industry for consideration of their possible use elsewhere. Examples include the following: - The Power Plant uses a staff-skills mapping process that significantly enhances knowledge of the facility's collective and individual skills and provides proactive management to address the loss of such skills; - As a measure to reduce the risk of workers' radiation exposure, the Power Plant uses a system to ensure that dose rate measurements are carried out at a precise distance from the source of radiation; and - Flood protection of the Power Plant is supported by special technical guidance documents and associated arrangements. The team identified a number of proposals for improvements to operational safety at Gravelines NPP. Examples include the following: - The Power Plant should reinforce its measures to prevent foreign objects from entering plant systems; - The Power Plant should ensure the 24-hour presence of an operator

Environmental, Safety, and Health Plan for the remedial investigation of the liquid low-level waste tanks at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1991-09-01

The Environmental, Safety, and Health (ES ampersand H) Plan presents the concepts and methodologies to be used during the Oak Ridge National Laboratory (ORNL) RI/FS project to protect the health and safety of employees, the public, and the environment. The ES ampersand H Plan acts as a management extension for ORNL and Energy Systems to direct and control implementation of the project ES ampersand H program. This report describes the program philosophy, requirements, quality assurance measures, and methods for applying the ES ampersand H program to individual task remedial investigations, project facilities, and other major tasks assigned to the project

75 FR 80054 - Input for a Strategic Plan for Federal Youth Policy

Science.gov (United States)

2010-12-21

...YouthInfo.gov , to promote effective community-based efforts to reduce the factors that put youth at...) basic needs: health, safety, and wellness; (2) school, family, and community engagement and connections... DEPARTMENT OF HEALTH AND HUMAN SERVICES Office of the Secretary Input for a Strategic Plan for...

Reducing our Carbon Footprint - an initial action plan for Northern Ireland

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-11-14

In the Energy White Paper, Our Energy Future - Creating a low carbon economy, the UK Government accepted the Royal Commission on Environmental Pollution's (RCEP) recommendations on how the UK should address the threat of climate change. These recommendations included the early development of a concerted, coordinated and integrated strategy across all Government Departments that would put the UK economy on an early path to reducing carbon dioxide (CO{sub 2}) emissions by at least 60% by 2050. Responding to this challenge, the Carbon Trust and Invest NI sponsored a project to develop an action plan that will set Northern Ireland on the path to realising the deep reductions in carbon emissions needed to reach this target. During the project, the prospects for reducing CO{sub 2} emissions (or carbon emissions) in five key sectors of the economy were examined. The main conclusion of this work was that it was possible to realise a 60% reduction in carbon emissions by 2050, provided early action is taken to set Northern Ireland on the path to a low carbon economy. The project also prepared an initial action plan to help initiate change. This consists of: Immediate actions, including encouraging the uptake of energy efficiency measures, revising building regulations and changing public procurement procedures. Developing options for the future, by supporting the exploitation of renewable resources, modifying the regulatory scheme to support combined heat and power (CHP) and encouraging additional investment in low carbon technologies. Cross-cutting actions, including developing planning procedures that take account of sustainability, marketing campaigns to capture hearts and minds, developing a skills base in low carbon technologies and exploring more radical ways of cutting carbon emissions. (UK)

Project Rulison: post-shot plans and evaluations

Energy Technology Data Exchange (ETDEWEB)

1969-12-01

Project Rulison post-shot plans and evaluations are discussed and include physical characteristics of the Rulison cavity; pressure and temperature expected in the cavity; amount, nature, and distribution of radioactivity in the cavity; reentry plan; radioactive species which may be encountered during reentry; public safety considerations arising from release of radioactivity; procedures to assure public safety; and the radiological safety plan. Maximum hypothetical accidents and ecological considerations are discussed in the appendices.

Environmental development plan: magnetic fusion

International Nuclear Information System (INIS)

1979-09-01

This Environmental Development Plan (EDP) identifies the planning and management requirements and schedules needed to evaluate and assess the environmental, health and safety (EH and S) aspects of the Magnetic Fusion Energy Program (MFE). Environment is defined to include the environmental, health (occupational and public), and safety aspects

Status of nuclear safety research - 2000

International Nuclear Information System (INIS)

Sobajima, Makoto; Sasajima, Hideo; Umemoto, Michitaka; Yamamoto, Toshihiro; Tanaka, Tadao; Togashi, Yoshihiro; Nakata, Masahito

2000-11-01

The nuclear safety research at JAERI is performed in accordance with the long term plan on nuclear research, development and use and the safety research yearly plan determined by the government and under close relationship to the related departments in and around the Nuclear Safety Research Center. The criticality accident having occurred in Tokai-mura in 1999 has been the highest level nuclear accident in Japan and ensuring safety in whole nuclear cycle is severely questioned. The causes of such an accident have to be clarified not only technical points but also organizational points, and it is extremely important to make efforts in preventing recurrence, to fulfill emergency plan and to improve the safety of whole nuclear fuel cycle for restoring the reliability by the people to nuclear energy system. The fields of conducting safety research are engineering safety research on reactor facilities and nuclear fuel cycle facilities including research on radioactive waste processing and disposal and research and development on future technology for safety improvement. Also, multinational cooperation and bilateral cooperation are promoted in international research organizations in the center to internationally share the recognition of world-common issues of nuclear safety and to attain efficient promotion of research and effective utilization of research resources. (author)

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

Safety evaluations required in the safety regulations for Monju and the validity confirmation of safety evaluation methods

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

The purposes of this study are to perform the safety evaluations of the fast breeder reactor 'Monju' and to confirm the validity of the safety evaluation methods. In JFY 2012, the following results were obtained. As for the development of safety evaluation methods needed in the safety examination achieved for the reactor establishment permission, development of the analysis codes, such as a core damage analysis code, were carried out according to the plan. As for the development of the safety evaluation method needed for the risk informed safety regulation, the quantification technique of the event tree using the Continuous Markov chain Monte Carlo method (CMMC method) were studied. (author)

Simulation study of coal mine safety investment based on system dynamics

Institute of Scientific and Technical Information of China (English)

Tong Lei; Dou Yuanyuan

2014-01-01

To generate dynamic planning for coal mine safety investment, this study applies system dynamics to decision-making, classifying safety investments by accident type. It validates the relationship between safety investments and accident cost, by structurally analyzing the causality between safety investments and their influence factors. Our simulation model, based on Vensim software, conducts simulation anal-ysis on a series of actual data from a coalmine in Shanxi Province. Our results indicate a lag phase in safety investments, and that increasing pre-phase safety investment reduces accident costs. We found that a 24%increase in initial safety investment could help reach the target accident costs level 14 months earlier. Our simulation test included nine kinds of variation trends of accident costs brought by different investment ratios on accident prevention. We found an optimized ratio of accident prevention invest-ments allowing a mine to reach accident cost goals 4 months earlier, without changing its total investment.

Seismic safety margin research program. Program plan, Revision I

International Nuclear Information System (INIS)

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

1978-01-01

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

Final report-passive safety optimization in liquid sodium-cooled reactors

International Nuclear Information System (INIS)

Cahalana, J. E.; Hahn, D.

2007-01-01

This report summarizes the results of a three-year collaboration between Argonne National Laboratory (ANL) and the Korea Atomic Energy Research Institute (KAERI) to identify and quantify the performance of innovative design features in metallic-fueled, sodium-cooled fast reactor designs. The objective of the work was to establish the reliability and safety margin enhancements provided by design innovations offering significant potential for construction, maintenance, and operating cost reductions. The project goal was accomplished with a combination of advanced model development (Task 1), analysis of innovative design and safety features (Tasks 2 and 3), and planning of key safety experiments (Task 4). Task 1--Computational Methods for Analysis of Passive Safety Design Features: An advanced three-dimensional subassembly thermal-hydraulic model was developed jointly and implemented in ANL and KAERI computer codes. The objective of the model development effort was to provide a high-accuracy capability to predict fuel, cladding, coolant, and structural temperatures in reactor fuel subassemblies, and thereby reduce the uncertainties associated with lower fidelity models previously used for safety and design analysis. The project included model formulation, implementation, and verification by application to available reactor tests performed at EBR-II. Task 2--Comparative Analysis and Evaluation of Innovative Design Features: Integrated safety assessments of innovative liquid metal reactor designs were performed to quantify the performance of inherent safety features. The objective of the analysis effort was to identify the potential safety margin enhancements possible in a sodium-cooled, metal-fueled reactor design by use of passive safety mechanisms to mitigate low-probability accident consequences. The project included baseline analyses using state-of-the-art computational models and advanced analyses using the new model developed in Task 1. Task 3--Safety

A Proposed Set of Metrics to Reduce Patient Safety Risk From Within the Anatomic Pathology Laboratory.

Science.gov (United States)

Banks, Peter; Brown, Richard; Laslowski, Alex; Daniels, Yvonne; Branton, Phil; Carpenter, John; Zarbo, Richard; Forsyth, Ramses; Liu, Yan-Hui; Kohl, Shane; Diebold, Joachim; Masuda, Shinobu; Plummer, Tim; Dennis, Eslie

2017-05-01

Anatomic pathology laboratory workflow consists of 3 major specimen handling processes. Among the workflow are preanalytic, analytic, and postanalytic phases that contain multistep subprocesses with great impact on patient care. A worldwide representation of experts came together to create a system of metrics, as a basis for laboratories worldwide, to help them evaluate and improve specimen handling to reduce patient safety risk. Members of the Initiative for Anatomic Pathology Laboratory Patient Safety (IAPLPS) pooled their extensive expertise to generate a list of metrics highlighting processes with high and low risk for adverse patient outcomes. : Our group developed a universal, comprehensive list of 47 metrics for patient specimen handling in the anatomic pathology laboratory. Steps within the specimen workflow sequence are categorized as high or low risk. In general, steps associated with the potential for specimen misidentification correspond to the high-risk grouping and merit greater focus within quality management systems. Primarily workflow measures related to operational efficiency can be considered low risk. Our group intends to advance the widespread use of these metrics in anatomic pathology laboratories to reduce patient safety risk and improve patient care with development of best practices and interlaboratory error reporting programs. © American Society for Clinical Pathology 2017.

Shortening Delivery Times of Intensity Modulated Proton Therapy by Reducing Proton Energy Layers During Treatment Plan Optimization

Energy Technology Data Exchange (ETDEWEB)

Water, Steven van de, E-mail: s.vandewater@erasmusmc.nl [Department of Radiation Oncology, Erasmus MC Cancer Institute, Rotterdam (Netherlands); Kooy, Hanne M. [F. H. Burr Proton Therapy Center, Department of Radiation Oncology, Massachusetts General Hospital and Harvard Medical School, Boston, Massachusetts (United States); Heijmen, Ben J.M.; Hoogeman, Mischa S. [Department of Radiation Oncology, Erasmus MC Cancer Institute, Rotterdam (Netherlands)

2015-06-01

Purpose: To shorten delivery times of intensity modulated proton therapy by reducing the number of energy layers in the treatment plan. Methods and Materials: We have developed an energy layer reduction method, which was implemented into our in-house-developed multicriteria treatment planning system “Erasmus-iCycle.” The method consisted of 2 components: (1) minimizing the logarithm of the total spot weight per energy layer; and (2) iteratively excluding low-weighted energy layers. The method was benchmarked by comparing a robust “time-efficient plan” (with energy layer reduction) with a robust “standard clinical plan” (without energy layer reduction) for 5 oropharyngeal cases and 5 prostate cases. Both plans of each patient had equal robust plan quality, because the worst-case dose parameters of the standard clinical plan were used as dose constraints for the time-efficient plan. Worst-case robust optimization was performed, accounting for setup errors of 3 mm and range errors of 3% + 1 mm. We evaluated the number of energy layers and the expected delivery time per fraction, assuming 30 seconds per beam direction, 10 ms per spot, and 400 Giga-protons per minute. The energy switching time was varied from 0.1 to 5 seconds. Results: The number of energy layers was on average reduced by 45% (range, 30%-56%) for the oropharyngeal cases and by 28% (range, 25%-32%) for the prostate cases. When assuming 1, 2, or 5 seconds energy switching time, the average delivery time was shortened from 3.9 to 3.0 minutes (25%), 6.0 to 4.2 minutes (32%), or 12.3 to 7.7 minutes (38%) for the oropharyngeal cases, and from 3.4 to 2.9 minutes (16%), 5.2 to 4.2 minutes (20%), or 10.6 to 8.0 minutes (24%) for the prostate cases. Conclusions: Delivery times of intensity modulated proton therapy can be reduced substantially without compromising robust plan quality. Shorter delivery times are likely to reduce treatment uncertainties and costs.

Nuclear safety authority. Strategical planning 2005- 2007

International Nuclear Information System (INIS)

Anon.

2006-01-01

The Nuclear safety Authority (A.S.N.) provides, in the name of the state, the monitoring of nuclear safety and radiation protection to protect workers, patients, public and environment from the risks in relation with nuclear activities and more broadly with ionizing radiations, it contributes to citizens information in these areas. The ambition of A.S.N. is to carry out a successful, legitimate, credible nuclear monitoring, recognized by citizens and that constitutes an international reference. (N.C.)

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...

Krsko NPP Quality Assurance Plan Application to Nuclear Safety Upgrade Projects (PCFV System and PAR System)

International Nuclear Information System (INIS)

Biscan, Romeo; Fifnja, Igor

2014-01-01

Nuklearna Elektrarna Krsko (NEK) has undertaken Nuclear Safety Upgrade Projects as a safety improvement driven by the lessons learned from the Fukushima-Daiichi Accident. Among other projects, new modification 1008-VA-L Passive Containment Filtered Vent (PCFV) System has been installed which acts as the last barrier minimizing the release of radioactive material into the environment in case of failure of all safety systems, and to insure containment integrity during beyond design basis accidents (BDBA). In addition, modification 1002-GH-L Severe Accident Hydrogen Control System (PAR) has been implemented to prevent and mitigate the consequences of explosive gas generation (hydrogen and carbon monoxide) in case of reactor core melting. To ensure containment integrity for all design basis accidents (DBA) and BDBA conditions, NEK has eliminated existing safety-related electrical recombiners, replaced them with two safety-related passive autocatalytic recombiners (PARs) and added 20 new PARs designed for the BDBA conditions. Krsko NPP Quality Assurance Plan has been applied to Nuclear Safety Upgrade Projects (PCFV System and PAR System) through the following activities: · Internal audit of modification process was performed. · Supplier audits were performed to evaluate QA program efficiency of the main design organization and engineering organizations. · Evaluation and approval of Suppliers were performed. · QA engineer was involved in the review and approval of 1008-VA-L and 1002-GH-L modification documentation (Conceptual Design Package, Design Modification Package, Installation Package, Field Design Change Request, Problem/Deficiency Report, and Final Documentation Package). · Purchasing documentation for modifications 1008-VA-L and 1002-GH-L (technical specifications, purchase orders) has been verified and approved by QA. · QA and QC engineers were involved in oversight of production and testing of the new 1008-VA-L and 1002-GH-L plant components. �

Population-based health promotion perspective for older driver safety: Conceptual framework to intervention plan

Science.gov (United States)

Classen, Sherrilene; Lopez, Ellen DS; Winter, Sandra; Awadzi, Kezia D; Ferree, Nita; Garvan, Cynthia W

2007-01-01

The topic of motor vehicle crashes among the elderly is dynamic and multi-faceted requiring a comprehensive and synergistic approach to intervention planning. This approach must be based on the values of a given population as well as health statistics and asserted through community, organizational and policy strategies. An integrated summary of the predictors (quantitative research), and views (qualitative research) of the older drivers and their stakeholders, does not currently exist. This study provided an explicit socio-ecological view explaining the interrelation of possible causative factors, an integrated summary of these causative factors, and empirical guidelines for developing public health interventions to promote older driver safety. Using a mixed methods approach, we were able to compare and integrate main findings from a national crash dataset with perspectives of stakeholders. We identified: 11 multi-causal factors for safe elderly driving; the importance of the environmental factors - previously underrated in the literature- interacting with behavioral and health factors; and the interrelatedness among many socio-ecological factors. For the first time, to our knowledge, we conceptualized the fundamental elements of a multi-causal health promotion plan, with measurable intermediate and long-term outcomes. After completing the detailed plan we will test the effectiveness of this intervention on multiple levels. PMID:18225470

Phase 2 sampling and analysis plan, Quality Assurance Project Plan, and environmental health and safety plan for the Clinch River Remedial Investigation: An addendum to the Clinch River RCRA Facility Investigation plan

International Nuclear Information System (INIS)

Cook, R.B.; Adams, S.M.; Beauchamp, J.J.; Bevelhimer, M.S.; Blaylock, B.G.; Brandt, C.C.; Etnier, E.L.; Ford, C.J.; Frank, M.L.; Gentry, M.J.; Greeley, M.S.; Halbrook, R.S.; Harris, R.A.; Holladay, S.K.; Hook, L.A.; Howell, P.L.; Kszos, L.A.; Levine, D.A.; Skiles, J.L.; Suter, G.W.

1992-12-01

This document contains a three-part addendum to the Clinch River Resource Conservation and Recovery Act (RCRA) Facility Investigation Plan. The Clinch River RCRA Facility Investigation began in 1989, as part of the comprehensive remediation of facilities on the US Department of Energy Oak Ridge Reservation (ORR). The ORR was added to the National Priorities List in December 1989. The regulatory agencies have encouraged the adoption of Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) terminology; therefore, the Clinch River activity is now referred to as the Clinch River Remedial Investigation (CRRI), not the Clinch River RCRA Facility Investigation. Part 1 of this document is the plan for sampling and analysis (S ampersand A) during Phase 2 of the CRRI. Part 2 is a revision of the Quality Assurance Project Plan for the CRRI, and Part 3 is a revision of the Environmental Health and Safety Plan for the CRRI. The Clinch River RI (CRRI) is designed to address the transport, fate, and distribution of waterborne contaminants (radionuclides, metals, and organic compounds) released from the DOE Oak Ridge Reservation (ORR) and to assess potential risks to human health and the environment associated with these contaminants. Primary areas of investigation are Melton Hill Reservoir, the Clinch River from Melton Hill Dam to its confluence with the Tennessee River, Poplar Creek, and Watts Bar Reservoir. The contaminants identified in the Clinch River/Watts Bar Reservoir (CR/WBR) downstream of the ORR are those associated with the water, suspended particles, deposited sediments, aquatic organisms, and wildlife feeding on aquatic organisms. The purpose of the Phase 2 S ampersand A Plan is to describe the proposed tasks and subtasks developed to meet the primary objectives of the CRRI

Phase 2 sampling and analysis plan, Quality Assurance Project Plan, and environmental health and safety plan for the Clinch River Remedial Investigation: An addendum to the Clinch River RCRA Facility Investigation plan

Energy Technology Data Exchange (ETDEWEB)

Cook, R.B.; Adams, S.M.; Beauchamp, J.J.; Bevelhimer, M.S.; Blaylock, B.G.; Brandt, C.C.; Etnier, E.L.; Ford, C.J.; Frank, M.L.; Gentry, M.J.; Greeley, M.S.; Halbrook, R.S.; Harris, R.A.; Holladay, S.K.; Hook, L.A.; Howell, P.L.; Kszos, L.A.; Levine, D.A.; Skiles, J.L.; Suter, G.W.

1992-12-01

This document contains a three-part addendum to the Clinch River Resource Conservation and Recovery Act (RCRA) Facility Investigation Plan. The Clinch River RCRA Facility Investigation began in 1989, as part of the comprehensive remediation of facilities on the US Department of Energy Oak Ridge Reservation (ORR). The ORR was added to the National Priorities List in December 1989. The regulatory agencies have encouraged the adoption of Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) terminology; therefore, the Clinch River activity is now referred to as the Clinch River Remedial Investigation (CRRI), not the Clinch River RCRA Facility Investigation. Part 1 of this document is the plan for sampling and analysis (S A) during Phase 2 of the CRRI. Part 2 is a revision of the Quality Assurance Project Plan for the CRRI, and Part 3 is a revision of the Environmental Health and Safety Plan for the CRRI. The Clinch River RI (CRRI) is designed to address the transport, fate, and distribution of waterborne contaminants (radionuclides, metals, and organic compounds) released from the DOE Oak Ridge Reservation (ORR) and to assess potential risks to human health and the environment associated with these contaminants. Primary areas of investigation are Melton Hill Reservoir, the Clinch River from Melton Hill Dam to its confluence with the Tennessee River, Poplar Creek, and Watts Bar Reservoir. The contaminants identified in the Clinch River/Watts Bar Reservoir (CR/WBR) downstream of the ORR are those associated with the water, suspended particles, deposited sediments, aquatic organisms, and wildlife feeding on aquatic organisms. The purpose of the Phase 2 S A Plan is to describe the proposed tasks and subtasks developed to meet the primary objectives of the CRRI.

The Influence of Laboratory Safety on Capital Planning.

Science.gov (United States)

Francis, Robert A.

1980-01-01

Discusses state and federal legislation concerning the handling of dangerous materials and its impact on the design of college and university buildings. Lists federal legislation affecting laboratory safety, the objectives of each act, and the influence of each act on laboratory safety. (IRT)

30 CFR 77.1500 - Auger mining; planning.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Auger mining; planning. 77.1500 Section 77.1500 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR COAL MINE SAFETY AND HEALTH... § 77.1500 Auger mining; planning. Auger mining shall be planned and conducted by the operator to insure...

Safety Culture and Issue in the Malaysian Manufacturing Sector

Directory of Open Access Journals (Sweden)

Ali Danish

2017-01-01

Full Text Available . This paper highlights the Safety culture and issue in the Malaysian Manufacturing Sector and emphasis the high occupational accidents due to lack of safety culture and non-compliance of the requirements of Occupational Safety and Health Act 1994. The aim of this study is to review the occupational accidents occurrence in the Malaysia workplace since 2012-2016. Malaysia aimed to reduce the occupational accidents, the results show by DOSH increase that Occupational Noise Induced Hearing Loss 83.7%, occupational musculoskeletal diseases, 4.4% and occupational lung diseases 2.3%. But the as per the record from DOSH that in last 5-Years, the increment in the fatal accidents by Average 26%, Permanent Disability by Average 71% and Non-Permanent Disability by 64 % are investigated only in Manufacturing Industries. The government must show their high interest on such a vulnerable employees to accomplish the above aim. This step will be helpful for planning to reduce the accidents in workplaces and it will also detect the prevention for the future accidents.

Safety And Reduce In Pollution Issues For Inland Waterway Transportation

Directory of Open Access Journals (Sweden)

Van Huong Dong

2017-04-01

Full Text Available According to the Ministry of Transport inland water transport is one of the five modes of transport in our country play a very important role. Inland waterway transport not only plays a major role in transporting large volumes of goods and passengers but also creates millions of jobs contributing to ensuring social security and national defense and security. However there are still many inadequacies in waterway transportation such as unequal waterway traffic The phenomenon of exploitation of river resources as planned or Process technology is not as planned exploitation of sand gravel etc. are common in most rivers and canals in the country. The signaling system is not synchronized between the signal of the inland waterway management unit and the signal of the owner The handling of domestic goods transportation and inland port management is inadequate The force of the means of development is fast uneven but concentrated in some urban areas and industrial parks. Therefore the Ministry of Transport has proposed a scheme to facilitate the development of a synchronized inland waterway infrastructure linking with other modes of transport To improve the capacity of the crew and the inland waterway transport crews. To create favorable conditions for inland waterway transportation business with reasonable transportation costs Improve the quality of water transport services Ensure safety and environmental friendliness Make a distinct advantage over other modes of transport. Specifically will develop promulgate mechanisms The policy is to facilitate the development of inland waterway infrastructure Build and promulgate mechanism The policy of supporting the development of the fleet has a reasonable structure with a fleet of about 30 self-propelled ships accounting for about 70 of the total number of inland waterway vessels To prioritize the development of the container fleet Inland waterway transportation and training retraining of human resources for

National nuclear safety report 2005. Convention on nuclear safety

International Nuclear Information System (INIS)

2006-01-01

This National Nuclear Safety Report was presented at the 3rd. Review meeting. In general the information contained in the report are: Highlights / Themes; Follow-up from 2nd. Review meeting; Challenges, achievements and good practices; Planned measures to improve safety; Updates to National report to 3rd. Review meeting; Questions from peer review of National Report; and Conclusions

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

International Nuclear Information System (INIS)

1978-03-01

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

LNG Safety Assessment Evaluation Methods

Energy Technology Data Exchange (ETDEWEB)

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

2015-05-01

Sandia National Laboratories evaluated published safety assessment methods across a variety of industries including Liquefied Natural Gas (LNG), hydrogen, land and marine transportation, as well as the US Department of Defense (DOD). All the methods were evaluated for their potential applicability for use in the LNG railroad application. After reviewing the documents included in this report, as well as others not included because of repetition, the Department of Energy (DOE) Hydrogen Safety Plan Checklist is most suitable to be adapted to the LNG railroad application. This report was developed to survey industries related to rail transportation for methodologies and tools that can be used by the FRA to review and evaluate safety assessments submitted by the railroad industry as a part of their implementation plans for liquefied or compressed natural gas storage ( on-board or tender) and engine fueling delivery systems. The main sections of this report provide an overview of various methods found during this survey. In most cases, the reference document is quoted directly. The final section provides discussion and a recommendation for the most appropriate methodology that will allow efficient and consistent evaluations to be made. The DOE Hydrogen Safety Plan Checklist was then revised to adapt it as a methodology for the Federal Railroad Administration’s use in evaluating safety plans submitted by the railroad industry.

49 CFR 659.19 - System safety program plan: contents.

Science.gov (United States)

2010-10-01

... implementation of the system safety program. (j) A description of the process used by the rail transit agency to... the rail transit agency to manage safety issues. (d) The process used to control changes to the system... hazard management program. (n) A description of the process used for facilities and equipment safety...

Risk-informed decision making a keystone in advanced safety assessment

International Nuclear Information System (INIS)

Reinhart, M.

2007-01-01

Probabilistic Safety Assessment (PSA) has provided extremely valuable complementary insight, perspective, comprehension, and balance to deterministic nuclear reactor safety assessment. This integrated approach of risk-informed management and decision making has been called Risk-Informed Decision Making (RIDM). RIDM provides enhanced safety, reliability, operational flexibility, reduced radiological exposure, and improved fiscal economy. Applications of RIDM continuously increase. Current applications are in the areas of design, construction, licensing, operations, and security. Operational phase safety applications include the following: technical specifications improvement, risk-monitors and configuration control, maintenance planning, outage planning and management, in-service inspection, inservice testing, graded quality assurance, reactor oversight and inspection, inspection finding significance determination, operational events assessment, and rulemaking. Interestingly there is a significant spectrum of approaches, methods, programs, controls, data bases, and standards. The quest of many is to assimilate the full compliment of PSA and RIDM information and to achieve a balanced international harmony. The goal is to focus the best of the best, so to speak, for the benefit of all. Accordingly, this presentation will address the principles, benefits, and applications of RIDM. It will also address some of the challenges and areas to improve. Finally it will highlight efforts by the IAEA and others to capture the international thinking, experience, successes, challenges, and lessons in RIDM. (authors)

Progress of nuclear safety research-2004

International Nuclear Information System (INIS)

Anoda, Yoshinari; Ebine, Noriya; Chuto, Toshinori; Sato, Satoshi; Ishikawa, Jun; Yamamoto, Toshihiro; Munakata, Masahiro; Asakura, Toshihide; Yamaguchi, Tetsuji; Kida, Takashi; Matsui, Hiroki; Haneishi, Akihiro; Araya, Fumimasa

2005-03-01

JAERI is conducting nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Annual Plan for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI are the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI has conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI has taken a responsible role by providing technical experts and investigation for assistance to the government or local public body. This report summarizes the nuclear safety research activities of JAERI from April 2002 through March 2004 and utilized facilities. (author)

Progress in Nuclear Safety Reform of TEPCO

International Nuclear Information System (INIS)

Kawano, A.

2016-01-01

On March 29, 2014, TEPCO issued the Nuclear Safety Reform Plan describing the background cause of our Fukushima Nuclear Accident and our plan to challenge organizational and cultural change to avoid recurrence of such a tragic accident and to pursue the excellence in safety. This report will reflect that background cause with some specific examples and introduce how we are currently implementing this reform plan.

Development of a Reality-Based Multimedia Case Study Teaching Method and Its Effect on Students' Planned Food Safety Behaviors

Science.gov (United States)

Alberts, Caitlin M.; Stevenson, Clinton D.

2017-01-01

There is opportunity to decrease the frequency of foodborne illnesses by improving food safety competencies and planned behaviors of college students before they begin careers in the food industry. The objectives of this study were to (1) develop a multimedia case study teaching method that provides real world context for food science education;…

Safety in urban environment and emergency notice boards

International Nuclear Information System (INIS)

Confortini, Claudia; Tira, Maurizio

2008-01-01

Reliable and safe urban system conditions have to be a crucial goal of ordinary planning activities. Among planning goals, priority must be given to indications relating to the safety levels to be achieved and to the amount of resources to be directed towards reducing the vulnerability of urban systems and therefore of the measures to be taken. Uban vulnerability cannot in fact be reduced to the sum of the vulnerability of single buildings or to the physical vulnerability of its various components. This research work consists of identifying those urban sub-areas that are important for safety in relation to natural risks, ambits that should be highlighted by means of permanent emergency notice boards/billboards. What are the hazard notices relating to all natural hazards and related risks? Where are they located? Are they clear and straightforward so that all residents and visitors are able to understand them, as it is already the case for road signs (or at least it should be)? What urban sub-areas are worth highlighting in relation to natural risks, acting for example as escape routes or meeting points? How is information for the public managed in order that people are immediately, easily and regularly notified? What is the relation of such signals to ordinary traffic signals? Research into the state of the art of permanent notice boards/billboards of this type, currently distinguished only by sporadic and local initiatives, aims at carrying out a census of and recognizing urban elements already considered as important for reducing the vulnerability of the urban system to different natural calamities and at providing new highlights as regards the identification of new ones. The next step is to work out a decision and common-language strategy for planning these elements and for their adequate signposting, so as to be able to live in the urban environment with awareness, safety and confidence, including with respect to more remote and therefore often neglected

Methods for Reducing Normal Tissue Complication Probabilities in Oropharyngeal Cancer: Dose Reduction or Planning Target Volume Elimination

Energy Technology Data Exchange (ETDEWEB)

Samuels, Stuart E.; Eisbruch, Avraham; Vineberg, Karen; Lee, Jae; Lee, Choonik; Matuszak, Martha M.; Ten Haken, Randall K.; Brock, Kristy K., E-mail: kbrock@med.umich.edu

2016-11-01

Purpose: Strategies to reduce the toxicities of head and neck radiation (ie, dysphagia [difficulty swallowing] and xerostomia [dry mouth]) are currently underway. However, the predicted benefit of dose and planning target volume (PTV) reduction strategies is unknown. The purpose of the present study was to compare the normal tissue complication probabilities (NTCP) for swallowing and salivary structures in standard plans (70 Gy [P70]), dose-reduced plans (60 Gy [P60]), and plans eliminating the PTV margin. Methods and Materials: A total of 38 oropharyngeal cancer (OPC) plans were analyzed. Standard organ-sparing volumetric modulated arc therapy plans (P70) were created and then modified by eliminating the PTVs and treating the clinical tumor volumes (CTVs) only (C70) or maintaining the PTV but reducing the dose to 60 Gy (P60). NTCP dose models for the pharyngeal constrictors, glottis/supraglottic larynx, parotid glands (PGs), and submandibular glands (SMGs) were analyzed. The minimal clinically important benefit was defined as a mean change in NTCP of >5%. The P70 NTCP thresholds and overlap percentages of the organs at risk with the PTVs (56-59 Gy, vPTV{sub 56}) were evaluated to identify the predictors for NTCP improvement. Results: With the P60 plans, only the ipsilateral PG (iPG) benefited (23.9% vs 16.2%; P<.01). With the C70 plans, only the iPG (23.9% vs 17.5%; P<.01) and contralateral SMG (cSMG) (NTCP 32.1% vs 22.9%; P<.01) benefited. An iPG NTCP threshold of 20% and 30% predicted NTCP benefits for the P60 and C70 plans, respectively (P<.001). A cSMG NTCP threshold of 30% predicted for an NTCP benefit with the C70 plans (P<.001). Furthermore, for the iPG, a vPTV{sub 56} >13% predicted benefit with P60 (P<.001) and C70 (P=.002). For the cSMG, a vPTV{sub 56} >22% predicted benefit with C70 (P<.01). Conclusions: PTV elimination and dose-reduction lowered the NTCP of the iPG, and PTV elimination lowered the NTCP of the cSMG. NTCP thresholds and the

Safety Evakuation Of Triga-2000 Reactor Operation Viewed From Safety Culture

International Nuclear Information System (INIS)

Karliana, Itjeu

2001-01-01

The safety evaluation activities of TRIGA-2000 operation viewed from safety culture performed by questioners data collected from the operators and supervisor site of TRIGA-2000 P3TN, Bandung. There are 9 activity aspects surveyed, for instant to avail the policy of safety from their chairman, safety management, education and training, emergency aids planning, safety consultancy, accident information, safety analysis, safety devices, safety and occupational health. The surveying undertaken by filling the questioner that containing of 9 activity aspects and 20 samples of employees. The safety evaluation results' of the operation personnel in TRIGA-2000 P3TN are good implemented by both the operators and supervisors should be improve and attention need to provide the equipment's. The education and training especially for safety refreshment must be performing

Safety research needs for Russian-designed reactors. Requirements situation

International Nuclear Information System (INIS)

Brown, R. Allan; Holmstrom, Heikki; Reocreux, Michel; Schulz, Helmut; Liesch, Klaus; Santarossa, Giampiero; Hayamizu, Yoshitaka; Asmolov, Vladimir; Bolshov, Leonid; Strizhov, Valerii; Bougaenko, Sergei; Nikitin, Yuri N.; Proklov, Vladimir; Potapov, Alexandre; Kinnersly, Stephen R.; Voronin, Leonid M.; Honekamp, John R.; Frescura, Gianni M.; Maki, Nobuo; Reig, Javier; ); Bekjord, Eric S.; Rosinger, Herbert E.

1998-01-01

In June 1995, an OECD Support Group was set up to perform a broad study of the safety research needs of Russian-designed reactors. The emphasis of the study is on the VVER-type reactors in part because of the larger base of knowledge within the NEA Member countries related to LWRs. For the RBMKs, the study does not make the judgement that such reactors can be brought to acceptable levels of safety but focuses on near term efforts that can contribute to reducing the risk to the public. The need for the safety research must be evaluated in context of the lifetime of the reactors. The principal outcome of the work of the Support Group is the identification of a number of research topics which the members believe should receive priority attention over the next several years if risk levels are to be reduced and public safety enhanced. These appear in the Conclusions and Recommendations section of the report, and are the following: - The most important near-term need for VVER and RBMK safety research is to establish a sound technical basis for the emergency operating procedures used by the plant staff to prevent or halt the progression of accidents (i.e., Accident Management) and for plant safety improvements. - Co-operation of Western and Eastern experts should help to avoid East-West know-how gaps in the future, as safety technology continues to improve. - Safety research in Eastern countries will make an important contribution to public safety as it has in OECD countries. - RBMK safety research, including verification of codes, starts from a smaller base of experience than VVER, and is at an earlier stage of development. Technical Conclusions: - Research to improve human performance and operational safety of VVER and RBMK plants is extremely important. - VVER thermal-hydraulic and reactor physics research should focus on full validation of codes to VVER-specific features, and on extension of experimental data base. - Methods of assessing VVER pressure boundary