Lessons learned in the implementation of Integrated Safety Management at DOE Order Compliance Sites vs Necessary and Sufficient Sites

International Nuclear Information System (INIS)

Hill, R.L.

2000-01-01

This paper summarizes the development and implementation of Integrated Safety Management (ISM) at an Order Compliance Site (Savannah River Site) and a Necessary and Sufficient Site (Nevada Test Site). A discussion of each core safety function of ISM is followed by an example from an Order Compliance Site and a Necessary and Sufficient Site. The Savannah River Site was the first DOE site to have a DOE Headquarters-validated and approved ISM System. The NTS is beginning the process of verification and validation. This paper defines successful strategies for integrating Environment, Safety, and Health management into work under various scenarios

Application of the Integrated Site and Environment Data Management System for LILW Disposal Site

International Nuclear Information System (INIS)

Lee, Ji Hoon; Lee, Eun Yong; Kim, Chang Lak

2007-01-01

During the last five years, Site Information and Total Environmental data management System(SITES) has been developed. SITES is an integrated program for overall data acquisition, environmental monitoring, and safety analysis. SITES is composed of three main modules, such as site database system (SECURE), safety assessment system (SAINT) and environmental monitoring system (SUDAL). In general, for the safe management of radioactive waste repository, the information of site environment should be collected and managed systematically from the initial site survey. For this, SECURE module manages its data for the site characterization, environmental information, and radioactive environmental information etc. The purpose of SAINT module is to apply and analyze the data from SECURE. SUDAL is developed for environmental monitoring of the radioactive waste repository. Separately, it is ready to open to the public for offering partial information

Environment, Safety and Health Progress Assessment of the Argonne Illinois Site

Energy Technology Data Exchange (ETDEWEB)

1993-11-01

This report documents the results of the US Department of Energy (DOE) Environment, Safety and Health (ES&H) Progress Assessment of the Argonne Illinois Site (AIS), near Chicago, Illinois, conducted from October 25 through November 9, 1993. During the Progress Assessment, activities included a selective review of the ES&H management systems and programs with principal focus on the DOE Office of Energy Research (ER); CH, which includes the Argonne Area Office; the University of Chicago; and the contractor`s organization responsible for operation of Argonne National Laboratory (ANL). The ES&H Progress Assessments are part of DOE`s continuing effort to institutionalize line management accountability and the self-assessment process throughout DOE and its contractor organizations. The purpose of the AIS ES&H Progress Assessment was to provide the Secretary of Energy, senior DOE managers, and contractor management with concise independent information on the following: change in culture and attitude related to ES&H activities; progress and effectiveness of the ES&H corrective actions resulting from the previous Tiger Team Assessment; adequacy and effectiveness of the ES&H self-assessment process of the DOE line organizations, the site management, and the operating contractor; and effectiveness of DOE and contractor management structures, resources, and systems to effectively address ES&H problems and new ES&H initiatives.

Environment, Safety and Health Progress Assessment of the Argonne Illinois Site

International Nuclear Information System (INIS)

1993-11-01

This report documents the results of the US Department of Energy (DOE) Environment, Safety and Health (ES ampersand H) Progress Assessment of the Argonne Illinois Site (AIS), near Chicago, Illinois, conducted from October 25 through November 9, 1993. During the Progress Assessment, activities included a selective review of the ES ampersand H management systems and programs with principal focus on the DOE Office of Energy Research (ER); CH, which includes the Argonne Area Office; the University of Chicago; and the contractor's organization responsible for operation of Argonne National Laboratory (ANL). The ES ampersand H Progress Assessments are part of DOE's continuing effort to institutionalize line management accountability and the self-assessment process throughout DOE and its contractor organizations. The purpose of the AIS ES ampersand H Progress Assessment was to provide the Secretary of Energy, senior DOE managers, and contractor management with concise independent information on the following: change in culture and attitude related to ES ampersand H activities; progress and effectiveness of the ES ampersand H corrective actions resulting from the previous Tiger Team Assessment; adequacy and effectiveness of the ES ampersand H self-assessment process of the DOE line organizations, the site management, and the operating contractor; and effectiveness of DOE and contractor management structures, resources, and systems to effectively address ES ampersand H problems and new ES ampersand H initiatives

Studies on Labour Safety in Construction Sites

Directory of Open Access Journals (Sweden)

S. Kanchana

2015-01-01

Full Text Available Construction industry has accomplished extensive growth worldwide particularly in past few decades. For a construction project to be successful, safety of the structures as well as that of the personnel is of utmost importance. The safety issues are to be considered right from the design stage till the completion and handing over of the structure. Construction industry employs skilled and unskilled labourers subject to construction site accidents and health risks. A proper coordination between contractors, clients, and workforce is needed for safe work conditions which are very much lacking in Indian construction companies. Though labour safety laws are available, the numerous accidents taking place at construction sites are continuing. Management commitment towards health and safety of the workers is also lagging. A detailed literature study was carried out to understand the causes of accidents, preventive measures, and development of safe work environment. This paper presents the results of a questionnaire survey, which was distributed among various categories of construction workers in Kerala region. The paper examines and discusses in detail the total working hours, work shifts, nativity of the workers, number of accidents, and type of injuries taking place in small and large construction sites.

Studies on Labour Safety in Construction Sites

Science.gov (United States)

Kanchana, S.; Sivaprakash, P.; Joseph, Sebastian

2015-01-01

Construction industry has accomplished extensive growth worldwide particularly in past few decades. For a construction project to be successful, safety of the structures as well as that of the personnel is of utmost importance. The safety issues are to be considered right from the design stage till the completion and handing over of the structure. Construction industry employs skilled and unskilled labourers subject to construction site accidents and health risks. A proper coordination between contractors, clients, and workforce is needed for safe work conditions which are very much lacking in Indian construction companies. Though labour safety laws are available, the numerous accidents taking place at construction sites are continuing. Management commitment towards health and safety of the workers is also lagging. A detailed literature study was carried out to understand the causes of accidents, preventive measures, and development of safe work environment. This paper presents the results of a questionnaire survey, which was distributed among various categories of construction workers in Kerala region. The paper examines and discusses in detail the total working hours, work shifts, nativity of the workers, number of accidents, and type of injuries taking place in small and large construction sites. PMID:26839916

Site Environmental Report for 2006. Volume I, Environment, Health, and Safety Division

Energy Technology Data Exchange (ETDEWEB)

None

2007-09-30

Each year, Ernest Orlando Lawrence Berkeley National Laboratory prepares an integrated report on its environmental programs to satisfy the requirements of United States Department of Energy Order 231.1A, Environment, Safety, and Health Reporting.1 The Site Environmental Report for 2006 summarizes Berkeley Lab’s environmental management performance, presents environmental monitoring results, and describes significant programs for calendar year 2006. (Throughout this report, Ernest Orlando Lawrence Berkeley National Laboratory is referred to as “Berkeley Lab,” “the Laboratory,” “Lawrence Berkeley National Laboratory,” and “LBNL.”) The report is separated into two volumes. Volume I is organized into an executive summary followed by six chapters that contain an overview of the Laboratory, a discussion of the Laboratory’s environmental management system, the status of environmental programs, and summarized results from surveillance and monitoring activities. Volume II contains individual data results from surveillance and monitoring activities.

Nuclear installations sites safety

International Nuclear Information System (INIS)

Barber, P.; Candes, P.; Duclos, P.; Doumenc, A.; Faure, J.; Hugon, J.; Mohammadioun, B.

1988-11-01

This report is divided into ten parts bearing: 1 Safety analysis procedures for Basis Nuclear Installations sites (BNI) in France 2 Site safety for BNI in France 3 Industrial and transport activities risks for BNI in France 4 Demographic characteristics near BNI sites in France 5 Meteorologic characteristics of BNI sites in France 6 Geological aspects near the BNI sites in France 7 Seismic studies for BNI sites in France 8 Hydrogeological aspects near BNI sites in France 9 Hydrological aspects near BNI sites in France 10 Ecological and radioecological studies of BNI sites in France [fr

Strategies for effective management of health and safety in confined site construction

Directory of Open Access Journals (Sweden)

John Spillane

2013-12-01

Full Text Available Purpose: The overall aim of this research is to identify and catalogue the numerous managerial strategies for effective management of health and safety on a confined, urban, construction site. Design/Methodology/Approach: This is achieved by utilising individual interviews, focus groups discussion on selected case studies of confined construction sites, coupled with a questionnaire survey. Findings: The top five key strategies include (1 Employ safe system of work plans to mitigate personnel health and safety issues; (2 Inform personnel, before starting on-site, of the potential issues using site inductions; (3 Effective communication among site personnel; (4 Draft and implement an effective design site layout prior to starting on-site; and (5 Use of banksman (traffic co-ordinator to segregate personnel from vehicular traffic. Practical Implication: The construction sector is one of the leading industries in accident causation and with the continued development and regeneration of our urban centres, confined site construction is quickly becoming the norm - an environment which only fuels accident creation within the construction sector. Originality/Value: This research aids on-site management that requires direction and assistance in the identification and implementation of key strategies for the management of health and safety, particularly in confined construction site environments.

PERCEPTION OF BUILDING CONSTRUCTION WORKERS TOWARDS SAFETY, HEALTH AND ENVIRONMENT

Directory of Open Access Journals (Sweden)

C.R. CHE HASSAN

2007-12-01

Full Text Available The construction industry is known as one of the most hazardous activities. Therefore, safety on the job site is an important aspect with respect to the overall safety in construction. This paper assesses the safety level perception of the construction building workers towards safety, health and environment on a construction job site in Kuala Lumpur, Malaysia. The above study was carried out by choosing 5 selected large building construction projects and 5 small building construction projects respectively in and around Kuala Lumpur area. In the present study, an exhaustive survey was carried out in these 10 project site areas using a standard checklist and a detailed developed questionnaire. The checklist comprised 17 divisions of safety measurements which are considered and perceived to be important from the safety point of view and was assessed based on the score obtained. The questionnaire comprised the general information with 36 safety attitude statements on a 1-5 Likert scale which was distributed to 100 construction workers. The results of the checklist show the difference of safety levels between the large and small projects. The study revealed that the large projects shown a high and consistent level in safety while the small projects shown a low and varied safety levels. The relationship between the factors can be obtained from the questionnaire. They are organizational commitment, factor influencing communication among workmates, worker related factors, personal role and supervisors’ role factors, obstacles to safety and safe behavior factors and management commitment at all levels in line with the management structure and risk taking behavioral factors. The findings of the present study revealed invaluable indications to the construction managers especially in improving the construction workers’ attitude towards safety, health and environment and hence good safety culture in the building construction industries.

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.

Nuclear power: Siting and safety

International Nuclear Information System (INIS)

Openshaw, S.

1986-01-01

By 2030, half, or even two-thirds, of all electricity may be generated by nuclear power. Major reactor accidents are still expected to be rare occurrences, but nuclear safety is largely a matter of faith. Terrorist attacks, sabotage, and human error could cause a significant accident. Reactor siting can offer an additional, design-independent margin of safety. Remote geographical sites for new plants would minimize health risks, protect the industry from negative changes in public opinion concerning nuclear energy, and improve long-term public acceptance of nuclear power. U.K. siting practices usually do not consider the contribution to safety that could be obtained from remote sites. This book discusses the present trends of siting policies of nuclear power and their design-independent margin of safety

Safety culture aspects of managing for safety. Experience of a large nuclear reprocessing site

International Nuclear Information System (INIS)

Rycraft, H.S.

1996-01-01

The Nuclear Industry is going through turbulent times both in terms of public acceptance and business issues. Safety is one area which impacts on whether the business is allowed to continue, and how an organisation organizes itself. The need to cut costs to make nuclear power a viable energy resource, has forced the nuclear utilities to review manning policies, and management style, and in particular how to maintain safety standards during a period of change, and ultimately support continuing improvement of standards. The shrinking workforce requires a new style of management, one that depends more on the people of the organisation taking responsibility for safety at all levels of the organisation. Not only personal safety but the safety of their colleagues, general public and the environment. The safety culture of an organisation is indivisible from the company culture, each aspect of a culture influences the whole and so the balance between business, safety and quality, has to be managed. BNFL provides a full fuel cycle service to nuclear power plants, and associated services to many national and international organisations. The following notes are taken from the work carried out in the company, and mostly at the Nuclear Reprocessing and Waste storage Site at Sellafield, based in the North West of England. Following the recent re-organisation, the site now employs 6200 people and has a further 1500 contractors working on construction activities on the site. Activities on the site range from remote handling to hands on tasks, involving highly active materials to low level waste. (author)

Environment, safety and health

International Nuclear Information System (INIS)

Luzianovich, L.Ch.; Fardeau, J.C.; Darras, M.

2000-01-01

Environment, safety and health were the three topics discussed by the WOC 8 working group of the worldwide gas congress. Environment protection has become a major preoccupation and constraint for natural gas industry at the dawn of the new millennium. It is closely linked with the safety of installation and with the health of workmen who exploit or use natural gas energy: methane emissions, health and safety in gas industry, environment management and evaluation. (J.S.)

Improving construction site safety through leader-based verbal safety communication.

Science.gov (United States)

Kines, Pete; Andersen, Lars P S; Spangenberg, Soren; Mikkelsen, Kim L; Dyreborg, Johnny; Zohar, Dov

2010-10-01

The construction industry is one of the most injury-prone industries, in which production is usually prioritized over safety in daily on-site communication. Workers have an informal and oral culture of risk, in which safety is rarely openly expressed. This paper tests the effect of increasing leader-based on-site verbal safety communication on the level of safety and safety climate at construction sites. A pre-post intervention-control design with five construction work gangs is carried out. Foremen in two intervention groups are coached and given bi-weekly feedback about their daily verbal safety communications with their workers. Foremen-worker verbal safety exchanges (experience sampling method, n=1,693 interviews), construction site safety level (correct vs. incorrect, n=22,077 single observations), and safety climate (seven dimensions, n=105 questionnaires) are measured over a period of up to 42 weeks. Baseline measurements in the two intervention and three control groups reveal that foremen speak with their workers several times a day. Workers perceive safety as part of their verbal communication with their foremen in only 6-16% of exchanges, and the levels of safety at the sites range from 70-87% (correct observations). Measurements from baseline to follow-up in the two intervention groups reveal that safety communication between foremen and workers increases significantly in one of the groups (factor 7.1 increase), and a significant yet smaller increase is found when the two intervention groups are combined (factor 4.6). Significant increases in the level of safety are seen in both intervention groups (7% and 12% increases, respectively), particularly in regards to 'access ways' and 'railings and coverings' (39% and 84% increases, respectively). Increases in safety climate are seen in only one of the intervention groups with respect to their 'attention to safety.' No significant trend changes are seen in the three control groups on any of the three measures

Studies on environment safety and application of advanced reactor for inland nuclear power plants

International Nuclear Information System (INIS)

Wei, L.; Jie, L.

2014-01-01

To study environment safety assessment of inland nuclear power plants (NPPs), the impact of environment safety under the normal operation was researched and the environment risk of serious accidents was analyzed. Moreover, the requirements and relevant provisions of site selection between international nuclear power plant and China's are comparatively studied. The conclusion was that the environment safety assessment of inland and coastal nuclear power plant have no essential difference; the advanced reactor can meet with high criteria of environment safety of inland nuclear power plants. In this way, China is safe and feasible to develop inland nuclear power plant. China's inland nuclear power plants will be as big market for advanced reactor. (author)

Optimisation (sampling strategies and analytical procedures) for site specific environment monitoring at the areas of uranium production legacy sites in Ukraine - 59045

International Nuclear Information System (INIS)

Voitsekhovych, Oleg V.; Lavrova, Tatiana V.; Kostezh, Alexander B.

2012-01-01

There are many sites in the world, where Environment are still under influence of the contamination related to the Uranium production carried out in past. Author's experience shows that lack of site characterization data, incomplete or unreliable environment monitoring studies can significantly limit quality of Safety Assessment procedures and Priority actions analyses needed for Remediation Planning. During recent decades the analytical laboratories of the many enterprises, currently being responsible for establishing the site specific environment monitoring program have been significantly improved their technical sampling and analytical capacities. However, lack of experience in the optimal site specific sampling strategy planning and also not enough experience in application of the required analytical techniques, such as modern alpha-beta radiometers, gamma and alpha spectrometry and liquid-scintillation analytical methods application for determination of U-Th series radionuclides in the environment, does not allow to these laboratories to develop and conduct efficiently the monitoring programs as a basis for further Safety Assessment in decision making procedures. This paper gives some conclusions, which were gained from the experience establishing monitoring programs in Ukraine and also propose some practical steps on optimization in sampling strategy planning and analytical procedures to be applied for the area required Safety assessment and justification for its potential remediation and safe management. (authors)

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

Safety assessment input for site selection - the Swedish example - 59031

International Nuclear Information System (INIS)

Andersson, Johan

2012-01-01

Svensk Kaernbraenslehantering AB (SKB) has performed comprehensive investigations of two candidate sites for a final repository for Sweden's spent nuclear fuel. In March 2011 SKB decided to submit licence applications for a final repository at Forsmark. Before selection, SKB stated that the site that offers the best prospects for achieving long-term safety in practice would be selected. Based on experiences previous safety assessments, a number of issues related to long-term safety need to be considered in the context of site comparison. The factors include sensitivity to climate change such as periods of permafrost and glaciations, rock mechanics evolution including the potential for thermally induced spalling and sensitivity to potential future earthquakes, current and future groundwater flow, evolution of groundwater composition and proximity to mineral resources. Each of these factors related to long-term safety for the two candidate sites is assessed in a comparative analysis of site characteristics. The assessment also considers differences in biosphere conditions and in the confidence of the site descriptions. The comparison is concluded by an assessment on how the identified differences would affect the estimated radiological risk from a repository located at either of the sites. The assessment concludes that there are a number of safety related site characteristics for which the analyses do not show any decisive differences in terms of implications on safety, between the sites Forsmark and Laxemar. However, the frequency of water conducting fractures at repository depth is much smaller at Forsmark than at Laxemar. This difference, in turn, affects the future stability of the current favourable groundwater composition, which combined with the much higher flows at Laxemar would, for the current repository design, lead to a breach in the safety functions for the buffer and the canister for many more deposition positions at Laxemar than at Forsmark. Thereby

Meteorological events in site evaluation for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

This Safety Guide provides recommendations and guidance on conducting hazard assessments of extreme and rare meteorological phenomena. It is of interest to safety assessors and regulators involved in the licensing process as well as to designers of nuclear power plants. This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. It supplements the IAEA Safety Requirements publication on Site Evaluation for Nuclear Facilities which is to supersede the Code on the Safety of Nuclear Power Plants: Siting, Safety Series No. 50-C-S (Rev. 1), IAEA, Vienna (1988). The present Safety Guide supersedes two earlier Safety Guides: Safety Series No. 50-SG-S11A (1981) on Extreme Meteorological Events in Nuclear Power Plant Siting, Excluding Tropical Cyclones and Safety Series No. 50-SG-S11B (1984) on Design Basis Tropical Cyclone for Nuclear Power Plants. The purpose of this Safety Guide is to provide recommendations and guidance on conducting hazard assessments of extreme and rare meteorological phenomena. This Safety Guide provides interpretation of the Safety Requirements publication on Site Evaluation for Nuclear Facilities and guidance on how to fulfil these requirements. It is aimed at safety assessors or regulators involved in the licensing process as well as designers of nuclear power plants, and provides them with guidance on the methods and procedures for analyses that support the assessment of the hazards associated with extreme and rare meteorological events. This Safety Guide discusses the extreme values of meteorological variables and rare meteorological phenomena, as well as their rates of occurrence, according to the following definitions: (a) Extreme values of meteorological variables such as air temperature and wind speed characterize the meteorological or climatological environment. And (b) Rare meteorological phenomena

Spatial distribution of tritium in the Rawatbhata Rajasthan site environment

International Nuclear Information System (INIS)

GilI, Rajpal; Tiwari, S.N.; Gocher, A.K.; Ravi, P.M.; Tripathi, R.M.

2014-01-01

Tritium is one of the most environmentally mobile radionuclides and hence has high potential for migration into the different compartments of environment. Tritium from nuclear facilities at RAPS site is released into the environment through 93 m and 100 m high stack mainly as tritiated water (HTO). The released tritium undergoes dilution and dispersion and then follows the ecological pathway of water molecule. Environmental Survey Laboratory of Health Physics Division, Bhabha Atomic Research Centre (BARC), located at Rajasthan Atomic Power Station (RAPS) site is continuously monitoring the concentration of tritium in the environment to ensure the public safety. Atmospheric tritium activity during the period (2009-2013) was measured regularly around Rajasthan Atomic Power Station (RAPS). Data collected showed a large variation of H-3 concentration in air fluctuating in the range of 0.43 - 5.80 Bq.m -3 at site boundary of 1.6 km. This paper presents the result of analyses of tritium in atmospheric environment covering an area up to 20 km radius around RAPS site. Large number of air moisture samples were collected around the RAPS site, for estimating tritium in atmospheric environment to ascertain the atmospheric dispersion and computation of radiation dose to the public

Environment, Safety & Health at SLAC

Science.gov (United States)

and safety of our staff, the community, and the environment as we carry out our scientific mission. We integral to each job. As stewards of our land, SLAC also seeks to minimize pollution to our environment and to protect our resources and biota. See the SLAC Environment, Safety and Health Policy for more

Environment, Health, and Safety - Construction Subcontractors Documents |

Science.gov (United States)

NREL Environment, Health, and Safety - Construction Subcontractors Documents Environment Environment, Health and Safety (EH&S) requirements are understood by construction subcontractors and with these requirements before submitting proposals and/or environment, health and safety plans for the

Comparative analysis of safety related site characteristics

International Nuclear Information System (INIS)

Andersson, Johan

2010-12-01

This document presents a comparative analysis of site characteristics related to long-term safety for the two candidate sites for a final repository for spent nuclear fuel in Forsmark (municipality of Oesthammar) and in Laxemar (municipality of Oskarshamn) from the point of view of site selection. The analyses are based on the updated site descriptions of Forsmark /SKB 2008a/ and Laxemar /SKB 2009a/, together with associated updated repository layouts and designs /SKB 2008b and SKB 2009b/. The basis for the comparison is thus two equally and thoroughly assessed sites. However, the analyses presented here are focussed on differences between the sites rather than evaluating them in absolute terms. The document serves as a basis for the site selection, from the perspective of long-term safety, in SKB's application for a final repository. A full evaluation of safety is made for a repository at the selected site in the safety assessment SR-Site /SKB 2011/, referred to as SR-Site main report in the following

Comparative analysis of safety related site characteristics

Energy Technology Data Exchange (ETDEWEB)

Andersson, Johan (ed.)

2010-12-15

This document presents a comparative analysis of site characteristics related to long-term safety for the two candidate sites for a final repository for spent nuclear fuel in Forsmark (municipality of Oesthammar) and in Laxemar (municipality of Oskarshamn) from the point of view of site selection. The analyses are based on the updated site descriptions of Forsmark /SKB 2008a/ and Laxemar /SKB 2009a/, together with associated updated repository layouts and designs /SKB 2008b and SKB 2009b/. The basis for the comparison is thus two equally and thoroughly assessed sites. However, the analyses presented here are focussed on differences between the sites rather than evaluating them in absolute terms. The document serves as a basis for the site selection, from the perspective of long-term safety, in SKB's application for a final repository. A full evaluation of safety is made for a repository at the selected site in the safety assessment SR-Site /SKB 2011/, referred to as SR-Site main report in the following

Information report on nuclear safety and radiation protection of the Tricastin AREVA site - Issue 2014. Figures and information about nuclear safety and radiation protection of the Tricastin AREVA site - Issue 2014

International Nuclear Information System (INIS)

2015-06-01

Published in compliance with the French code of the environment, this report first presents different aspects of the Areva's Tricastin site which comprises five basic nuclear installations or INBs, and seven ICPE (installation classified for environment protection). The activities are dedicated to uranium conversion, uranium enrichment, uranium chemistry, industrial services, and fuel manufacturing. The report presents this important industrial site, describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which occurred on this site and had to be declared, reports the management of releases by this site and the control of the environment. The next part addresses the management of the various wastes produced by the different installations present on this site. The management of other impacts is also reported. The last chapter reviews the actions undertaken in the field of transparency and information

Information report on nuclear safety and radiation protection of the Tricastin AREVA site - Issue 2013. Figures and information about nuclear safety and radiation protection of the Tricastin AREVA site - Issue 2013

International Nuclear Information System (INIS)

2014-06-01

Published in compliance with the French code of the environment, this report first presents different aspects of the Areva's Tricastin site which comprises five basic nuclear installations or INBs, and seven ICPE (installation classified for the protection of the environment). The activities are dedicated to uranium conversion, uranium enrichment, uranium chemistry, industrial services, and fuel manufacturing. The report presents this important industrial site, describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which occurred on this site and had to be declared, reports the management of releases by this site and the control of the environment. The next part addresses the management of the various wastes produced by the different installations present on this site. The management of other impacts is also reported. The last chapter reviews the actions undertaken in the field of transparency and information

Information report on nuclear safety and radiation protection of the Romans site - Issue 2014

International Nuclear Information System (INIS)

2015-06-01

In compliance with the French Code of the Environment, this annual document describes the arrangements regarding nuclear safety and radiation protection, reports incidents and accidents of nuclear safety and radiation protection which must be declared according to this Code and which occurred within the installation, as well as the actions undertaken to limit their development and the consequences for people health for the environment, describes the nature and results of measurements of radioactive and not radioactive releases by the installation in the environment, describes the nature and quantities of radioactive wastes which are warehoused on the installation site as well as measures to limit their volume and their impact on health and on the environment, notably in soils and waters. After a presentation of the AREVA plant located in Romans-sur-Isere which comprises two basic nuclear installations (INB) and where fuel assemblies are manufactured, the different parts of this report address the measures regarding nuclear safety and radiation protection, nuclear events according to the INES scale, the management of releases by the different installations of this site and the control of the environment, the management of radioactive wastes, and the actions undertaken regarding information and transparency. Recommendations of the CHSCT are also reported

Information report on nuclear safety and radiation protection of the Romans site - Issue 2012

International Nuclear Information System (INIS)

2013-06-01

In compliance with the French Code of the Environment, this annual document describes the arrangements regarding nuclear safety and radiation protection, reports incidents and accidents of nuclear safety and radiation protection which must be declared according to this Code and which occurred within the installation, as well as the actions undertaken to limit their development and the consequences for people health for the environment, describes the nature and results of measurements of radioactive and not radioactive releases by the installation in the environment, describes the nature and quantities of radioactive wastes which are warehoused on the installation site as well as measures to limit their volume and their impact on health and on the environment, notably in soils and waters. After a presentation of the AREVA plant located in Romans-sur-Isere which comprises two basic nuclear installations (INB) and where fuel assemblies are manufactured, the different parts of this report address the measures regarding nuclear safety and radiation protection, nuclear events according to the INES scale, the management of releases by the different installations of this site and the control of the environment, the management of radioactive wastes, and the actions undertaken regarding information and transparency. Recommendations of the CHSCT are also reported

Information report on nuclear safety and radiation protection of the Romans site - Issue 2013

International Nuclear Information System (INIS)

2014-06-01

In compliance with the French Code of the Environment, this annual document describes the arrangements regarding nuclear safety and radiation protection, reports incidents and accidents of nuclear safety and radiation protection which must be declared according to this Code and which occurred within the installation, as well as the actions undertaken to limit their development and the consequences for people health for the environment, describes the nature and results of measurements of radioactive and not radioactive releases by the installation in the environment, describes the nature and quantities of radioactive wastes which are warehoused on the installation site as well as measures to limit their volume and their impact on health and on the environment, notably in soils and waters. After a presentation of the AREVA plant located in Romans-sur-Isere which comprises two basic nuclear installations (INB) and where fuel assemblies are manufactured, the different parts of this report address the measures regarding nuclear safety and radiation protection, nuclear events according to the INES scale, the management of releases by the different installations of this site and the control of the environment, the management of radioactive wastes, and the actions undertaken regarding information and transparency. Recommendations of the CHSCT are also reported

Radioactive safety analysis and assessment of waste rock pile site in uranium tailings

International Nuclear Information System (INIS)

Liu Changrong; Liu Zehua; Wang Zhiyong; Zhou Xinghuo

2007-01-01

Based on theoretical calculation and in-situ test results, distribution and emissions of radioactive nuclides of uranium tailings impoundment and waste rock pile sites are analyzed in this paper. It is pointed out that 222 Rn is the main nuclide of uranium tailings impoundment and waste rock pile site. Also 222 Rn is the main source term of public dose. 222 Rn concentrations in the atmospheric environment around and individual dose to Rn gradually decrease with increasing distances to uranium tailings impoundment and waste rock pile site. Based on in-situ tests on five uranium tailings impoundment and waste rock pile sites, a decisive method and safety protection distance are presented, which can be used to guide the validation and design of radioactive safety protection in uranium tailings impoundment and waste rock pile sites. (authors)

New Reactor Siting in Finland, Hanhikivi Site in Pyhaejoki - STUK preliminary safety assessment

International Nuclear Information System (INIS)

Nevalainen, Janne

2013-01-01

STUK has performed a preliminary assessment of the Decision-in-Principle on the Fennovoima application. A variety of factors must be considered in the selection of a site, including effects of the site on the plant design and the effects of the plant on the site environment. These include external hazards, both natural and human-induced. Since this is a new site, an extensive siting process is followed, that can include an EIA. A site survey is performed to identify candidate sites, after investigating a large region and rejecting unsuitable sites. The remaining sites are then screened and compared on the basis of safety and other considerations to select one or more preferred sites. Natural hazards include geology, seismology, hydrology and meteorology. Offshore ice will be a particular hazard for this plant, since the site is on average only 1.5 m above sea level. The design basis earthquake corresponds to a return frequency of 100,000 years, with 50 % confidence. The existing sites in southern Finland used a design peak ground acceleration of 0.1 g with the ground response spectrum maximum at 10 Hz. The candidate sites in northern Finland will require a peak ground acceleration of 0.2 g with the ground response spectrum maximum at 25 Hz

Empirical estimation of school siting parameter towards improving children's safety

Science.gov (United States)

Aziz, I. S.; Yusoff, Z. M.; Rasam, A. R. A.; Rahman, A. N. N. A.; Omar, D.

2014-02-01

Distance from school to home is a key determination in ensuring the safety of hildren. School siting parameters are made to make sure that a particular school is located in a safe environment. School siting parameters are made by Department of Town and Country Planning Malaysia (DTCP) and latest review was on June 2012. These school siting parameters are crucially important as they can affect the safety, school reputation, and not to mention the perception of the pupil and parents of the school. There have been many studies to review school siting parameters since these change in conjunction with this ever-changing world. In this study, the focus is the impact of school siting parameter on people with low income that live in the urban area, specifically in Johor Bahru, Malaysia. In achieving that, this study will use two methods which are on site and off site. The on site method is to give questionnaires to people and off site is to use Geographic Information System (GIS) and Statistical Product and Service Solutions (SPSS), to analyse the results obtained from the questionnaire. The output is a maps of suitable safe distance from school to house. The results of this study will be useful to people with low income as their children tend to walk to school rather than use transportation.

SafetyAnalyst : software tools for safety management of specific highway sites

Science.gov (United States)

2010-07-01

SafetyAnalyst provides a set of software tools for use by state and local highway agencies for highway safety management. SafetyAnalyst can be used by highway agencies to improve their programming of site-specific highway safety improvements. SafetyA...

Site selection for deep geologic repositories - Consequences for society, economy and environment

International Nuclear Information System (INIS)

2010-03-01

In a few years, Switzerland will make the decision regarding site selection for geological underground repositories for the storage of radioactive wastes. Besides the safety issue, many citizens are interested in how such a repository will affect environment, economy and society in the selected site's region. This brochure summarizes the results of many studies on the socio-economic impacts of nuclear waste repositories. Radioactive wastes must be stored in such a way that mankind and environment are safely protected for a long period of time. How this goal may be achieved, is already known: geologic deep repositories warrant long-term safety. For the oncoming years in Switzerland the question is where the repository will be built. The search for an appropriate site for a repository in the proposed regions will launch discussions. Within the participative framework the regions may bring their requests. The demonstration of the safety of potential repository sites has the highest priority in the selection process. In the third procedural step additional rock investigations will be made. The socio-economic studies and the experience with existing plants show that radioactive waste management plants can be built and operated in good agreement with environmental requirements. The radioactive wastes in a deep underground repository are stored many hundred meters below the Earth's surface. There, they are isolated from our vital space. Technical barriers and the surrounding dense rock confinement prevent the release of radioactive materials into the environment. A deep repository has positive consequences for the regional economy. It increases trade and value creation and creates work places. The socio-economic impacts practically extend over one century, but strongly vary with time; they are the largest during the building period. High life quality and a positive population development in the selected site region are compatible with a deep repository. A fair and

Information report on nuclear safety and radiation protection of the Tricastin AREVA site, 2010 edition

International Nuclear Information System (INIS)

2010-01-01

This report presents the Tricastin site, the different arrangements concerning nuclear safety and radiation protection on this site, and recent nuclear events. It describes how site releases are managed and how the environment is controlled and monitored, how wastes are managed, and how other impacts are controlled. It finally presents the different actions regarding transparency and information

Health and Safety Procedures Manual for hazardous waste sites

Energy Technology Data Exchange (ETDEWEB)

Thate, J.E.

1992-09-01

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

Proceeding of Radiation Safety and Environment

International Nuclear Information System (INIS)

1996-01-01

Scientific Presentation of Radiation Safety and Environment was held on 20-21 august 1996 at Center of Research Atomic Energy Pasar Jum'at, Jakarta, Indonesia. Have presented 50 papers about Radiation Safety, dosimetry and standardization, environment protection and radiation effect

Safety aspects of siting

International Nuclear Information System (INIS)

Rosen, M.

1976-01-01

Outline of parameters to be considered in site selection, radiation safety, and mechanisms of radiation release. Radiation doses in tablular form for areas at various distances from the plant. (HP) [de

Hanford Site Environmental Safety and Health Fiscal Year 2001 Budget-Risk management summary

Energy Technology Data Exchange (ETDEWEB)

REEP, I.E.

1999-05-12

The Hanford Site Environment, Safety and Health (ES&H) Budget-Risk Management Summary report is prepared to support the annual request to sites in the U.S. Department of Energy (DOE) Complex by DOE, Headquarters. The request requires sites to provide supplementary crosscutting information related to ES&H activities and the ES&H resources that support these activities. The report includes the following: (1) A summary status of fiscal year (FY) 1999 ES&H performance and ES&H execution commitments; (2)Status and plans of Hanford Site Office of Environmental Management (EM) cleanup activities; (3) Safety and health (S&H) risk management issues and compliance vulnerabilities of FY 2001 Target Case and Below Target Case funding of EM cleanup activities; (4) S&H resource planning and crosscutting information for FY 1999 to 2001; and (5) Description of indirect-funded S&H activities.

Site safety requirements for high level waste disposal

International Nuclear Information System (INIS)

Chen Weiming; Wang Ju

2006-01-01

This paper outlines the content, status and trend of site safety requirements of International Atomic Energy Agency, America, France, Sweden, Finland and Japan. Site safety requirements are usually represented as advantageous vis-a-vis disadvantagous conditions, and potential advantage vis-a-vis disadvantage conditions, respectively in aspects of geohydrology, geochemistry, lithology, climate and human intrusion etc. Study framework and steps of site safety requirements for China are discussed under the view of systems science. (authors)

Information report on nuclear safety and radiation protection of the Tricastin AREVA site - Issue 2012

International Nuclear Information System (INIS)

2013-06-01

Published in compliance with the French code of the environment, this report first presents different aspects of the Areva's Tricastin site which comprises five basic nuclear installations or INBs, and seven ICPE (installation classified for the protection of the environment). The activities are dedicated to uranium conversion, uranium enrichment, uranium chemistry, industrial services, and fuel manufacturing. The report presents this important industrial site, describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which occurred on this site and had to be declared, reports the management of releases by this site and the control of the environment. The next part addresses the management of the various wastes produced by the different installations present on this site. The management of other impacts is also reported. The last chapter reviews the actions undertaken in the field of transparency and information

Safety Oversight of Decommissioning Activities at DOE Nuclear Sites

International Nuclear Information System (INIS)

Zull, Lawrence M.; Yeniscavich, William

2008-01-01

The Defense Nuclear Facilities Safety Board (Board) is an independent federal agency established by Congress in 1988 to provide nuclear safety oversight of activities at U.S. Department of Energy (DOE) defense nuclear facilities. The activities under the Board's jurisdiction include the design, construction, startup, operation, and decommissioning of defense nuclear facilities at DOE sites. This paper reviews the Board's safety oversight of decommissioning activities at DOE sites, identifies the safety problems observed, and discusses Board initiatives to improve the safety of decommissioning activities at DOE sites. The decommissioning of former defense nuclear facilities has reduced the risk of radioactive material contamination and exposure to the public and site workers. In general, efforts to perform decommissioning work at DOE defense nuclear sites have been successful, and contractors performing decommissioning work have a good safety record. Decommissioning activities have recently been completed at sites identified for closure, including the Rocky Flats Environmental Technology Site, the Fernald Closure Project, and the Miamisburg Closure Project (the Mound site). The Rocky Flats and Fernald sites, which produced plutonium parts and uranium materials for defense needs (respectively), have been turned into wildlife refuges. The Mound site, which performed R and D activities on nuclear materials, has been converted into an industrial and technology park called the Mound Advanced Technology Center. The DOE Office of Legacy Management is responsible for the long term stewardship of these former EM sites. The Board has reviewed many decommissioning activities, and noted that there are valuable lessons learned that can benefit both DOE and the contractor. As part of its ongoing safety oversight responsibilities, the Board and its staff will continue to review the safety of DOE and contractor decommissioning activities at DOE defense nuclear sites

75 FR 73946 - Worker Safety and Health Program: Safety Conscious Work Environment

Science.gov (United States)

2010-11-30

... Environment AGENCY: Office of the General Counsel, Department of Energy (DOE). ACTION: Notice of denial of... Nuclear Regulatory Commission's ``Safety-Conscious Work Environment'' guidelines as a model. DOE published.... Second, not only would instituting a ``Safety-Conscious Work Environment'' by regulation be redundant...

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.

Environment, health and safety guiding principles

International Nuclear Information System (INIS)

1997-06-01

The Canadian Energy Pipeline Association (CEPA) has taken a leadership role in promoting responsible planning, management and work practices that meet the pipeline industry's environment, health and safety objectives. This brochure contains CEPA's environment, health and safety statement. It lists the guiding principles developed and endorsed by CEPA and its member companies in support of protecting the environment and the health and safety of its employees and the public. The 11 CEPA member companies are: Alberta Natural Gas Company Ltd., ATCO Gas Services Ltd., Foothills Pipe Lines Ltd., Interprovincial Pipe Line Inc., NOVA Gas Transmission Limited, TransGas Limited, Trans Mountain Pipe Line Company Ltd., Trans-Northern Pipelines Inc., Trans Quebec and Maritimes Pipeline Inc., and Westcoast Energy Inc

Dispersion of radioactive material in air and water and consideration of population distribution in site evaluation for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

Dispersion of Radioactive Material in Relation to Nuclear Power Plant Siting (Safety Series No. 50-SG-S6 (1985)). And Nuclear Power Plant Siting: Hydrogeological Aspects (Safety Series No. 50-SG-S7 (1984)). Radioactive materials discharged from a nuclear power plant might reach the public and might contaminate the environment in the region by way of both direct and indirect pathways. The objective of this Safety Guide is to provide guidance on the studies and investigations necessary for assessing the impact of a nuclear power plant on humans and the environment. It also provides guidance on the feasibility of an effective emergency response plan, in consideration of all the relevant site features. This Safety Guide provides guidance on investigations relating to population distribution, and on the dispersion of effluents in air, surface water and groundwater. The guidance is intended to help determine whether the site selected for a nuclear power plant satisfies national requirements and whether possible radiological exposure and hazards to the population and to the environment are controlled within the limits set by the regulatory body, with account taken of international recommendations

Dispersion of radioactive material in air and water and consideration of population distribution in site evaluation for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2002-01-01

Dispersion of Radioactive Material in Relation to Nuclear Power Plant Siting (Safety Series No. 50-SG-S6 (1985)); and Nuclear Power Plant Siting: Hydrogeological Aspects (Safety Series No. 50-SG-S7 (1984)). Radioactive materials discharged from a nuclear power plant might reach the public and might contaminate the environment in the region by way of both direct and indirect pathways. The objective of this Safety Guide is to provide guidance on the studies and investigations necessary for assessing the impact of a nuclear power plant on humans and the environment. It also provides guidance on the feasibility of an effective emergency response plan, in consideration of all the relevant site features. This Safety Guide provides guidance on investigations relating to population distribution, and on the dispersion of effluents in air, surface water and groundwater. The guidance is intended to help determine whether the site selected for a nuclear power plant satisfies national requirements and whether possible radiological exposure and hazards to the population and to the environment are controlled within the limits set by the regulatory body, with account taken of international recommendations

Evolution of Safety Basis Documentation for the Fernald Site

International Nuclear Information System (INIS)

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

2004-01-01

The objective of the Department of Energy's (DOE) Fernald Closure Project (FCP), in suburban Cincinnati, Ohio, is to safely complete the environmental restoration of the Fernald site by 2006. Over 200 out of 220 total structures, at this DOE plant site which processed uranium ore concentrates into high-purity uranium metal products, have been safely demolished, including eight of the nine major production plants. Documented Safety Analyses (DSAs) for these facilities have gone through a process of simplification, from individual operating Safety Analysis Reports (SARs) to a single site-wide Authorization Basis containing nuclear facility Bases for Interim Operations (BIOs) to individual project Auditable Safety Records (ASRs). The final stage in DSA simplification consists of project-specific Integrated Health and Safety Plans (I-HASPs) and Nuclear Health and Safety Plans (N-HASPs) that address all aspects of safety, from the worker in the field to the safety basis requirements preserving the facility/activity hazard categorization. This paper addresses the evolution of Safety Basis Documentation (SBD), as DSAs, from production through site closure

Protection of environment, health and safety using risk management

Energy Technology Data Exchange (ETDEWEB)

Abraham, G [Ghafari Associates, Inc. 17101 Michegan Avenue Dearborn, MI 48126-2736 (United States); Kummler, R H [Department of Chemical engineering Wayne Stae University Detroit, MI 48202 (United States); louvar, J [Research Services Basf Corporation Wyandotte, MI 48192 (United States)

1997-12-31

Section 304 of the 1990 clean air amendments (CAAA) directed the US occupational safety and health administration (OSFA) to develop a chemical process safety standard to protect workers on-site from accidents involving hazardous substances. OSHA issued 29 CFR 1910.119, process safety management of Highly hazardous chemicals (PSM) in 1992. Section 112 r of the CAAA further mandated that a standard be developed to protect the environment from accidental releases of hazardous substances. The US environmental protection agency (EPA) proposed such a standard in 1993 (58 Fr 54190) and revised their proposal in 1995). The final rule for risk management and accidental release prevention is more comprehensive and extensive than OSHA`s PSM standard. In this paper we will discuss the concepts of both programs, the classes of substances that would trigger a facility`s need for compliance and review the regulations for risk management.

Protection of environment, health and safety using risk management

International Nuclear Information System (INIS)

Abraham, G.; Kummler, R.H.; louvar, J.

1996-01-01

Section 304 of the 1990 clean air amendments (CAAA) directed the US occupational safety and health administration (OSFA) to develop a chemical process safety standard to protect workers on-site from accidents involving hazardous substances. OSHA issued 29 CFR 1910.119, process safety management of Highly hazardous chemicals (PSM) in 1992. Section 112 r of the CAAA further mandated that a standard be developed to protect the environment from accidental releases of hazardous substances. The US environmental protection agency (EPA) proposed such a standard in 1993 (58 Fr 54190) and revised their proposal in 1995). The final rule for risk management and accidental release prevention is more comprehensive and extensive than OSHA's PSM standard. In this paper we will discuss the concepts of both programs, the classes of substances that would trigger a facility's need for compliance and review the regulations for risk management

Analysis of safety culture components based on site interviews

International Nuclear Information System (INIS)

Ueno, Akira; Nagano, Yuko; Matsuura, Shojiro

2002-01-01

Safety culture of an organization is influenced by many factors such as employee's moral, safety policy of top management and questioning attitude among site staff. First this paper analyzes key factors of safety culture on the basis of site interviews. Then the paper presents a safety culture composite model and its applicability in various contexts. (author)

Information report on nuclear safety and radiation protection of the SOMANU site - Issue 2014

International Nuclear Information System (INIS)

2015-01-01

Published in compliance with the French code of the environment, this report first presents different aspects of the SOMANU plant which is dedicated to the maintenance of materials and equipment from nuclear installations: location and environment, history, description of activities, regulatory framework. It describes the various measures regarding nuclear safety and radiation protection: general principles of nuclear safety, organization, presentation of the Areva's nuclear safety Charter, inspections and controls, measures regarding radiation protection. The next part addresses nuclear events which occurred on this site and had to be declared. The report gives an overview of activities and measures regarding the management of releases and the control of the environment. The next part addresses waste management: general considerations on radioactive waste management in France, description and classification of radioactive wastes present in the INB, management of conventional wastes. The management of other impacts is also reported. The last chapter reviews the actions undertaken in the field of transparency and information. Recommendations of the CHSCT are reported

Information report on nuclear safety and radiation protection of the SOMANU site - Issue 2012

International Nuclear Information System (INIS)

2013-06-01

Published in compliance with the French code of the environment, this report first presents different aspects of the SOMANU plant which is dedicated to the maintenance of materials and equipment from nuclear installations: location and environment, history, description of activities, regulatory framework. It describes the various measures regarding nuclear safety and radiation protection: general principles of nuclear safety, organization, presentation of the Areva's nuclear safety Charter, inspections and controls, measures regarding radiation protection. The next part addresses nuclear events which occurred on this site and had to be declared. The report gives an overview of activities and measures regarding the management of releases and the control of the environment. The next part addresses waste management: generalities on radioactive waste management in France, description and classification of radioactive wastes present in the INB, management of conventional wastes. The management of other impacts is also reported. The last chapter reviews the actions undertaken in the field of transparency and information. Recommendations of the CHSCT are reported

Empirical estimation of school siting parameter towards improving children's safety

International Nuclear Information System (INIS)

Aziz, I S; Yusoff, Z M; Rasam, A R A; Rahman, A N N A; Omar, D

2014-01-01

Distance from school to home is a key determination in ensuring the safety of hildren. School siting parameters are made to make sure that a particular school is located in a safe environment. School siting parameters are made by Department of Town and Country Planning Malaysia (DTCP) and latest review was on June 2012. These school siting parameters are crucially important as they can affect the safety, school reputation, and not to mention the perception of the pupil and parents of the school. There have been many studies to review school siting parameters since these change in conjunction with this ever-changing world. In this study, the focus is the impact of school siting parameter on people with low income that live in the urban area, specifically in Johor Bahru, Malaysia. In achieving that, this study will use two methods which are on site and off site. The on site method is to give questionnaires to people and off site is to use Geographic Information System (GIS) and Statistical Product and Service Solutions (SPSS), to analyse the results obtained from the questionnaire. The output is a maps of suitable safe distance from school to house. The results of this study will be useful to people with low income as their children tend to walk to school rather than use transportation

General safety guidelines for looking for a low mass activity-long life waste storage site

International Nuclear Information System (INIS)

2008-01-01

The objective of this document is to define general guidelines which must be followed during the stages of search for a site and stages of design of a storage facility for low activity-long life radioactive wastes, in order to ensure its safety after closure. After having specified the considered wastes, geological shapes, and situations, this document defines the fundamental objective and the associated criteria (protection against chemical risk, radioprotection). It presents the design aspects related to safety (safety principles and functions, waste packages, public works engineering, geological environment, storage concepts). The last part deals with the safety demonstration after site closure which includes the control of some components, the assessment of disturbances in the storage facility or due to its presence, the taking of uncertainty and sensitivity studies into account, the influence of natural events

Development of the NUMO pre-selection, site-specific safety case

International Nuclear Information System (INIS)

Fujiyama, Tetsuo; Suzuki, Satoru; Deguchi, Akira; Umeki, Hiroyuki

2016-01-01

Key conclusions: ◆ “The NUMO pre-selection, site-specific safety case” provides the basic structure for subsequent safety cases that will be applied to any selected site, emphasising practical approaches and methodology which will be applicable for the conditions/constraints during an actual siting process. ◆ The preliminary results of the design and safety assessment would underpin the feasibility and safety of geological disposal in Japan.

Safety cases and siting processes

International Nuclear Information System (INIS)

Metlay, Daniel; Ewing, Rodney

2014-01-01

Central to any process for building a deep-mined geologic repository for high-activity radioactive waste is the development of a safety case. To date, such cases, in various forms have been elaborated for a variety of concepts for geologic disposal, including in salt, clay, argillite, crystalline rock (granite and gneiss) and volcanic tuff formations. In addition to the technical effort required to develop a safety case, increasingly nations have come to believe that it is also critical to obtain the consent of the region or community where the facility might be located. The purpose of this paper is to explore issues associated with just one aspect of consent-based siting: How can such a process be designed so that willingness to accept a site for a repository continues to be meaningful even as new technical knowledge and insights emerge during site characterisation? In short, what is the meaning of 'informed consent' in the context of repository development? (authors)

Long-term safety for the final repository for spent nuclear fuel at Forsmark. Main report of the SR-Site project

Energy Technology Data Exchange (ETDEWEB)

2011-03-15

The central conclusion of the safety assessment SR-Site is that a KBS-3 repository that fulfils long-term safety requirements can be built at the Forsmark site. This conclusion is reached because the favourable properties of the Forsmark site ensure the required long-term durability of the barriers of the KBS-3 repository. In particular, the copper canisters with their cast iron inserts have been demonstrated to provide a sufficient resistance to the mechanical and chemical loads to which they may be subjected in the repository environment. The conclusion is underpinned by: - The reliance of the KBS-3 repository on i) a geological environment that exhibits long-term stability with respect to properties of importance for long-term safety, i.e. mechanical stability, low groundwater flow rates at repository depth and the absence of high concentrations of detrimental components in the groundwater, and ii) the choice of naturally occurring materials (copper and bentonite clay) for the engineered barriers that are sufficiently durable in the repository environment to provide the barrier longevity required for safety. - The understanding, through decades of research at SKB and in international collaboration, of the phenomena that affect long-term safety, resulting in a mature knowledge base for the safety assessment. - The understanding of the characteristics of the site through several years of surface-based investigations of the conditions at depth and of scientific interpretation of the data emerging from the investigations, resulting in a mature model of the site, adequate for use in the safety assessment. - The detailed specifications of the engineered parts of the repository and the demonstration of how components fulfilling the specifications are to be produced in a quality assured manner, thereby providing a quality assured initial state for the safety assessment. The detailed analyses demonstrate that canister failures in a one million year perspective are rare

Long-term safety for the final repository for spent nuclear fuel at Forsmark. Main report of the SR-Site project

International Nuclear Information System (INIS)

2011-03-01

The central conclusion of the safety assessment SR-Site is that a KBS-3 repository that fulfils long-term safety requirements can be built at the Forsmark site. This conclusion is reached because the favourable properties of the Forsmark site ensure the required long-term durability of the barriers of the KBS-3 repository. In particular, the copper canisters with their cast iron inserts have been demonstrated to provide a sufficient resistance to the mechanical and chemical loads to which they may be subjected in the repository environment. The conclusion is underpinned by: - The reliance of the KBS-3 repository on i) a geological environment that exhibits long-term stability with respect to properties of importance for long-term safety, i.e. mechanical stability, low groundwater flow rates at repository depth and the absence of high concentrations of detrimental components in the groundwater, and ii) the choice of naturally occurring materials (copper and bentonite clay) for the engineered barriers that are sufficiently durable in the repository environment to provide the barrier longevity required for safety. - The understanding, through decades of research at SKB and in international collaboration, of the phenomena that affect long-term safety, resulting in a mature knowledge base for the safety assessment. - The understanding of the characteristics of the site through several years of surface-based investigations of the conditions at depth and of scientific interpretation of the data emerging from the investigations, resulting in a mature model of the site, adequate for use in the safety assessment. - The detailed specifications of the engineered parts of the repository and the demonstration of how components fulfilling the specifications are to be produced in a quality assured manner, thereby providing a quality assured initial state for the safety assessment. The detailed analyses demonstrate that canister failures in a one million year perspective are rare

Health, Safety and Environmental Risk Assessment in Laboratory Sites

Directory of Open Access Journals (Sweden)

2012-05-01

Full Text Available Introduction: ”Exposing to danger” or in other words, “risk” is a process which is led to an uncertain result in every field. Project risks are uncertain contingent events or situations that if they occur will have positive or negative effects on project’s objectives. Todays, research and educational process and more complicated and the professional risk management become much more difficult, as a result. .Material and Method: In this research, the health and safety issues have been studied and analyzed using ISO 14121 and the environmental issues by EMEA to determine the risk level separately for research laboratories and to prioritize corrective measure in each field (school. .Result: The finding in this study showed that from all the main risks within the rage of 38-86 percent have been decreased. Moreover average of the risk level for the health, safety and environment cases showed a significant decrease (Pvalue<0.0001 by implement controlling and protective countermeasures compariy to the priority state without any measures. . Conclusion: The risk assessment with hazards control strategy based on ISO 14121 is a compatible method in laboratory site as universities and other reasearch sites.

Sandia Laboratories environment and safety programs

International Nuclear Information System (INIS)

Zak, B.D.; McGrath, P.E.; Trauth, C.A. Jr.

1975-01-01

Sandia, one of ERDA's largest laboratories, is primarily known for its extensive work in the nuclear weapons field. In recent years, however, Sandia's role has expanded to embrace sizeable programs in the energy, resource recovery, and the environment and safety fields. In this latter area, Sandia has programs which address nuclear, fossil fuel, and general environment and safety issues. Here we survey ongoing activities and describe in more detail aa few projects of particular interest. These range from a study of the impact of sealed disposal of radioactive wastes, through reactor safety and fossil fuel plume chemistry, to investigations of the composition and dynamics of the stratosphere

Preliminary Safety Analysis of the Gorleben Site: Safety Concept and Application to Scenario Development Based on a Site-Specific Features, Events and Processes (FEP) Database - 13304

Energy Technology Data Exchange (ETDEWEB)

Moenig, Joerg; Beuth, Thomas; Wolf, Jens [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Theodor-Heuss-Str. 4, D-38122 Braunschweig (Germany); Lommerzheim, Andre [DBE TECHNOLOGY GmbH, Eschenstr. 55, D-31224 Peine (Germany); Mrugalla, Sabine [Federal Institute for Geosciences and Natural Resources (BGR), Stilleweg 2, D-30655 Hannover (Germany)

2013-07-01

Based upon the German safety criteria, released in 2010 by the Federal Ministry of the Environment (BMU), a safety concept and a safety assessment concept for the disposal of heat-generating high-level waste have both been developed in the framework of the preliminary safety case for the Gorleben site (Project VSG). The main objective of the disposal is to contain the radioactive waste inside a defined rock zone, which is called containment-providing rock zone. The radionuclides shall remain essentially at the emplacement site, and at the most, a small defined quantity of material shall be able to leave this rock zone. This shall be accomplished by the geological barrier and a technical barrier system, which is required to seal the inevitable penetration of the geological barrier by the construction of the mine. The safe containment has to be demonstrated for probable and less probable evolutions of the site, while evolutions with very low probability (less than 1 % over the demonstration period of 1 million years) need not to be considered. Owing to the uncertainty in predicting the real evolution of the site, plausible scenarios have been derived in a systematic manner. Therefore, a comprehensive site-specific features, events and processes (FEP) data base for the Gorleben site has been developed. The safety concept was directly taken into account, e.g. by identification of FEP with direct influence on the barriers that provide the containment. No effort was spared to identify the interactions of the FEP, their probabilities of occurrence, and their characteristics (values). The information stored in the data base provided the basis for the development of scenarios. The scenario development methodology is based on FEP related to an impairment of the functionality of a subset of barriers, called initial barriers. By taking these FEP into account in their probable characteristics the reference scenario is derived. Thus, the reference scenario describes a

Report on safety and the environment 1992-93

International Nuclear Information System (INIS)

1993-09-01

The steps taken by AEA Technology to implement high safety and environmental standards and performance levels achieved are summarized. AEA's policy on safety and the environment is stated. The way that safety is organised, how plant safety cases are made, plant operations and safety 1992-93 and decommissioning work at several of AEA's plants are reported. Radiological doses for AEA plants are shown to have fallen since 1990. General industrial and office safety, what is learned from accidents and incidents, how the environment is protected, the occupational health services provided and the emergency arrangements in operation are also mentioned briefly. (UK)

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

Radiation safety for site radiography

International Nuclear Information System (INIS)

1986-01-01

This guidance is an update of the 1975 Code of Practice for Site Radiography and is for the use of employers and their radiographers who carry out site work. The subject is discussed under the following headings: Administrative organization, Personnel requirements, Equipment (x-ray and gamma-ray equipment, security, pipeline crawler equipment and safety equipment) Work methods and monitoring, Carriage of sources, Contingency plans, Legal considerations. (U.K.)

Strategy for safety case development: impact of a volunteering approach to siting a japanese HLW repository

International Nuclear Information System (INIS)

Kitayama, K.; Ishiguro, K.; Takeuchi, M.; Tsuchi, H.; Kato, T.; Sakabe, Y.; Wakasugi, K.

2008-01-01

NUMO strategy for safety case development is constrained by a staged siting approach, which has been initiated by a call for volunteer municipalities to host the HLW repository. For each site, the safety case is an important factor to be considered at the selection steps which narrow down towards the preferred repository location. This is particularly challenging, however, as every site requires a tailored repository concept, with associated performance assessment and an individual site evaluation programme all of which evolve with gradually increasing understanding of the host environment. In order to maintain flexibility without losing focus, NUMO has developed a formalized tailoring procedure, termed the NUMO Structured Approach (NSA). The NSA guides the interaction of the key site characterisation, repository design and performance assessment groups and is facilitated by tools to help the decision making associated with the tailoring process (e.g. a requirements management system) and with comparison of siting and design options (e.g. multi-attribute analysis). Pragmatically, the post-closure safety case will initially emphasize near-field processes and a robust engineering barrier system, considering the limited geological information at early stages. This will be complemented by a more realistic assessment of total system performance, as needed to compare options. In addition, efforts to rigorously assess operational phase safety and the practicality of assuring quality of the constructed engineered barriers are components of the total safety case which are receiving particular attention now, as they may better discriminate between sites while information is still limited. (authors)

High temperature reactor safety and environment

International Nuclear Information System (INIS)

Brisbois, J.; Charles, J.

1975-01-01

High-temperature reactors are endowed with favorable safety and environmental factors resulting from inherent design, main-component safety margins, and conventional safety systems. The combination of such characteristics, along with high yields, prove in addition, that such reactors are plagued with few problems, can be installed near users, and broaden the recourse to specific power, therefore fitting well within a natural environment [fr

Environmental Assessment: Waste Tank Safety Program, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1994-02-01

The US Department of Energy (DOE) needs to take action in the near-term, to accelerate resolution of waste tank safety issues at the Hanford Site near the City of Richland, Washington, and reduce the risks associated with operations and management of the waste tanks. The DOE has conducted nuclear waste management operations at the Hanford Site for nearly 50 years. Operations have included storage of high-level nuclear waste in 177 underground storage tanks (UST), both in single-shell tank (SST) and double-shell tank configurations. Many of the tanks, and the equipment needed to operate them, are deteriorated. Sixty-seven SSTs are presumed to have leaked a total approximately 3,800,000 liters (1 million gallons) of radioactive waste to the soil. Safety issues associated with the waste have been identified, and include (1) flammable gas generation and episodic release; (2) ferrocyanide-containing wastes; (3) a floating organic solvent layer in Tank 241-C-103; (4) nuclear criticality; (5) toxic vapors; (6) infrastructure upgrades; and (7) interim stabilization of SSTs. Initial actions have been taken in all of these areas; however, much work remains before a full understanding of the tank waste behavior is achieved. The DOE needs to accelerate the resolution of tank safety concerns to reduce the risk of an unanticipated radioactive or chemical release to the environment, while continuing to manage the wastes safely

Hanford site environment

International Nuclear Information System (INIS)

Isaacson, R.E.

1976-01-01

A synopsis is given of the detailed characterization of the existing environment at Hanford. The following aspects are covered: demography, land use, meteorology, geology, hydrology, and seismology. It is concluded that Hanford is one of the most extensively characterized nuclear sites

General aspects of siting and safety considerations

International Nuclear Information System (INIS)

Rutgers, E.

1980-01-01

The siting process from site selection to the different stages of review by the regulatory body is described. Special attention is payed to the role and responsibilities of the licensing authority. Next, the basic considerations involved in the siting process are reviewed. They include system planning, engineering, safety, environmental impact (including land use) and economics. Case studies illustrating different aspects of the siting process (e.g. site selection) are presented. (orig.)

The site of a nuclear power plant and environmental safety; Ydinvoimalaitoksen sijaintipaikka ja ympaeristoen turvallisuus

Energy Technology Data Exchange (ETDEWEB)

Rossi, J. [VTT Energy, Espoo (Finland)

2001-11-01

The purpose of this report is to give the reader a general view of the things associated with the site of a nuclear power plant. In this context the effect of a nuclear power plant and site on environmental safety is considered. Planning, construction and operating a nuclear power plant require several judgements and licenses based on different laws. The location of the planned nuclear facility project and environmental conditions contribute in great detail to the compliance arguments of permits. At first the environmental impacts of the siting project and its alternatives shall be investigated in the Environmental Impact Assessment procedure. Then the decision in principle according to the Nuclear Energy Act can be applied from the Council of State, the decision shall further be confirmed by Parliament. When the decision in principle is considered the overall good of society shall be assessed by means of considering i.a. site alternatives and safety. The safety related basic principle is that operation of a nuclear power plant may not cause danger to the environment, public or property. After the affirmative principle approval the construction license and later on the operation license can be applied from the Council of State, these licenses need to be supported i.a. by building and environmental licenses of separate authorities. Also some international contracts concern realisation of a nuclear power plant siting. The nuclear power plant site shall be suitable for the needs of the electricity production and the transmission system and it shall be technically appropriate for building and operation of a power plant. The site shall be safe enough on the other hand from the view of external events threatening the power plant - although one can be partly prepared for these things in the design of the plant - and on the other hand from the point of public safety. Requirements for the safety of the site are directed in the decision of the Council of State's general

Health, Safety, and Environment Division

Energy Technology Data Exchange (ETDEWEB)

Wade, C [comp.

1992-01-01

The primary responsibility of the Health, Safety, and Environmental (HSE) Division at the Los Alamos National Laboratory is to provide comprehensive occupational health and safety programs, waste processing, and environmental protection. These activities are designed to protect the worker, the public, and the environment. Meeting these responsibilities requires expertise in many disciplines, including radiation protection, industrial hygiene, safety, occupational medicine, environmental science and engineering, analytical chemistry, epidemiology, and waste management. New and challenging health, safety, and environmental problems occasionally arise from the diverse research and development work of the Laboratory, and research programs in HSE Division often stem from these applied needs. These programs continue but are also extended, as needed, to study specific problems for the Department of Energy. The results of these programs help develop better practices in occupational health and safety, radiation protection, and environmental science.

Safety leadership: application in construction site.

Science.gov (United States)

Cooper, Dominic

2010-01-01

The extant safety literature suggests that managerial Safety Leadership is vital to the success and maintenance of a behavioral safety process. The current paper explores the role of Managerial Safety Leadership behaviors in the success of a behavioral safety intervention in the Middle-East with 47,000 workers from multiple nationalities employed by fourteen sub-contractors and one main contractor. A quasi-experimental repeating ABABAB, within groups design was used. Measurement focused on managerial Safety Leadership and employee safety behaviors as well as Corrective Actions. Data was collected over 104 weeks. During this time, results show safety behavior improved by 30 percentage points from an average of 65% during baseline to an average of 95%. The site achieved 121 million man-hours free of lost-time injuries on the longest run. Stepwise multiple regression analyses indicated 86% of the variation in employee safety behavior was associated with senior, middle and front-line manager's Safety Leadership behaviors and the Corrective Action Rate. Approximately 38% of the variation in the Total Recordable Incident Rate (TRIR) was associated with the Observation rate, Corrective Action Rate and Observers Records of managerial safety leaders (Visible Ongoing Support). The results strongly suggest manager's Safety Leadership influences the success of Behavioral Safety processes.

Prospective safety performance evaluation on construction sites.

Science.gov (United States)

Wu, Xianguo; Liu, Qian; Zhang, Limao; Skibniewski, Miroslaw J; Wang, Yanhong

2015-05-01

This paper presents a systematic Structural Equation Modeling (SEM) based approach for Prospective Safety Performance Evaluation (PSPE) on construction sites, with causal relationships and interactions between enablers and the goals of PSPE taken into account. According to a sample of 450 valid questionnaire surveys from 30 Chinese construction enterprises, a SEM model with 26 items included for PSPE in the context of Chinese construction industry is established and then verified through the goodness-of-fit test. Three typical types of construction enterprises, namely the state-owned enterprise, private enterprise and Sino-foreign joint venture, are selected as samples to measure the level of safety performance given the enterprise scale, ownership and business strategy are different. Results provide a full understanding of safety performance practice in the construction industry, and indicate that the level of overall safety performance situation on working sites is rated at least a level of III (Fair) or above. This phenomenon can be explained that the construction industry has gradually matured with the norms, and construction enterprises should improve the level of safety performance as not to be eliminated from the government-led construction industry. The differences existing in the safety performance practice regarding different construction enterprise categories are compared and analyzed according to evaluation results. This research provides insights into cause-effect relationships among safety performance factors and goals, which, in turn, can facilitate the improvement of high safety performance in the construction industry. Copyright © 2015 Elsevier Ltd. All rights reserved.

Health, Safety, and Environment Division: Annual progress report 1987

Energy Technology Data Exchange (ETDEWEB)

Rosenthal, M.A. (comp.)

1988-04-01

The primary responsibility of the Health, Safety, and Environment (HSE) Division at the Los Alamos National Laboratory is to provide comprehensive occupational health and safety programs, waste processing, and environment protection. These activities are designed to protect the worker, the public, and the environment. Many disciplines are required to meet the responsibilities, including radiation protection, industrial hygiene, safety, occupational medicine, environmental science, epidemiology, and waste management. New and challenging health and safety problems arise occasionally from the diverse research and development work of the Laboratory. Research programs in HSE Division often stem from these applied needs. These programs continue but are also extended, as needed to study specific problems for the Department of Energy and to help develop better occupational health and safety practices.

Health, Safety, and Environment Division: Annual progress report 1987

International Nuclear Information System (INIS)

Rosenthal, M.A.

1988-04-01

The primary responsibility of the Health, Safety, and Environment (HSE) Division at the Los Alamos National Laboratory is to provide comprehensive occupational health and safety programs, waste processing, and environment protection. These activities are designed to protect the worker, the public, and the environment. Many disciplines are required to meet the responsibilities, including radiation protection, industrial hygiene, safety, occupational medicine, environmental science, epidemiology, and waste management. New and challenging health and safety problems arise occasionally from the diverse research and development work of the Laboratory. Research programs in HSE Division often stem from these applied needs. These programs continue but are also extended, as needed to study specific problems for the Department of Energy and to help develop better occupational health and safety practices

Design of plant safety model in plant enterprise engineering environment

International Nuclear Information System (INIS)

Gabbar, Hossam A.; Suzuki, Kazuhiko; Shimada, Yukiyasu

2001-01-01

Plant enterprise engineering environment (PEEE) is an approach aiming to manage the plant through its lifecycle. In such environment, safety is considered as the common objective for all activities throughout the plant lifecycle. One approach to achieve plant safety is to embed safety aspects within each function and activity within such environment. One ideal way to enable safety aspects within each automated function is through modeling. This paper proposes a theoretical approach to design plant safety model as integrated with the plant lifecycle model within such environment. Object-oriented modeling approach is used to construct the plant safety model using OO CASE tool on the basis of unified modeling language (UML). Multiple views are defined for plant objects to express static, dynamic, and functional semantics of these objects. Process safety aspects are mapped to each model element and inherited from design to operation stage, as it is naturally embedded within plant's objects. By developing and realizing the plant safety model, safer plant operation can be achieved and plant safety can be assured

Preliminary safety evaluation for the Laxemar subarea. Based on data and site descriptions after the initial site investigation stage

Energy Technology Data Exchange (ETDEWEB)

Andersson, Johan [JA Streamflow AB, Aelvsjoe (Sweden)

2006-03-15

The main objectives of this Preliminary Safety Evaluation (PSE) of the Laxemar subarea have been to determine, with limited efforts, whether the feasibility study's judgement of the suitability of the candidate area with respect to long-term safety holds up in the light of the actual site investigation data; to provide feedback to continued site investigations and site-specific repository design and to identify site-specific scenarios and geoscientific issues for further analyses. The PSE focuses on comparing the attained knowledge of the sites with the suitability criteria as set out by SKB in 2000. These criteria both concern properties of the site judged to be necessary for safety and engineering (requirements) and properties judged to be beneficial (preferences). The findings are then evaluated in order to provide feedback to continued investigations and design work. The PSE does not aim at comparing sites and does not assess compliance with safety and radiation protection criteria. The latter is eventually done in coming Safety Assessments. This preliminary safety evaluation shows that, according to existing data, the Laxemar subarea meets all safety requirements. The evaluation also shows that the Laxemar subarea meets most of the safety preferences, but for some aspects of the site description further reduction of the uncertainties would enhance the safety case. Despite the stated concerns, there is no reason, from a safety point of view, not to continue the Site Investigations at the Laxemar subarea. There are uncertainties to resolve and the safety would eventually need to be verified through a proper safety assessment. Only some of the uncertainties noted in the Site Descriptive Model have safety implications and need further resolution for this reason. Furthermore, uncertainties may need resolving for other reasons, such as giving an adequate assurance of site understanding or assisting in optimising design. Notably, there are questions about the

Preliminary safety evaluation for the Laxemar subarea. Based on data and site descriptions after the initial site investigation stage

International Nuclear Information System (INIS)

Andersson, Johan

2006-03-01

The main objectives of this Preliminary Safety Evaluation (PSE) of the Laxemar subarea have been to determine, with limited efforts, whether the feasibility study's judgement of the suitability of the candidate area with respect to long-term safety holds up in the light of the actual site investigation data; to provide feedback to continued site investigations and site-specific repository design and to identify site-specific scenarios and geoscientific issues for further analyses. The PSE focuses on comparing the attained knowledge of the sites with the suitability criteria as set out by SKB in 2000. These criteria both concern properties of the site judged to be necessary for safety and engineering (requirements) and properties judged to be beneficial (preferences). The findings are then evaluated in order to provide feedback to continued investigations and design work. The PSE does not aim at comparing sites and does not assess compliance with safety and radiation protection criteria. The latter is eventually done in coming Safety Assessments. This preliminary safety evaluation shows that, according to existing data, the Laxemar subarea meets all safety requirements. The evaluation also shows that the Laxemar subarea meets most of the safety preferences, but for some aspects of the site description further reduction of the uncertainties would enhance the safety case. Despite the stated concerns, there is no reason, from a safety point of view, not to continue the Site Investigations at the Laxemar subarea. There are uncertainties to resolve and the safety would eventually need to be verified through a proper safety assessment. Only some of the uncertainties noted in the Site Descriptive Model have safety implications and need further resolution for this reason. Furthermore, uncertainties may need resolving for other reasons, such as giving an adequate assurance of site understanding or assisting in optimising design. Notably, there are questions about the

Geosphere process report for the safety assessment SR-Site

International Nuclear Information System (INIS)

Skagius, Kristina

2010-11-01

This report documents geosphere processes identified as relevant to the long-term safety of a KBS-3 repository, and forms an important part of the reporting of the safety assessment SR-Site. The detailed assessment methodology, including the role of the process reports in the assessment, is described in the SR-Site Main report /SKB 2011/

Geosphere process report for the safety assessment SR-Site

Energy Technology Data Exchange (ETDEWEB)

Skagius, Kristina (ed.) (Kemakta Konsult AB, Stockholm (Sweden))

2010-11-15

This report documents geosphere processes identified as relevant to the long-term safety of a KBS-3 repository, and forms an important part of the reporting of the safety assessment SR-Site. The detailed assessment methodology, including the role of the process reports in the assessment, is described in the SR-Site Main report /SKB 2011/

Health, Safety, and Environment Division annual report, 1988

International Nuclear Information System (INIS)

Rosenthal, M.A.

1989-10-01

The primary responsibility of the Health, Safety, and Environment (HSE) Division at the Los Alamos National Laboratory is to provide comprehensive occupational health and safety programs, waste processing, and environmental protection. These activities are designed to protect the worker, the public, and the environment. Many disciplines are required to meet the responsibilities, including radiation protection, industrial hygiene, safety, occupational medicine, environmental science, epidemiology, and waste management. New and challenging health and safety problems occasionally arise from the diverse research and development work of the Laboratory. Research programs in HSE Division often stem from these applied needs. These programs continue but are also extended, as needed, to study specific problems for the Department of Energy and to help develop better occupational health and safety practices. 52 refs

Approaches to safety, environment and regulatory approval for the International Thermonuclear Experimental Reactor

International Nuclear Information System (INIS)

Saji, G.; Bartels, H.W.; Chuyanov, V.; Holland, D.; Kashirski, A.V.; Morozov, S.I.; Piet, S.J.; Poucet, A.; Raeder, J.; Rebut, P.H.; Topilski, L.N.

1995-01-01

International Thermonuclear Experimental Reactor (ITER) Engineering Design Activities (EDA) in safety and environment are approaching the point where conceptual safety design, topic studies and research will give way to project oriented engineering design activities. The Joint Central Team (JCT) is promoting safety design and analysis necessary for siting and regulatory approval. Scoping studies are underway at the general level, in terms of laying out the safety and environmental design framework for ITER. ITER must follow the nuclear regulations of the host country as the future construction site of ITER. That is, regulatory approval is required before construction of ITER. Thus, during the EDA, some preparations are necessary for the future application for regulatory approval. Notwithstanding the future host country's jurisdictional framework of nuclear regulations, the primary responsibility for safety and reliability of ITER rests with the legally responsible body which will operate ITER. Since scientific utilization of ITER and protection of the large investment depends on safe and reliable operation of ITER, we are highly motivated to achieve maximum levels of operability, maintainability, and safety. ITER will be the first fusion facility in which overall 'nuclear safety' provisions need to be integrated into the facility. For example, it will be the first fusion facility with significant decay heat and structural radiational damage. Since ITER is an experimental facility, it is also important that necessary experiments can be performed within some safety design limits without requiring extensive regulatory procedures. ITER will be designed with such a robust safety envelope compatible with the fusion power and the energy inventories. The basic approach to safety will be realized by 'defense-in-depth'. (orig.)

External human induced events in site evaluation for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

The purpose of the present Safety Guide is to provide recommendations and guidance for the examination of the region considered for site evaluation for a plant in order to identity hazardous phenomena associated with human induced events initiated by sources external to the plant. In some cases it also presents preliminary guidance for deriving values of relevant parameters for the design basis. This Safety Guide is also applicable for periodic site evaluation and site evaluation following a major human induced event, and for the design and operation of the site's environmental monitoring system. Site evaluation includes site characterization. Consideration of external events that could lead to a degradation of the safety features of the plant and cause a release of radioactive material from the plant and/or affect the dispersion of such material in the environment. And consideration of population issues and access issues significant to safety (such as the feasibility of evacuation, the population distribution and the location of resources). The process of site evaluation continues throughout the lifetime of the facility, from siting to design, construction, operation and decommissioning. The external human induced events considered in this Safety Guide are all of accidental origin. Considerations relating to the physical protection of the plant against wilful actions by third parties are outside its scope. However, the methods described herein may also have some application for the purposes of such physical protection. The present Safety Guide may also be used for events that may originate within the boundaries of the site, but from sources which are not directly involved in the operational states of the nuclear power plant units, such as fuel depots or areas for the storage of hazardous materials for the construction of other facilities at the same site. Special consideration should be given to the hazardous material handled during the construction, operation and

Audit Report The Procurement of Safety Class/Safety-Significant Items at the Savannah River Site

International Nuclear Information System (INIS)

2009-01-01

The Department of Energy operates several nuclear facilities at its Savannah River Site, and several additional facilities are under construction. This includes the National Nuclear Security Administration's Tritium Extraction Facility (TEF) which is designated to help maintain the reliability of the U.S. nuclear stockpile. The Mixed Oxide Fuel Fabrication Facility (MOX Facility) is being constructed to manufacture commercial nuclear reactor fuel assemblies from weapon-grade plutonium oxide and depleted uranium. The Interim Salt Processing (ISP) project, managed by the Office of Environmental Management, will treat radioactive waste. The Department has committed to procuring products and services for nuclear-related activities that meet or exceed recognized quality assurance standards. Such standards help to ensure the safety and performance of these facilities. To that end, it issued Departmental Order 414.1C, Quality Assurance (QA Order). The QA Order requires the application of Quality Assurance Requirements for Nuclear Facility Applications (NQA-1) for nuclear-related activities. The NQA-1 standard provides requirements and guidelines for the establishment and execution of quality assurance programs during the siting, design, construction, operation, and decommissioning of nuclear facilities. These requirements, promulgated by the American Society of Mechanical Engineers, must be applied to 'safety-class' and 'safety-significant' structures, systems and components (SSCs). Safety-class SSCs are defined as those necessary to prevent exposure off site and to protect the public. Safety-significant SSCs are those whose failure could irreversibly impact worker safety such as a fatality, serious injury, or significant radiological or chemical exposure. Due to the importance of protecting the public, workers, and environment, we initiated an audit to determine whether the Department of Energy procured safety-class and safety-significant SSCs that met NQA-1 standards at

Environment and safety research status report: 1993

International Nuclear Information System (INIS)

1993-03-01

The 1993 status report discusses ongoing and planned research activities in the GRI Environment and Safety Program. The objectives and goals, accomplishments, and strategy along with the basis for each project area are presented for the supply, end use, and gas operations subprograms. Within the context of these subprograms, contract status summaries under their conceptual titles are given for the following project areas: Gas Supply Environmental and Safety Research, Air Quality Research, End Use Equipment Safety Research, Gas Operations Safety Research, Liquefied Natural Gas, Safety Research, and Gas Operations Environmental Research

Identification of scenarios in the safety assessment of a deep geological site for radioactive waste disposal

International Nuclear Information System (INIS)

Escalier des Orres, P.; Devillers, C.; Cernes, A.

1990-01-01

The selection and qualification procedure of a site for radioactive wastes disposal in a deep geologic formation, has begun in France in the early eighties. The public authorities, on ANDRA's proposal, has preselected in 1987 four sites, each of them corresponding to a type of geologic formations (granite, clay, salt and shale). Within two years, one of these sites will be chosen for the location of an underground laboratory. The safety analysis for the site's qualification uses evolution scenarios of the repository and its environment, chosen according to a deterministic method. With an appropriate detail level, are defined a reference scenario and scenario with random events. 4 refs., 1 tab [fr

Perspective on safety case to support a possible site recommendation decision

International Nuclear Information System (INIS)

Gil, A.V.; Gamble, R.P.

2002-01-01

The mission of the US Department of Energy (DOE) is to provide the basis for a national decision regarding the development of a geological repository for spent nuclear fuel and high-level radioactive waste at the Yucca Mountain site in Nevada. There are a number of steps in the decision process defined by US law that must be completed prior to development of a repository at this site. The DOE's focus is currently on the first two steps in this process: characterization of the site to support a determination by the DOE on whether the site is suitable for a geologic repository and a decision by the Secretary of Energy (the Secretary) on whether to recommend to the President that the site be approved for a repository. To enhance the confidence of multiple audiences in the basis for these actions, and to provide a basis for subsequent action by the President and the US Congress, information supporting the decision process must include the elements of a safety case consistent with the statutory and regulatory framework for these decisions. The idea of a safety case is to broaden the basis for confidence by decision-makers and the public in conclusions about safety. A safety case should cite multiple lines of evidence, or reasoning, beyond the results of a safety assessment to support the demonstration of safety, which includes compliance with applicable safety criteria. The multiple lines of evidence should show the basis for confidence in safety. To be most effective, such evidence requires information not directly used in the safety assessment. (author)

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

Handling of future human actions in the safety assessment SR-Site

International Nuclear Information System (INIS)

2010-12-01

authorities in their review of SR-Can /Dverstorp and Stroemberg 2008/ maintain that the state, rather than SKB, is expected to be responsible for the supervision and monitoring of the repository after sealing. Man is dependent on, and influences, the environment in which he lives. After the repository has been closed, future generations should be able to utilise the repository site according to their needs without jeopardising their health. In the case of a final repository of the KBS-3 type, there are, however, inevitably examples of activities that, if carried out carelessly or without knowledge of the repository, could result in exposure to radiotoxic elements from the spent fuel. Therefore, there is an international consensus that future human activities shall be considered in safety assessments of deep geological repositories. Based on generally accepted principles and the Swedish Radiation Safety Authority's, SSM's, regulations SSM FS 2008:21 and SSM FS 2008:37, the future human actions considered in this part of the safety assessment are restricted to global pollution and actions that: - are carried out after the sealing of the repository, - take place at or close to the repository site, - are unintentional, i.e. are carried out when the location of the repository is unknown, its purpose forgotten or the consequences of the action are unknown, - impair the safety functions of the repository's barriers. However, in line with SSM's general guidance /SSM 2008a/, future human actions and their impact on the repository are evaluated separately, and are not included in the main scenario reference evolution or in the risk summation

Handling of future human actions in the safety assessment SR-Site

Energy Technology Data Exchange (ETDEWEB)

2010-12-15

authorities in their review of SR-Can /Dverstorp and Stroemberg 2008/ maintain that the state, rather than SKB, is expected to be responsible for the supervision and monitoring of the repository after sealing. Man is dependent on, and influences, the environment in which he lives. After the repository has been closed, future generations should be able to utilise the repository site according to their needs without jeopardising their health. In the case of a final repository of the KBS-3 type, there are, however, inevitably examples of activities that, if carried out carelessly or without knowledge of the repository, could result in exposure to radiotoxic elements from the spent fuel. Therefore, there is an international consensus that future human activities shall be considered in safety assessments of deep geological repositories. Based on generally accepted principles and the Swedish Radiation Safety Authority's, SSM's, regulations SSM FS 2008:21 and SSM FS 2008:37, the future human actions considered in this part of the safety assessment are restricted to global pollution and actions that: - are carried out after the sealing of the repository, - take place at or close to the repository site, - are unintentional, i.e. are carried out when the location of the repository is unknown, its purpose forgotten or the consequences of the action are unknown, - impair the safety functions of the repository's barriers. However, in line with SSM's general guidance /SSM 2008a/, future human actions and their impact on the repository are evaluated separately, and are not included in the main scenario reference evolution or in the risk summation

The Safety Analysis of Shipborne Ammunition in Fire Environment

Science.gov (United States)

Ren, Junpeng; Wang, Xudong; Yue, Pengfei

2017-12-01

The safety of Ammunition has always been the focus of national military science and technology issues. And fire is one of the major safety threats to the ship’s ammunition storage environment, In this paper, Mk-82 shipborne aviation bomb has been taken as the study object, simulated the whole process of fire by using the FDS (Fire Detection System) software. According to the simulation results of FDS, ANSYS software was used to simulate the temperature field of Mk-82 carrier-based aviation bomb under fire environment, and the safety of aviation bomb in fire environment was analyzed. The result shows that the aviation bombs under the fire environment can occur the combustion or explosion after 70s constant cook-off, and it was a huge threat to the ship security.

Integrated environment, safety, and health management system description

International Nuclear Information System (INIS)

Zoghbi, J. G.

2000-01-01

The Integrated Environment, Safety, and Health Management System Description that is presented in this document describes the approach and management systems used to address integrated safety management within the Richland Environmental Restoration Project

Boundary conditions for pathways, safety analysis and basic criteria for low-level radiation waste site selection

International Nuclear Information System (INIS)

Saverot, P.

1994-01-01

There are three successive periods in the life of a disposal facility: the operating period, the institutional control period and the unrestricted site access period. The purpose of safety analysis of the disposal facility is to ensure that the radiological impacts for each period in the life of the facility are acceptable under all circumstances. Founded on a deterministic approach, this analysis leads to a determination of the maximum quantity of each radionuclide present in the facility at the beginning of the institutional control period in order for the impacts to be considered acceptable. Safety analysis involves the calculation of the radiological impacts of a given radiological inventory under a selected scenario, from all plausible scenarios of radionuclide migration to the environment in both normal and accident conditions, and taking into account other specified variables. The calculation itself involves an assessment of the quantities of radionuclides that could be released to the environment under the specific scenario selected and following identified pathways, and a determination of the resultant exposure, both internal and external, to the public. An iterative approach is used in the performance of pathways analyses. If the pathways analyses result in unacceptable radiological impacts, either the radiological inventory of the site is reduced or barrier characteristics not previously factored into the analysis are taken into account. New pathways analyses are then performed until the results are within the acceptable range. Once accepted by the safety authorities, the radiological inventory becomes the radiological capacity, which is the approved quantities of specific radionuclides that may be disposed of at the site. The following elaborates on the boundary conditions used in safety analyses and describes the types of pathways analyses performed for a LLW disposal facility

Alternative off-site power supply improves nuclear power plant safety

International Nuclear Information System (INIS)

Gjorgiev, Blaže; Volkanovski, Andrija; Kančev, Duško; Čepin, Marko

2014-01-01

Highlights: • Additional power supply for mitigation of the station blackout event in NPP is used. • A hydro power plant is considered as an off-site alternative power supply. • An upgrade of the probabilistic safety assessment from its traditional use is made. • The obtained results show improvement of nuclear power plant safety. - Abstract: A reliable power system is important for safe operation of the nuclear power plants. The station blackout event is of great importance for nuclear power plant safety. This event is caused by the loss of all alternating current power supply to the safety and non-safety buses of the nuclear power plant. In this study an independent electrical connection between a pumped-storage hydro power plant and a nuclear power plant is assumed as a standpoint for safety and reliability analysis. The pumped-storage hydro power plant is considered as an alternative power supply. The connection with conventional accumulation type of hydro power plant is analysed in addition. The objective of this paper is to investigate the improvement of nuclear power plant safety resulting from the consideration of the alternative power supplies. The safety of the nuclear power plant is analysed through the core damage frequency, a risk measure assess by the probabilistic safety assessment. The presented method upgrades the probabilistic safety assessment from its common traditional use in sense that it considers non-plant sited systems. The obtained results show significant decrease of the core damage frequency, indicating improvement of nuclear safety if hydro power plant is introduced as an alternative off-site power source

Siting of nuclear facilities. Selections from Nuclear Safety

Energy Technology Data Exchange (ETDEWEB)

Buchanan, J.R.

1976-07-01

The report presented siting policy and practice for nuclear power plants as developed in the U.S. and abroad. Twenty-two articles from Nuclear Safety on this general topic are reprinted since they provide a valuable reference source. The appendices also include reprints of some relevant regulatory rules and guides on siting. Advantages and disadvantages of novel siting concepts such as underground containment, offshore siting, and nuclear energy parks are addressed. Other topics include site criteria, risk criteria, and nuclear ship criteria.

Siting of nuclear facilities. Selections from Nuclear Safety

International Nuclear Information System (INIS)

Buchanan, J.R.

1976-07-01

The report presented siting policy and practice for nuclear power plants as developed in the U.S. and abroad. Twenty-two articles from Nuclear Safety on this general topic are reprinted since they provide a valuable reference source. The appendices also include reprints of some relevant regulatory rules and guides on siting. Advantages and disadvantages of novel siting concepts such as underground containment, offshore siting, and nuclear energy parks are addressed. Other topics include site criteria, risk criteria, and nuclear ship criteria

Proceedings of The First National Seminar on Safety, Public Health and Environment

International Nuclear Information System (INIS)

Hiswara, Eri; Bunawas; Dumais, Johannes P.; Alatas, Zubaidah; Melyani

2001-11-01

The first national seminar of safety, public health and environment was held in 23-24 Oct 2001 at the center for research and development of radiation safety and nuclear biomedicine natural energy agency, Indonesia have presented 27 papers, about safety, public health and environment the proceedings is expected to give illustration of the research result on safety, health and environment. (PPIN)

A program approach for site safety at oil spills

International Nuclear Information System (INIS)

Whipple, F.L.; Glenn, S.P.; Ocken, J.J.; Ott, G.L.

1993-01-01

When OSHA developed the hazardous waste operations (Hazwoper) regulations (29 CFR 1910.120) members of the response community envisioned a separation of oil and open-quotes hazmatclose quotes response operations. Organizations that deal with oil spills have had difficulty applying Hazwoper regulations to oil spill operations. This hinders meaningful implementation of the standard for their personnel. We should approach oil spills with the same degree of caution that is applied to hazmat response. Training frequently does not address the safety of oil spill response operations. Site-specific safety and health plans often are neglected or omitted. Certain oils expose workers to carcinogens, as well as chronic and acute hazards. Significant physical hazards are most important. In responding to oil spills, the hazards must be addressed. It is the authors' contention that a need exists for safety program at oil spill sites. Gone are the days of labor pool hires cleaning up spills in jeans and sneakers. The key to meaningful programs for oil spills requires application of controls focused on relevant safety risks rather than minimal chemical exposure hazards. Working with concerned reviewers from other agencies and organizations, the authors have developed a general safety and health program for oil spill response. It is intended to serve as the basis for organizations to customize their own written safety and health program (required by OSHA). It also provides a separate generic site safety plan for emergency phase oil spill operations (check-list) and long term post-emergency phase operations

Patient Safety in Spine Surgery: Regarding the Wrong-Site Surgery

OpenAIRE

Lee, Seung-Hwan; Kim, Ji-Sup; Jeong, Yoo-Chul; Kwak, Dae-Kyung; Chun, Ja-Hae; Lee, Hwan-Mo

2013-01-01

Patient safety regarding wrong site surgery has been one of the priority issues in surgical fields including that of spine care. Since the wrong-side surgery in the DM foot patient was reported on a public mass media in 1996, the wrong-site surgery issue has attracted wide public interest as regarding patient safety. Despite the many wrong-site surgery prevention campaigns in spine care such as the operate through your initial program by the Canadian Orthopaedic Association, the sign your sit...

Climate and climate-related issues for the safety assessment SR-Site

International Nuclear Information System (INIS)

2010-12-01

The purpose of this report is to document current scientific knowledge on climate and climate-related conditions, relevant to the long-term safety of a KBS-3 repository, to a level required for an adequate treatment in the safety assessment SR-Site. The report also presents a number of dedicated studies on climate and selected climate-related processes of relevance for the assessment of long term repository safety. Based on this information, the report presents a number of possible future climate developments for Forsmark, the site selected for building a repository for spent nuclear fuel in Sweden (Figure 1-1). The presented climate developments are used as basis for the selection and analysis of SR-Site safety assessment scenarios in the SR-Site main report /SKB 2011/. The present report is based on research conducted and published by SKB as well as on research reported in the general scientific literature

Climate and climate-related issues for the safety assessment SR-Site

Energy Technology Data Exchange (ETDEWEB)

2010-12-15

The purpose of this report is to document current scientific knowledge on climate and climate-related conditions, relevant to the long-term safety of a KBS-3 repository, to a level required for an adequate treatment in the safety assessment SR-Site. The report also presents a number of dedicated studies on climate and selected climate-related processes of relevance for the assessment of long term repository safety. Based on this information, the report presents a number of possible future climate developments for Forsmark, the site selected for building a repository for spent nuclear fuel in Sweden (Figure 1-1). The presented climate developments are used as basis for the selection and analysis of SR-Site safety assessment scenarios in the SR-Site main report /SKB 2011/. The present report is based on research conducted and published by SKB as well as on research reported in the general scientific literature

Developing the health, safety and environment excellence instrument.

Science.gov (United States)

Mohammadfam, Iraj; Saraji, Gebraeil Nasl; Kianfar, Ali; Mahmoudi, Shahram

2013-01-07

Quality and efficiency are important issues in management systems. To increase quality, to reach best results, to move towards the continuous improvement of system and also to make the internal and external customers satisfied, it is necessary to consider the system performance measurement. In this study the Health, Safety and Environment Excellence Instrument was represented as a performance measurement tool for a wide range of health, safety and environment management systems. In this article the development of the instrument overall structure, its parts, and its test results in three organizations are presented. According to the results, the scores ranking was the managership organization, the manufacturing company and the powerhouse construction project, respectively. The results of the instrument test in three organizations show that, on the whole, the instrument has the ability to measure the performance of health, safety and environment management systems in a wide range of organizations.

Environment, Safety and Health progress assessment of the Idaho National Engineering Laboratory (INEL)

International Nuclear Information System (INIS)

1993-08-01

The ES ampersand H Progress Assessments are part of the Department's continuous improvement process throughout DOE and its contractor organizations. The purpose of the INEL ES ampersand H Progress Assessment is to provide the Department with concise independent information on the following: (1) change in culture and attitude related to ES ampersand H activities; (2) progress and effectiveness of the ES ampersand H corrective actions resulting from previous Tiger Team Assessments; (3) adequacy and effectiveness of the ES ampersand H self-assessment programs of the DOE line organizations and the site management and operating contractor; and (4) effectiveness of DOE and contractor management structures, resources, and systems to effectively address ES ampersand H problems. It is not intended that this Progress Assessment be a comprehensive compliance assessments of ES ampersand H activities. The points of reference for assessing programs at the INEL were, for the most part, the 1991 INEL Tiger Team Assessment, the INEL Corrective Action Plan, and recent appraisals and self-assessments of INEL. Horizontal and vertical reviews of the following programmatic areas were conducted: Management: Corrective action program; self-assessment; oversight; directives, policies, and procedures; human resources management; and planning, budgeting, and resource allocation. Environment: Air quality management, surface water management, groundwater protection, and environmental radiation. Safety and Health: Construction safety, worker safety and OSHA, maintenance, packaging and transportation, site/facility safety review, and industrial hygiene

Radionuclide transport report for the safety assessment SR-Site

Energy Technology Data Exchange (ETDEWEB)

2010-12-15

This document compiles radionuclide transport calculations of a KBS-3 repository for the safety assessment SR-Site. The SR-Site assessment supports the licence application for a final repository at Forsmark, Sweden

Code on the safety of nuclear power plants: Siting

International Nuclear Information System (INIS)

1988-01-01

This Code provides criteria and procedures that are recommended for safety in nuclear power plant siting. It forms part of the Agency's programme for establishing Codes and Safety Guides relating to land based stationary thermal neutron power plants

Management of construction safety at KKNPP site

International Nuclear Information System (INIS)

Khare, P.K.

2016-01-01

Construction is considered as one of the most hazardous activities owing to the number of accidents and injuries. At KKNPP, management of industrial safety has been envisaged since the preliminary stage of construction planning, including design aspects. The governing principles of safety management are evolved from the Factories Act, 1948, the Atomic Energy(Factories) Rules, 1996, AERB safety guidelines on Control of works (2011) and Corporate HSE policy of NPCIL (2014). Numerous risk assessment and hazard control measures are adopted consistently to ensure a safe work environment during the construction, which includes Job Hazard Analysis, work permit through Computerized Maintenance Management System, safety procedures, exclusive safety training facility for the contractor's workmen, safety motivational measures, safety surveillance and reporting through Safety Related Deficiencies Management System. Assessment of efficacy of safety management system is continuously done through safety audits and observations are being circulated and discussed in committee meetings. Fire safety is also being taken care of since inception of project work. Well-equipped fire station with trained fire fighters was made available since the beginning as per AERB safety standard on fire protection system for Nuclear facilities. Fire prevention measures specific to the work are implemented during all activities. (author)

Development and Application of SITES

International Nuclear Information System (INIS)

Park, Jo Wan; Yoon; Yoon, Jeong Hyoun; Kim, Chank Lak; Cho, Sung IL

2008-01-01

SITES (Site Information and Total Environmental Data Management System) has been developed for the purpose of systematically managing site characteristics and environmental data produced during the pre-operational, operational, and post-closure phases of a radioactive waste disposal facility. SITES is an integration system, which consists of 4 modules, to be available for maintenance of site characteristics data, for safety assessment, and for site/environment monitoring; site environmental data management module (SECURE), integrated safety assessment module (SAINT), site/environment monitoring module (SUDAL) and geological information module for geological data management (SITES-GIS). Each module has its database with the functions of browsing, storing, and reporting data and information. Data from SECURE and SUDAL are interconnected to be utilized as inputs to SAINT. SAINT has the functions that multi-user can access simultaneously via client-server system, and the safety assessment results can be managed with its embedded Quality Assurance feature. Comparison between assessment results and environmental monitoring data can be made and visualized in SUDAL and SITES-GIS. Also, SUDAL is designed that the periodic monitoring data and information could be opened to the public via internet homepage. SITES has applied to the Wolsong low- and intermediate-level radioactive waste disposal center in Korea, and is expected to enhance the function of site/environment monitoring in other nuclear-related facilities and also in industrial facilities handling hazardous materials.

Safety issues and updates under MR environments

Energy Technology Data Exchange (ETDEWEB)

Kim, Soo Jung; Kim, Kyung Ah, E-mail: bellenina@daum.net

2017-04-15

Highlights: • Unexpected biological effects can occur within stronger magnetic fields. • MR safety for MR conditional items is not guaranteed beyond the tested conditions. • Updated knowledge about MR-related safety is important for a safe MR environment. - Abstract: Magnetic resonance (MR) imaging is a useful imaging tool with superior soft tissue contrast for diagnostic evaluation. The MR environments poses unique risks to patients and employees differently from ionizing radiation exposure originated from computed tomography and plain x-ray films. The technology associated with MR system has evolved continuously since its introduction in the late 1970s. MR systems have advanced with static magnetic fields, faster and stronger gradient magnetic fields and more powerful radiofrequency transmission coils. Higher field strengths of MR offers greater signal to noise capability and better spatial resolution, resulting in better visualization of anatomic detail, with a reduction in scan time. With the rapid evolution of technology associated with MR, we encounter new MR-related circumstances and unexpected dangerous conditions. A comprehensive update of our knowledge about MR safety is necessary to prevent MR-related accidents and to ensure safety for patients and staff associated with MR. This review presents an overview about MR-related safety issues and updates.

Seismic Hazards in Site Evaluation for Nuclear Installations. Specific Safety Guide

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-08-15

This Safety Guide was prepared under the IAEA programme for safety standards for nuclear installations. It supplements the Safety Requirements publication on Site Evaluation for Nuclear Installations. The present publication provides guidance and recommends procedures for the evaluation of seismic hazards for nuclear power plants and other nuclear installations. It supersedes Evaluation of Seismic Hazards for Nuclear Power Plants, IAEA Safety Standards Series No. NS-G-3.3 (2002). In this publication, the following was taken into account: the need for seismic hazard curves and ground motion spectra for the probabilistic safety assessment of external events for new and existing nuclear installations; feedback of information from IAEA reviews of seismic safety studies for nuclear installations performed over the previous decade; collective knowledge gained from recent significant earthquakes; and new approaches in methods of analysis, particularly in the areas of probabilistic seismic hazard analysis and strong motion simulation. In the evaluation of a site for a nuclear installation, engineering solutions will generally be available to mitigate, by means of certain design features, the potential vibratory effects of earthquakes. However, such solutions cannot always be demonstrated to be adequate for mitigating the effects of phenomena of significant permanent ground displacement such as surface faulting, subsidence, ground collapse or fault creep. The objective of this Safety Guide is to provide recommendations and guidance on evaluating seismic hazards at a nuclear installation site and, in particular, on how to determine: (a) the vibratory ground motion hazards, in order to establish the design basis ground motions and other relevant parameters for both new and existing nuclear installations; and (b) the potential for fault displacement and the rate of fault displacement that could affect the feasibility of the site or the safe operation of the installation at

Information report on nuclear safety and radiation protection of La Hague AREVA site. Issue 2014

International Nuclear Information System (INIS)

2013-01-01

Published in compliance with the French code of the environment, this report first presents the Areva's La Hague site which comprises several basic nuclear installations (INB), is dedicated to several activities related to the nuclear fuel cycle, is submitted to a constraining legal and regulatory framework, and implements a policy for a sustainable development and continuous progress. The document describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which are classified according to the INES scale and occurred and had to be declared in 2014, describes the management of effluents by the different installations present on this site and the control of the environment. It addresses the waste management and the management of other impacts. It gives an overview of actions undertaken regarding information and transparency. Recommendations of the CHSCT are reported

Information report on nuclear safety and radiation protection of La Hague AREVA site. Issue 2013

International Nuclear Information System (INIS)

2014-01-01

Published in compliance with the French code of the environment, this report first presents the Areva's La Hague site which comprises several basic nuclear installations (INB), is dedicated to several activities related to the nuclear fuel cycle, is submitted to a constraining legal and regulatory framework, and implements a policy for a sustainable development and continuous progress. The document describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which are classified according to the INES scale and occurred and had to be declared in 2013, describes the management of effluents by the different installations present on this site and the control of the environment. It addresses the waste management and the management of other impacts. It gives an overview of actions undertaken regarding information and transparency. Recommendations of the CHSCT are reported

LANL Safety Conscious Work Environment (SCWE) Self-Assessment

Energy Technology Data Exchange (ETDEWEB)

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

2014-01-29

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

Monitoring product safety in the postmarketing environment.

Science.gov (United States)

Sharrar, Robert G; Dieck, Gretchen S

2013-10-01

The safety profile of a medicinal product may change in the postmarketing environment. Safety issues not identified in clinical development may be seen and need to be evaluated. Methods of evaluating spontaneous adverse experience reports and identifying new safety risks include a review of individual reports, a review of a frequency distribution of a list of the adverse experiences, the development and analysis of a case series, and various ways of examining the database for signals of disproportionality, which may suggest a possible association. Regulatory agencies monitor product safety through a variety of mechanisms including signal detection of the adverse experience safety reports in databases and by requiring and monitoring risk management plans, periodic safety update reports and postauthorization safety studies. The United States Food and Drug Administration is working with public, academic and private entities to develop methods for using large electronic databases to actively monitor product safety. Important identified risks will have to be evaluated through observational studies and registries.

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

Environment, safety and health progress assessment manual

International Nuclear Information System (INIS)

1992-12-01

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

Design and implementation of an identification system in construction site safety for proactive accident prevention.

Science.gov (United States)

Yang, Huanjia; Chew, David A S; Wu, Weiwei; Zhou, Zhipeng; Li, Qiming

2012-09-01

Identifying accident precursors using real-time identity information has great potential to improve safety performance in construction industry, which is still suffering from day to day records of accident fatality and injury. Based on the requirements analysis for identifying precursor and the discussion of enabling technology solutions for acquiring and sharing real-time automatic identification information on construction site, this paper proposes an identification system design for proactive accident prevention to improve construction site safety. Firstly, a case study is conducted to analyze the automatic identification requirements for identifying accident precursors in construction site. Results show that it mainly consists of three aspects, namely access control, training and inspection information and operation authority. The system is then designed to fulfill these requirements based on ZigBee enabled wireless sensor network (WSN), radio frequency identification (RFID) technology and an integrated ZigBee RFID sensor network structure. At the same time, an information database is also designed and implemented, which includes 15 tables, 54 queries and several reports and forms. In the end, a demonstration system based on the proposed system design is developed as a proof of concept prototype. The contributions of this study include the requirement analysis and technical design of a real-time identity information tracking solution for proactive accident prevention on construction sites. The technical solution proposed in this paper has a significant importance in improving safety performance on construction sites. Moreover, this study can serve as a reference design for future system integrations where more functions, such as environment monitoring and location tracking, can be added. Copyright © 2011 Elsevier Ltd. All rights reserved.

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

Fuel and canister process report for the safety assessment SR-Site

International Nuclear Information System (INIS)

Werme, Lars; Lilja, Christina

2010-12-01

This report documents fuel and canister processes identified as relevant to the long-term safety of a KBS-3 repository. It forms an important part of the reporting of the safety assessment SR-Site. The detailed assessment methodology, including the role of the process reports in the assessment, is described in the SR-Site Main report /SKB 2011/

Fuel and canister process report for the safety assessment SR-Site

Energy Technology Data Exchange (ETDEWEB)

Werme, Lars; Lilja, Christina (eds.)

2010-12-15

This report documents fuel and canister processes identified as relevant to the long-term safety of a KBS-3 repository. It forms an important part of the reporting of the safety assessment SR-Site. The detailed assessment methodology, including the role of the process reports in the assessment, is described in the SR-Site Main report /SKB 2011/

Use of safety analysis to site comfirmation procedure in case of hard rock repository

International Nuclear Information System (INIS)

Peltonen, E.K.

1984-02-01

The role of safety analysis in a confirmation procedure of a candidate disposal site of radioactive wastes is discussed. Items dealt with include principle reasons and practical goals of the use of safety analysis, methodology of safety analysis and assessment, as well as usefulness and adequacy of the present safety analysis. Safety analysis is a tool, which enables one to estimate quantitatively the possible radiological impacts from the disposal. The results can be compared with the criteria and the suitability conclusions drawn. Because of its systems analytical nature safety analysis is an effective method to reveal, what are the most important factors of the disposal system and the most critical site characteristics inside the lumped parameters often provided by the experimental site investigation methods. Furthermore it gives information on the accuracy needs of different site properties. This can be utilized to judge whether the quality and quantity of the measurements for the characterization are sufficient as well as to guide the further site investigations. A more practical discussion regarding the applicability of the use of safety analysis is presented by an example concerning the assessment of a Finnish candidate site for low- and intermediate-level radioactive waste repository. (author)

Safety assessment of multi-unit NPP sites subject to external events

International Nuclear Information System (INIS)

Samaddar, Sujit; Hibino, Kenta; Coman, Ovidiu

2014-01-01

This paper presents a framework for conducting a probabilistic safety assessment of multi-unit sites against external events. The treatment of multiple hazard on a unit, interaction between units, implementation of severe accident measures, human reliability, environmental conditions, metric of risk for both reactor and non-reactor sources, integration of risk and responses and many such important factors need to be addressed within the context of this framework. The framework facilitates the establishment of a comprehensive methodology that can be applied internationally to the peer review of safety assessment of multi-unit sites under the impact of multiple external hazards. In summary, it can be said that the site safety assessment for a multi-unit site will be quite complex and need to start with individual unit risk assessments, these need to be combined considering the interactions between units and their responses, and the fragilities of the installations established considering the combined demands from all interactions. Using newly established risk metric the risk can then be integrated for the overall site. Fig. 2 shows schematically such a proposal. Much work has to done and the IAEA has established a working group that is systematically establishing the structure and process to incorporate the many issues that are a part of a multi-unit site safety assessment. (authors)

Radioiodine in the Savannah River Site environment

Energy Technology Data Exchange (ETDEWEB)

Kantelo, M.V.; Bauer, L.R.; Marter, W.L.; Murphy, C.E. Jr.; Zeigler, C.C.

1993-01-15

Radioiodine, which is the collective term for all radioactive isotopes of the element iodine, is formed at the Savannah River Site (SRS) principally as a by-product of nuclear reactor operations. Part of the radioiodine is released to the environment during reactor and reprocessing operations at the site. The purpose of this report is to provide an introduction to radioiodine production and disposition, its status in the environment, and the radiation dose and health risks as a consequence of its release to the environment around the Savannah River Plant. A rigorous dose reconstruction study is to be completed by thee Center for Disease Control during the 1990s.

Radioiodine in the Savannah River Site environment

International Nuclear Information System (INIS)

Kantelo, M.V.; Bauer, L.R.; Marter, W.L.; Murphy, C.E. Jr.; Zeigler, C.C.

1993-01-01

Radioiodine, which is the collective term for all radioactive isotopes of the element iodine, is formed at the Savannah River Site (SRS) principally as a by-product of nuclear reactor operations. Part of the radioiodine is released to the environment during reactor and reprocessing operations at the site. The purpose of this report is to provide an introduction to radioiodine production and disposition, its status in the environment, and the radiation dose and health risks as a consequence of its release to the environment around the Savannah River Plant. A rigorous dose reconstruction study is to be completed by thee Center for Disease Control during the 1990s

Safety level assessment in the production environment using Fuzzy logic

Directory of Open Access Journals (Sweden)

2012-05-01

Conclusion: The application of the proposed method can reveal which safety items and factors are most important in improving workers safety, and therefore decide where to concentrate resources in order to improve the safety of the work environment.

Occupational health and safety in the Moroccan construction sites: preliminary diagnosis

Science.gov (United States)

Tarik, Bakeli; Adil, Hafidi Alaoui

2018-05-01

Managing occupational health and safety on Moroccan construction sector represents the first step for projects' success. In fact, by avoiding accidents, all the related direct and indirect costs and delays can be prevented. That leads to an important question always asked by any project manager: what are the factors responsible for accidents? How can they be avoided? Through this research, the aim is to go through these questions, to contribute in occupational health and safety principles understanding, to identify construction accidentology and risk management opportunities and to approach the case of Moroccan construction sites by an accurate diagnosis. The approach is to make researchers, managers, stakeholders and deciders aware about the criticality of construction sites health and safety situation. And, to do the first step for a scientific research project in relation with health and safety in the Moroccan construction sector. For this, the paper will study the related state of art namely about construction sites accidents causation, and will focus on Reason's `Swiss cheese' model and its utilization for Moroccan construction sites health and safety diagnosis. The research will end with an estimation of an accidents fatality rate in the Moroccan construction sector and a benchmarking with the international rates. Finally, conclusions will be presented about the necessity of Occupational Health and Safety Management System (OHSMS) implementation, which shall cover all risk levels, and insure, at the same time, that the necessary defenses against accidents are on place.

Probabilistic and deterministic safety study of the transportation of liquefied gases in the vicinity of a nuclear site

International Nuclear Information System (INIS)

Gobert, T.; Lannoy, A.

1982-01-01

The safety analyses for nuclear power plants devotes special attention to the evaluation of hazards which may be induced by industrial activity in the environment of nuclear sites. For instance, explosion of a drifting gas cloud resulting from an accidental release of liquefied gas may jeopardize the plant safety. The paper presents the methodology, both probabilistic and deterministic, followed by Electricite de France to evaluate these risks. It particularly shows that the probabilistic approach is strongly linked with the definition of ''design basis accidents'' and the evaluation of their effects

Information report on nuclear safety and radiation protection of the La Hague AREVA site- Issue 2012

International Nuclear Information System (INIS)

2013-06-01

Published in compliance with the French code of the environment, this report first presents the Areva's La Hague site which comprises several basis nuclear installations (INB), is dedicated to several activities related to the nuclear fuel cycle, is submitted to a constraining legal and regulatory framework, and implements a policy for a sustainable development and continuous progress. The document describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which are classified according to the INES scale and occurred and had to be declared in 2012, describes the management of effluents by the different installations present on this site and the control of the environment. It addresses the waste management and the management of other impacts. It gives an overview of actions undertaken regarding information and transparency. Recommendations of the CHSCT are reported

Oskarshamn site investigation. Programme for further investigations of bedrock, soil, water and environment in Laxemar subarea

International Nuclear Information System (INIS)

2006-03-01

SKB (the Swedish Nuclear Fuel and Waste Management Co), has been conducting a site investigation at Simpevarp and Laxemar in Oskarshamn for siting of a final repository for spent nuclear fuel. An equivalent investigation is being conducted in Forsmark in Ohmmeter's. The initial part of the site investigations had been completed for the both of the subareas Simpevarp and Laxemar in the autumn of 2004. Based on the results of these investigations, SKB preliminarily prioritized the Laxemar subarea for further investigations. A programme was presented for the first stage of the complete site investigation in the Laxemar subarea, along with the main features of the remainder of the site investigation. The programme included investigations up until the summer of 2005 and was particularly aimed at obtaining answers to several vital questions so that the subsequent investigations could be focused on the rock areas judged to be most suitable for a final repository. These investigations have now been completed. This report presents the programme for the remainder of the site investigation. The points of departure are the general goals for the Deep Repository Project during the site investigation phase, analyses and evaluations of data from completed investigations, and the needs for additional data to be able to evaluate the site as a siting alternative for the final repository. The account mainly covers the investigations on the site. All other work - analyses, site descriptive modelling, facility design, safety assessments and studies and assessments of consequences for the environment, human health and society - are only mentioned to the extent necessary in order to place the investigations in their context. The direction of the site investigation in Oskarshamn and the investigation programme presented in this report is based on SKB's preliminary decision to prioritize the Laxemar subarea for further investigations. A final decision on the direction of the site

Scenarios used for the evaluations of the safety of a site for adioactive waste disposal in deep geologic formations

International Nuclear Information System (INIS)

Escalier des Orres, P.; Devillers, C.; Cernes, A.

1989-11-01

The selection and qualification procedure of a site for radioactive wastes disposal in a deep geologic formation, has begun in France in the early eighties. The public authorities, on ANDRA's proposal, has preselected in 1987 four sites, each of them coppresponding to a type, of geologic formations (granite, clay, salt and shale). Within two years, one of these sites will be chosen for the location of an undergound laboratory. The safety analysis for the site's qualification uses evolution scenarios of the repository and its environment, chosen according to a deterministic method. With an appropriate detail level, are defined a reference scenario and scenario with random events [fr

Safety Report within the licence application for the siting of a radioactive waste repository/disposal facility

International Nuclear Information System (INIS)

Horyna, J.; Sinaglova, R.

2004-01-01

The initial safety specification report, which is submitted to the licensing authority as one of the application documents, is the basic document assessing the planned repository/disposal facility with respect to the suitability of the chosen site for this purpose. The following topics are covered: General information; Description and evidence of suitability of the site chosen; Description and tentative assessment of the repository/disposal facility design; Tentative assessment of impacts of running the facility on the employees, general public and environment (radionuclide inventory, transport routes, radionuclide release in normal, abnormal and emergency situations); Proposed concept of repository/disposal facility shutdown; and Assessment of quality assurance in the site selection, in preparatory work for the construction of the facility and in the subsequent stages. (P.A.)

Global positioning site environment evaluator

International Nuclear Information System (INIS)

Leffler, S.; Reeser, H.G.; Zaker, E.; Hansen, W.; Sikorski, R.W.

1990-01-01

Development of an innovative, integrated, automated system (Global Positioning Site Environment Evaluator - GPSEETM) for surveying contaminated waste sites is described. This system makes novel use of the Global Positioning System (GPS) satellite constellation for establishing specific locations and current times for surveying radioactive, hazardous, or mixed-waste sites. GPSEE may also be used for waste site contamination surveys after remediation activities to ensure environmental remediation is complete. A base station is established for collecting and recording data and directing field operations for field stations which may be located many miles from the base station. The field operators collect site surveying and contamination data utilizing a variety of chemical and radiological sensors. A major goal for the data collection process is to collect all data utilizing in situ sensors, thereby minimizing the need for collecting soil and water samples. Site contamination data is transmitted electronically to the base station for recording and processing. The GPSEE system is being developed for use at DOE/DOD and a variety of industrial facilities. 3 figs

Methodology for calculating guideline concentrations for safety shot sites

International Nuclear Information System (INIS)

1997-06-01

Residual plutonium (Pu), with trace quantities of depleted uranium (DU) or weapons grade uranium (WU), exists in surficial soils at the Nevada Test Site (NTS), Nellis Air Force Range (NAFR), and the Tonopah Test Range (TTR) as the result of the above-ground testing of nuclear weapons and special experiments involving the detonation of plutonium-bearing devices. The special experiments (referred to as safety shots) involving plutonium-bearing devices were conducted to study the behavior of Pu as it was being explosively compressed; ensure that the accidental detonation of the chemical explosive in a production weapon would not result in criticality; evaluate the ability of personnel to manage large-scale Pu dispersal accidents; and develop criteria for transportation and storage of nuclear weapons. These sites do not pose a health threat to either workers or the general public because they are under active institutional control. The DOE is committed to remediating the safety shot sites so that radiation exposure to the public, both now and in the future, will be maintained within the established limits and be as low as reasonably achievable. Remediation requires calculation of a guideline concentration for the Pu, U, and their decay products that are present in the surface soil. This document presents the methodology for calculating guideline concentrations of weapons grade plutonium, weapons grade uranium, and depleted uranium in surface soils at the safety shot sites. Emphasis is placed on obtaining site-specific data for use in calculating dose to potential residents from the residual soil contamination

Methodology for calculating guideline concentrations for safety shot sites

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-06-01

Residual plutonium (Pu), with trace quantities of depleted uranium (DU) or weapons grade uranium (WU), exists in surficial soils at the Nevada Test Site (NTS), Nellis Air Force Range (NAFR), and the Tonopah Test Range (TTR) as the result of the above-ground testing of nuclear weapons and special experiments involving the detonation of plutonium-bearing devices. The special experiments (referred to as safety shots) involving plutonium-bearing devices were conducted to study the behavior of Pu as it was being explosively compressed; ensure that the accidental detonation of the chemical explosive in a production weapon would not result in criticality; evaluate the ability of personnel to manage large-scale Pu dispersal accidents; and develop criteria for transportation and storage of nuclear weapons. These sites do not pose a health threat to either workers or the general public because they are under active institutional control. The DOE is committed to remediating the safety shot sites so that radiation exposure to the public, both now and in the future, will be maintained within the established limits and be as low as reasonably achievable. Remediation requires calculation of a guideline concentration for the Pu, U, and their decay products that are present in the surface soil. This document presents the methodology for calculating guideline concentrations of weapons grade plutonium, weapons grade uranium, and depleted uranium in surface soils at the safety shot sites. Emphasis is placed on obtaining site-specific data for use in calculating dose to potential residents from the residual soil contamination.

Promoting Safety Environment for School Sports | Aluko | AFRREV ...

African Journals Online (AJOL)

The purpose of this study was to examine the safety environment under which school sports programme is organized in Nigeria schools. The paper noted that poor environment under which PES is administered militated against smooth attainment of physical education and sports in schools. In this regard the paper explored ...

Savannah River Site K-Reactor Probabilistic Safety Assessment

International Nuclear Information System (INIS)

Brandyberry, M.D.; Bailey, R.T.; Baker, W.H.; Kearnaghan, D.P.; O'Kula, K.R.; Wittman, R.S.; Woody, N.D.; Amos, C.N.; Weingardt, J.J.

1992-12-01

This report gives the results of a Savannah River Site (SRS) K-Reactor Probabilistic Safety Assessment (PSA). Measures of adverse consequences to health and safety resulting from representations of severe accidents in SRS reactors are presented. In addition, the report gives a summary of the methods employed to represent these accidents and to assess the resultant consequences. The report is issued to provide useful information to the U. S. Department of Energy (DOE) on the risk of operation of SRS reactors, for insights into severe accident phenomena that contribute to this risk, and in support of improved bases for other DOE programs in Heavy Water Reactor safety

Tiger Team Assessment of the Savannah River Site

International Nuclear Information System (INIS)

1990-06-01

This draft document contains findings identified during the Tiger Team Compliance Assessment of the US Department of Energy Savannah River Site (SRS), located in three counties (Aiken, Barnwell and Allendale), South Carolina. The Assessment was directed by the Department's Office of the Assistant Secretary for Environment, Safety, and Health (ES ampersand H) and was conducted from January 29 to March 23, 1990. The Savannah River Site Tiger Team Compliance Assessment was broad in scope covering the Environment, Safety and Health, and Management areas and was designed to determine the site's compliance with applicable Federal (including DOE), state, and local regulations and requirements. The scope of the Environmental assessment was sitewide while the Safety and Health assessments included site operating facilities (except reactors), and the sitewide elements of Aviation Safety, Emergency Preparedness, Medical Services, and Packaging and Transportation

Approach of the safety of nuclear sites

International Nuclear Information System (INIS)

Faure, J.

1991-08-01

The implantation on a site of nuclear power plant, nuclear facility, laboratory or nuclear waste storage, or more generally a risk facility, require to take into account the aggression of the environment on the facility (earth quakes, explosions, inundations, aircraft crash...) and dangers presented by the facility on the environment (radioactive release, noise...). The consequences of releases on the environment aim to study and also the characteristics of the environment to evaluate the consequences in normal and accidental conditions [fr

Occupational Safety and Related Impacts on Health  and the Environment.

Science.gov (United States)

Watterson, Andrew

2016-10-05

The inter-relationship between safety, health and the 'environment' is a complex and at times a relatively neglected topic. In this issue, 'safety' is often viewed by contributors as 'health and safety' and includes occupationally-related ill health as well as injury or harm to employees and the wider public. 'Environment' is also interpreted in the widest sense covering both physical and work environments with upstream work hazards presenting risks to downstream communities. The focus is very much on exploring and where possible addressing the challenges, some old and some facing workers in a range of public and private settings and also at times their nearby communities. The 19 papers in the issue cover public and private sectors, global and very local populations, macro-theoretical perspectives, large epidemiological and some single factory or hospital site small case studies. A number of the papers are just beginning to explore and draw out for the first time the risks from hazards in their part of the world. The methodologies adopted also range from lab-based studies through ergonomic assessments and interventions to therapeutic approaches.

Pilot research on a pupil’s psychological safety in the multicultural educational environment

Directory of Open Access Journals (Sweden)

Kulikova, Tatyana I.

2016-09-01

Full Text Available In the modern world, the environment of any educational institution represents a spectrum of ethnic groups and subcultures: a multicultural educational environment. Pupils who are aware of their national identity often demonstrate intolerance toward students of other nationalities, which threatens pupils’ psychological safety. In this article, we present the results of pilot research examining the level of a pupil’s psychological safety in the multicultural educational environment and identifying the criteria that influence a pupil’s psychological safety. The research sample comprised 127 pupils aged 13–14 years from different schools living in various places that differed by the type of settlement, industrial development and level of science and culture. We isolated the following criteria for a pupil’s psychological safety in the multicultural educational environment: satisfaction with the educational environment, protection from psychological abuse and self-confidence. According to pupils, the essential characteristics of safety in the educational environment, regardless of school category and type, are being able to ask for help, protection of personal dignity, interactions with other students, and self-respect. Empirical data reveal the current status of the psychological safety of the entire sample group (n = 127 and compare indices of psychological safety in the educational institutions under study. Analysis of the results of our research indicates that protecting a pupil’s personality in the multicultural educational environment has the greatest influence on his/her psychological safety. In addition, a comfortable psychological atmosphere, mutual aid and support of pupils and low levels of classmates’ and coevals’ aggression positively influence the protection experience.

Environment Health & Safety Research Program. Organization and 1979-1980 Publications

Energy Technology Data Exchange (ETDEWEB)

None

1981-01-01

This document was prepared to assist readers in understanding the organization of Pacific Northwest Laboratory, and the organization and functions of the Environment, Health and Safety Research Program Office. Telephone numbers of the principal management staff are provided. Also included is a list of 1979 and 1980 publications reporting on work performed in the Environment, Health and Safety Research Program, as well as a list of papers submitted for publication.

Organizational culture and a safety-conscious work environment: The mediating role of employee communication satisfaction.

Science.gov (United States)

Silla, Inmaculada; Navajas, Joaquin; Koves, G Kenneth

2017-06-01

A safety-conscious work environment allows high-reliability organizations to be proactive regarding safety and enables employees to feel free to report any concern without fear of retaliation. Currently, research on the antecedents to safety-conscious work environments is scarce. Structural equation modeling was applied to test the mediating role of employee communication satisfaction in the relationship between constructive culture and a safety-conscious work environment in several nuclear power plants. Employee communication satisfaction partially mediated the positive relationships between a constructive culture and a safety-conscious work environment. Constructive cultures in which cooperation, supportive relationships, individual growth and high performance are encouraged facilitate the establishment of a safety-conscious work environment. This influence is partially explained by increased employee communication satisfaction. Constructive cultures should be encouraged within organizations. In addition, managers should promote communication policies and practices that support a safety-conscious work environment. Copyright © 2017 Elsevier Ltd and National Safety Council. All rights reserved.

Oak Ridge National Laboratory site data for safety-analysis report

International Nuclear Information System (INIS)

Fitzpatrick, F.C.

1982-12-01

The Oak Ridge National Laboratory site data contained herein were compiled in support of the United States Department of Energy (USDOE) Oak Ridge Operations Office Order OR 5481.1. That order sets forth assignment of responsibilities for safety analysis and review responsibilities and provides guidance relative to the content and format of safety analysis reports. The information presented in this document is intended for use by reference in individual safety analysis reports where applicable to support accident analyses or the establishment of design bases of significance to safety, and it is applicable only to Oak Ridge National Laboratory facilities in Bethel and Melton Valleys. This information includes broad descriptions of the site characteristics, radioactive waste handling and monitoring practices, and the organization and operating policies at Oak Ridge National Laboratory. The historical background of the Laboratory is discussed briefly and the overall physical situation of the facilities is described in the following paragraphs

Oak Ridge National Laboratory site data for safety-analysis report

Energy Technology Data Exchange (ETDEWEB)

Fitzpatrick, F.C.

1982-12-01

The Oak Ridge National Laboratory site data contained herein were compiled in support of the United States Department of Energy (USDOE) Oak Ridge Operations Office Order OR 5481.1. That order sets forth assignment of responsibilities for safety analysis and review responsibilities and provides guidance relative to the content and format of safety analysis reports. The information presented in this document is intended for use by reference in individual safety analysis reports where applicable to support accident analyses or the establishment of design bases of significance to safety, and it is applicable only to Oak Ridge National Laboratory facilities in Bethel and Melton Valleys. This information includes broad descriptions of the site characteristics, radioactive waste handling and monitoring practices, and the organization and operating policies at Oak Ridge National Laboratory. The historical background of the Laboratory is discussed briefly and the overall physical situation of the facilities is described in the following paragraphs.

The role of safety analyses in site selection. Some personal observations based on the experience from the Swiss site selection process

Energy Technology Data Exchange (ETDEWEB)

Zuidema, Piet [Nagra, Wettingen (Switzerland)

2015-07-01

In Switzerland, the site selection process according to the ''Sectoral Plan for Deep Geological Repositories'' (BFE 2008) is underway since 2008. This process takes place in three stages. In stage 1 geological siting regions (six for the L/ILW repository and three for the HLW repository) have been identified, in stage 2 sites for the surface facilities have been identified for all siting regions in close co-operation with the sting regions and a narrowing down of the number of siting regions based on geological criteria will take place. In stage 3 the sites for a general license application are selected and the general license applications will be submitted which eventually will lead to the siting decision for both repository types. In the Swiss site selection process, safety has the highest priority. Many factors affect safety and thus a whole range of safety-related issues are considered in the identification and screening of siting possibilities. Besides dose calculations a range of quantitative and qualitative issues are considered. Dose calculations are performed in all three stages of the site selection process. In stage 1 generic safety calculations were made to develop criteria to be used for the identification of potential siting regions. In stage 2, dose calculations are made for comparing the different siting regions according to a procedure prescribed in detail by the regulator. Combined with qualitative evaluations this will lead to a narrowing down of the number of siting regions to at least two siting regions for each repository type. In stage 3 full safety cases will be prepared as part of the documentation for the general license applications. Besides the dose calculations, many other issues related to safety are analyzed in a quantitative and qualitative manner. These consider the 13 criteria defined in the Sectoral Plan and the corresponding indicators. The features analyzed cover the following broad themes: efficiency of

The role of safety analyses in site selection. Some personal observations based on the experience from the Swiss site selection process

International Nuclear Information System (INIS)

Zuidema, Piet

2015-01-01

In Switzerland, the site selection process according to the ''Sectoral Plan for Deep Geological Repositories'' (BFE 2008) is underway since 2008. This process takes place in three stages. In stage 1 geological siting regions (six for the L/ILW repository and three for the HLW repository) have been identified, in stage 2 sites for the surface facilities have been identified for all siting regions in close co-operation with the sting regions and a narrowing down of the number of siting regions based on geological criteria will take place. In stage 3 the sites for a general license application are selected and the general license applications will be submitted which eventually will lead to the siting decision for both repository types. In the Swiss site selection process, safety has the highest priority. Many factors affect safety and thus a whole range of safety-related issues are considered in the identification and screening of siting possibilities. Besides dose calculations a range of quantitative and qualitative issues are considered. Dose calculations are performed in all three stages of the site selection process. In stage 1 generic safety calculations were made to develop criteria to be used for the identification of potential siting regions. In stage 2, dose calculations are made for comparing the different siting regions according to a procedure prescribed in detail by the regulator. Combined with qualitative evaluations this will lead to a narrowing down of the number of siting regions to at least two siting regions for each repository type. In stage 3 full safety cases will be prepared as part of the documentation for the general license applications. Besides the dose calculations, many other issues related to safety are analyzed in a quantitative and qualitative manner. These consider the 13 criteria defined in the Sectoral Plan and the corresponding indicators. The features analyzed cover the following broad themes: efficiency of

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

Integrating environment health and safety management at Petro-Canada

International Nuclear Information System (INIS)

Raymond, G.

1993-01-01

Petro-Canada has developed a tool to integrate, measure, and improve its management systems of environment, health, and safety (EH ampersand S). This tool, called the Total Loss Management System, is described in the areas of general management issues, policies and procedures, evaluations, organization, stewardship, issue management, and performance measures. Petro-Canada's policies on occupational health and safety are consistent with its environmental policy, being structured in the same way. An integrated audit system is used to cover health, safety, industrial hygiene, reliability, environment, and risk management. EH ampersand S matters are integrated at the corporate level in a separate department. Regional divisions review EH ampersand S performance every month, incidents are discussed, and preventive measures are taken as necessary. Regional performances are combined every quarter for ultimate presentation to the Petro-Canada board. New or emerging issues that may affect divisions are assigned an issue sponsor, a member of divisional management who makes sure the issue receives the resources necessary to study and define its impact. Examples of issues include soil contamination, process hazard management, and benzene exposure limits. Performance measures flow from the corporate environment and occupational health and safety policies, and come in two types: those that measure activities to improve performance and those that measure the outcome of the activities

Requirements on information of the site of the European Union from member states within the area of the environment

International Nuclear Information System (INIS)

Virgovic, R.; Grofova, R; Sochorova, O.

2005-01-01

In this presentation authors deal with requirements on information of the site of the European Union from member states within the area of the environment. As of May 1, 2004 with entrance into the European Union for the Slovak Republic results the responsibility feeding reports about the environment. Reports about the environment (State of the environment Report - Slovak Republic) deal with the following areas: (A) Horizontally measures; (B) Air protection; (C) Waste management; (D) Water protection; (E) Nature protection; (F) Inspection of industrial pollution and risk management; (G) Chemical agents and genetically modified organisms; (H) Noise from motor-cars and machines; (I) Nuclear safety; (J) Civil protection

Oskarshamn site investigation. Programme for further investigations of bedrock, soil, water and environment in Laxemar subarea

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-03-15

SKB (the Swedish Nuclear Fuel and Waste Management Co), has been conducting a site investigation at Simpevarp and Laxemar in Oskarshamn for siting of a final repository for spent nuclear fuel. An equivalent investigation is being conducted in Forsmark in Ohmmeter's. The initial part of the site investigations had been completed for the both of the subareas Simpevarp and Laxemar in the autumn of 2004. Based on the results of these investigations, SKB preliminarily prioritized the Laxemar subarea for further investigations. A programme was presented for the first stage of the complete site investigation in the Laxemar subarea, along with the main features of the remainder of the site investigation. The programme included investigations up until the summer of 2005 and was particularly aimed at obtaining answers to several vital questions so that the subsequent investigations could be focused on the rock areas judged to be most suitable for a final repository. These investigations have now been completed. This report presents the programme for the remainder of the site investigation. The points of departure are the general goals for the Deep Repository Project during the site investigation phase, analyses and evaluations of data from completed investigations, and the needs for additional data to be able to evaluate the site as a siting alternative for the final repository. The account mainly covers the investigations on the site. All other work - analyses, site descriptive modelling, facility design, safety assessments and studies and assessments of consequences for the environment, human health and society - are only mentioned to the extent necessary in order to place the investigations in their context. The direction of the site investigation in Oskarshamn and the investigation programme presented in this report is based on SKB's preliminary decision to prioritize the Laxemar subarea for further investigations. A final decision on the direction of the site

Promoting safety in the work environment: the role of internal marketing

OpenAIRE

2009-01-01

M.Comm. The process of creating a safe working environment for all has proved to be one of the most complex facets within an organisation. This may be attributed to the fact that there are so many elements involved in ensuring occupational safety. Not only has the individual employee a responsibility towards safety, including his or her attitude and risk-taking behaviour, but also does the organisation contribute towards this hazard-free environment in providing a culture where safety is r...

The CEA Cadarache site. Additional safety assessment with respect to the accident which occurred in the Fukushima-Daiichi nuclear power station

International Nuclear Information System (INIS)

2012-01-01

After a presentation of some characteristics of the CEA Cadarache site (internal and external industrial environment, crisis management organization at the CEA level and at the local level), this document reports the identification of structures and equipment concerned by crisis management (site support functions, critical structures and equipment concerned by additional safety assessments). Then, it addresses the different risks: earthquake (sizing of critical structures and equipment, margin assessment), flooding (possible origins, alarm measures), other extreme natural events (extreme meteorological conditions, extreme earthquake with induced flooding, forest fire), and loss of electric supplies and of cooling systems. The last parts address the organization of accident management in situation typically related to additional safety management), and subcontracting conditions and practices

Plutonium working group report on environmental, safety and health vulnerabilities associated with the department's plutonium storage. Volume II, Appendix B, Part 10: Sandia National Laboratories - New Mexico site assessment team report

International Nuclear Information System (INIS)

1994-09-01

On March 15, 1994, Secretary O'Leary directed the Office of Environment, Safety and Health to conduct an environment, safety and health (ES ampersand H) vulnerability study of plutonium at DOE sites. This report presents Sandia National Laboratories'/New Mexico (SNL/NM) response to that request. Sandia National Laboratories (SNL) is a multi-program laboratory operated for United States Department of Energy(DOE) by Martin Marietta Corporation. The primary mission of Sandia is research and development of nuclear weapons systems for concept to retirement. The laboratory also has extensive programs in nuclear reactor safety, nuclear safeguards, energy research, and microelectronics. The facilities addressed in the SNL/NM Site Assessment include the Hot Cell Facility (HCF), the Annular Core Research Reactor (ACRR), and dedicated on-site nuclear material storage facilities. Also included in the assessment were sealed radiation sources that contain plutonium

Characterization of the Hanford Site and environs

Energy Technology Data Exchange (ETDEWEB)

Cushing, C.E. (ed.)

1991-03-01

The US Department of Energy (DOE) proposes to site, construct, and operate a new production reactor (NPR) intended to produce materials for the US nuclear weapons program. The DOE has determined that this proposed action constitutes an action that may significantly affect the quality of the human environment; therefore, the DOE is preparing an environmental impact statement (EIS) to assess the potential impacts of the proposed action and reasonable alternatives on the human and natural environment. The NPR-EIS is being prepared in accordance with Section 102(2)(C) of the National Environmental Policy Act of 1969 (NEPA), as implemented in regulations (40 CFR 1500--1508) promulgated by the Council on Environmental Quality (CEQ). Information on the potentially affected environment at the Hanford Site and its environs was provided to ANL by PNL in various submissions during CY-1989, and some of that information was consolidated into this report, which is considered to be supporting documentation for the NPR-EIS. 93 refs., 35 figs., 46 tabs.

Preliminary safety evaluation for the Simpevarp subarea. Based on data and site descriptions after the initial site investigation stage

International Nuclear Information System (INIS)

2005-04-01

The main objectives of this Preliminary safety evaluation (PSE) of the Simpevarp subarea are: to determine, whether the feasibility study's judgement of the suitability of the candidate area with respect to long-term safety holds up in the light of the site investigation data; to provide feedback to continued site investigations and site-specific repository design and to identify site specific scenarios and geoscientific issues for further analyses. The PSE focuses on comparing the attained knowledge of the sites with the suitability criteria as set out by SKB in the report SKB-TR--00-12. These criteria both concern properties of the site judged to be necessary for safety and engineering (requirements) and properties judged to be beneficial (preferences). The findings are then evaluated in order to provide feedback to continued investigations and design work. The PSE does not aim at comparing sites and does not assess compliance with safety and radiation protection criteria. The evaluation shows that even considering remaining uncertainties, the Simpevarp subarea meets all safety requirements and most of the safety preferences. Consequently, from a safety point of view, there is no reason not to continue the Site Investigations of the Simpevarp subarea. There are still uncertainties to resolve and the safety would eventually need to be verified through a full safety assessment. Still, this Preliminary Safety Evaluation demonstrates that it is likely that a safe repository for spent nuclear fuel of the KBS-3 type could be constructed at the site. The following feedback is provided to the site investigations and the associated site modelling: Reducing the uncertainty on the deformation zone geometry within the Simpevarp subarea would allow for a more specified layout, although the sensitivity analysis shows that the space needed is rather robust with respect to uncertainties in the zones. There is substantial uncertainty in the discrete fracture network (DFN) model

Environment, safety, and health manual, closeout report

International Nuclear Information System (INIS)

1975-12-01

A coordination draft of the Environment, Safety, and Health (ES and H) manual was submitted on 2 September 1975. Comments provided by Operational Safety personnel were being incorporated by a task team when the effort was terminated on 31 October 1975. This report documents the development history of the manual and provides a status of the manual up to the time the efforts were discontinued. Also discussed are issues which effect completion of the manual. Additionally a plan for completion of the manual is suggested

Taking ownership of safety. What are the active ingredients of safety coaching and how do they impact safety outcomes in critical offshore working environments?

Science.gov (United States)

Krauesslar, Victoria; Avery, Rachel E; Passmore, Jonathan

2015-01-01

Safety coaching interventions have become a common feature in the safety critical offshore working environments of the North Sea. Whilst the beneficial impact of coaching as an organizational tool has been evidenced, there remains a question specifically over the use of safety coaching and its impact on behavioural change and producing safe working practices. A series of 24 semi-structured interviews were conducted with three groups of experts in the offshore industry: safety coaches, offshore managers and HSE directors. Using a thematic analysis approach, several significant themes were identified across the three expert groups including connecting with and creating safety ownership in the individual, personal significance and humanisation, ingraining safety and assessing and measuring a safety coach's competence. Results suggest clear utility of safety coaching when applied by safety coaches with appropriate coach training and understanding of safety issues in an offshore environment. The current work has found that the use of safety coaching in the safety critical offshore oil and gas industry is a powerful tool in managing and promoting a culture of safety and care.

Rock siting of nuclear power plants from a reactor safety standpoint

International Nuclear Information System (INIS)

1975-11-01

The study has aimed at surveying the advantages and disadvantages of a rock sited nuclear power plant from a reactor safety standpoint. The studies performed are almost entirely concentrated on the BWR alternative. The design of a nuclear power plant in rock judged most appropriate has been studied in greater detail, and a relatively extensive safety analysis has been made. It is found that the presented technical design of the rock sited alternative is sufficiently advanced to form a basis for further projecting treatment. The chosen technical design of the reactor plant demands a cavern with a 45-50 metre span. Caverns without strengthening efforts with such spans are used in mines, but have no previously been used for industrial plants. Studies of the stability of such caverns show that a safety level is attainable corresponding to the safety required for the other parts of the nuclear power plant. The conditions are that the rock is of high quality, that necessary strengthening measures are taken and that careful studies of the rock are made before and during the blasting, and also during operation of the plant. When locating a rock sited nuclear power plant, the same criteria must be considered as for an above ground plant, with additional stronger demands for rock quality. The presented rock sited nuclear power plant has been assessed to cost 20 % more in total construction costs than a corresponding above ground plant. The motivations for rock siting also depend on whether a condensing plant for only electricity production, or a plant for combined power production and district heating, is considered. The latter would under certain circumstances make rock siting look more attractive. (author)

Responsible management for Health, Safety and Environment (HSE) in uranium mining and processing, starting from public support

International Nuclear Information System (INIS)

Saint-Pierre, S.

2014-01-01

Seeking, gaining and maintaining public support is inherent to mining and to responsible management in this sector. In particular, it holds special relevance for remote mining sites for which the buy in from the regional and local workforce and populations is a necessity all along the life span of a mining project from exploration to development, commissioning, operation, closure and restoration. This paper briefly highlights some key features to be accounted for nowadays for the successful development, shaping and implementation of mining projects with a view to improve public support. It is essential to address responsible management for health, safety and environment (HSE) in uranium mining and processing through key program elements such as policy; baseline; operational preparation for implementation; monitoring, reporting, review and continued improvements; as well as some insights on site closure and restoration. In particular, examples illustrate how these program elements are implemented in practice in uranium mining and processing. Some emphasis is put on radiation safety as responsible management for the other HSE dimensions tends to be analogous for all mines and mineral processing sites. (author)

Safety campaigns. TIS Launches New Safety Information Campaign

CERN Multimedia

2001-01-01

Need to start a new installation and worried about safety aspects? Or are you newly responsible for safety matters in a CERN building? Perhaps you're simply interested in how to make the working environment safer for yourself and your colleagues. Whatever the case, a new information campaign launched by TIS this week can help. The most visible aspects of the new campaign will be posters distributed around the Laboratory treating a different subject each month. The Web site - http://safety.cern.ch/ - which provides all safety related information. But these are not the only aspects of the new campaign. Members of the TIS/GS group, whose contact details can be found on the safety web site, are available to give information and advice on a one-to-one basis at any time. The campaign's launch has been timed to coincide with European Safety Week, organized by the European Agency for Safety and Health at Work and the subject treated in the first posters is safety inspection. This particular topic only concerns thos...

Safety assessment for Area 5 radioactive-waste-management site

International Nuclear Information System (INIS)

Hunter, P.H.; Card, D.H.; Horton, K.

1982-09-01

The Area 5 Radioactive Waste Management Safety Assessment Document contains evaluations of site characteristics, facilities, and operating practices that contribute to the safe handling, storage, and disposal of low-level radioactive wastes at the Nevada Test Site. Physical geography, cultural factors, climate and meteorology, geology, hydrology (with emphasis on radionuclide migration), ecology, natural phenomena, and natural resources are discussed and determined to be suitable for effective containment of radionuclides. A separate section considers facilities and operating practices such as monitoring, storage/disposal criteria, site maintenance, equipment, and support. The section also considers the transportation and waste handling requirements supporting the new Greater Confinement Disposal Facility (GCDF), GCDF demonstration project, and other requirements for the safe handling, storage, and disposal of low-level radioactive wastes. Finally, the document provides an analysis of releases and an assessment of the near-term operational impacts and dose commitments to operating personnel and the general public from normal operations and anticipated accidental occurrences. The conclusion of this report is that the Area 5 Radioactive Waste Management Site is suitable for low-level radioactive waste handling, storage, and disposal. Also, the new GCDF demonstration project will not affect the overall safety of the Area 5 Radioactive Waste Management Site

Safety Assessment Document for the Spent Reactor Fuel Geologic Storage Test in the Climax Granite Stock at the Nevada Test site

International Nuclear Information System (INIS)

1980-01-01

The objective of the Spent Fuel Geologic Storage Test in the Climax Granite Stock is to evaluate the response of a granitic rock mass to the underground storage of encapsulated spent reactor fuel in a geometry that simulates a module of a large-scale geologic repository. This document reports an assessment of the safety of conducting this test. Descriptions are provided of the geography, meteorology, hydrology, geology, and seismology of the Climax Site; the effects of postulated natural phenomena and other activities at the nevada Test Site on the safety of the test; and the design and operation of the test facility and associated equipment. Evaluations are made of both the radiological and nonradiological impacts of normal operations, abnormal operations, and postulated accidents. It is concluded that conduct of the spent fuel test at the Climax Site will not result in any undue risk to the public, property, environment, or site employees

Site specific information in site selection

International Nuclear Information System (INIS)

Aeikaes, T.; Hautojaervi, A.

1998-01-01

The programme for the siting of a deep repository for final disposal of spent nuclear fuel was started already in 1983 and is carried out today by Posiva Oy which continues the work started by Teollisuuden Voima Oy. The programme aims at site selection by the end of the year 2000. The programme has progressed in successive interim stages with defined goals. After an early phase for site identification, five sites were selected in 1987 for preliminary site characterisation. Three of these were selected and judged to be best suited for the more detailed characterisation in 1992. An additional new site was included into the programme based on a separate feasibility study in the beginning of 1997. Since the year 1983 several safety assessments together with technical plans of the facility have been completed. When approaching the site selection the needs for more detailed consideration of the site specific properties in the safety assessment have been increased. The Finnish regulator STUK has published a proposal for general safety requirements for the final disposal of spent nuclear fuel in Finland. This set of requirements has been projected to be used in conjunction of the decision making by the end 2000. Based on the site evaluation all sites can provide a stable environment and there is evidence that the requirements for the longevity of the canister can be fulfilled at each site. In this manner the four candidate sites do not differ too much from each other. The main difference between the sites is in the salinity of the deep groundwater. The significance of differences in the salinity for the long-term safety cannot be defined yet. The differences may contribute to the discussion of the longevity of the bentonite buffer and also to the modelling of the groundwater flow and transport. The use of the geosphere as a transport barrier is basically culminated on the questions about sparse but fast flow routes and 'how bad channeling can be'. To answer these questions

FEP report for the safety assessment SR-Site

Energy Technology Data Exchange (ETDEWEB)

2010-12-15

This report documents the analysis and processing of features, events and processes, FEPs, that has been carried out within the safety assessment SR-Site, and forms an important part of the reporting of the project. The main part of the work was conducted within the earlier safety assessment SR-Can, which was a preparatory stage for the SR-Site assessment. The overall objective of the FEP analysis and processing in both SR-Can and SR-Site included development of a database of features, events and processes, an SKB FEP database, in a format that facilitates both a systematic analysis of FEPs and documentation of that FEP analysis, as well as facilitating revisions and updates to be made in connection with new safety assessments. The primary objective in SR-Site was to establish an SR-Site FEP catalogue within the framework of the SKB FEP database. This FEP catalogue was required to contain all FEPs that needed to be handled in SR-Site and is an update of the corresponding SR-Can FEP catalogue that was established for the SR-Can assessment. The starting point for the handling of FEPs in SR-Site was the SR-Can version of the SKB FEP database and associated SR-Can reports. The SR-Can version of the SKB FEP database includes the SR-Can FEP catalogue, as well as the sources for the identification of FEPs in SR-Can, namely the SR 97 processes and variables, Project FEPs in the NEA International FEP database version 1.2 and matrix interactions in the Interaction matrices developed for a deep repository of the KBS-3 type. Since the completion of the FEP work within SR-Can, an updated electronic version, version 2.1, of the NEA FEP database has become available. Compared with version 1.2 of the NEA FEP database, version 2.1 contains FEPs from two more projects. As part of SR-Site, all new Project FEPs in version 2.1 of the NEA FEP database have been mapped according to the methodology adopted in SR-Can resulting in an SR-Site version of the SKB FEP database. The SKB FEP

FEP report for the safety assessment SR-Site

International Nuclear Information System (INIS)

2010-12-01

This report documents the analysis and processing of features, events and processes, FEPs, that has been carried out within the safety assessment SR-Site, and forms an important part of the reporting of the project. The main part of the work was conducted within the earlier safety assessment SR-Can, which was a preparatory stage for the SR-Site assessment. The overall objective of the FEP analysis and processing in both SR-Can and SR-Site included development of a database of features, events and processes, an SKB FEP database, in a format that facilitates both a systematic analysis of FEPs and documentation of that FEP analysis, as well as facilitating revisions and updates to be made in connection with new safety assessments. The primary objective in SR-Site was to establish an SR-Site FEP catalogue within the framework of the SKB FEP database. This FEP catalogue was required to contain all FEPs that needed to be handled in SR-Site and is an update of the corresponding SR-Can FEP catalogue that was established for the SR-Can assessment. The starting point for the handling of FEPs in SR-Site was the SR-Can version of the SKB FEP database and associated SR-Can reports. The SR-Can version of the SKB FEP database includes the SR-Can FEP catalogue, as well as the sources for the identification of FEPs in SR-Can, namely the SR 97 processes and variables, Project FEPs in the NEA International FEP database version 1.2 and matrix interactions in the Interaction matrices developed for a deep repository of the KBS-3 type. Since the completion of the FEP work within SR-Can, an updated electronic version, version 2.1, of the NEA FEP database has become available. Compared with version 1.2 of the NEA FEP database, version 2.1 contains FEPs from two more projects. As part of SR-Site, all new Project FEPs in version 2.1 of the NEA FEP database have been mapped according to the methodology adopted in SR-Can resulting in an SR-Site version of the SKB FEP database. The SKB FEP

Journal of Research in Forestry, Wildlife and Environment: Site Map

African Journals Online (AJOL)

Journal of Research in Forestry, Wildlife and Environment: Site Map. Journal Home > About the Journal > Journal of Research in Forestry, Wildlife and Environment: Site Map. Log in or Register to get access to full text downloads.

Figures and information on nuclear safety and radiation protection on the Tricastin AREVA site

International Nuclear Information System (INIS)

2010-01-01

This report presents and briefly comments figures concerning the environment (water consumption, greenhouse gas emissions, liquid releases in a canal, radioactive and hazardous industrial wastes), radiological impact and radiation protection (computed dose for a reference group, computed maximum dose for the reference group, radiological exposures of workers), nuclear safety (number of events, controls and audits), production (quantities of various materials) and transport (flows of radioactive products) for the whole Tricastin site for which only some general data are indicated, and more precisely the various installations and establishments it comprises: AREVA NC Pierrelatte, COMURHEX Pierrelatte, EURODIF Production, FBFC Pierrelatte, SET, SOCATRI

Nuclear safety criteria applied in site selection - the practice in France

International Nuclear Information System (INIS)

Candes, P.; Aussourd, Ph.

1975-01-01

In France, the safety of nuclear facilities is the responsibility of the Ministry for Industry and Research (Central Department for the Safety of Nuclear Facilities). The first part of the paper deals with the conception and contents of the site studies which are included in a safety report with the object of obtaining authorization to go ahead with work on the establishment of a facility. The conception is governed by the following two considerations: (a) the site is a place where the natural elements and living organisms occur and which is characterized by the permanent presence of the human factor, while the proposed nuclear facility will - like any industrial facility - present risks and have an impact on the site, particularly through the discharge of radioactive effluent and potentially in consequence of a nuclear accident; (b) the site exercises an influence - in fact, it even imposes constraints - on the nuclear facility. The site study as submitted by the operators to the authorities responsible for the safety evaluation traditionally consists of six sections, covering: (I) description and history of the site; (II) meteorological conditions; (III) hydrology of the area; (IV) geological and seismological conditions; (V) ecological factors; (VI) natural and/or previous radioactivity at the site. These six sections contain the data which serve as a basis for applying the two considerations spelled out above. However, the two corresponding directions of study and analysis do not settle the fundamental problem of the distribution of the population around the site. Methods for dealing with this problem are suggested in the second part of the paper; they take into account the efforts made so far at the international level. The authors consider that limiting criteria should not be based solely on the radioactive effluent discharges associated with normal operation but on the radioactivity releases associated with accidents. The methods proposed by them constitute

Areva, Chalon/St-Marcel site, Environment, social and societal report for 2010-2011

International Nuclear Information System (INIS)

2012-08-01

After a brief indication of Areva's activities and a map locating Areva's implantations, and the distribution of turnover and personnel in the different continents, a brief recall of safety commitments, and a presentation of the activity of the Reactors and Services Business Group (turnover, personnel, number of reactors in charge), this report briefly presents the different AREVA sites in Burgundy, and more precisely the Chalon/St-Marcel site which comprises a technical centre and a plant of production of heavy components. The activities of the technical centre concern welding technology, nuclear fusion, corrosion and chemistry, fluid and structure mechanics, and technologies related to the development of new energies and to the environment. Fields of intervention and clients are evoked. The activity of the plant of production of heavy components (vapor generators, pressurizers, vessels, etc.) and some characteristics of these components are presented. The environmental aspect is then addressed: evolution of resource consumption (gas, water, electricity, paper), and of releases (greenhouse gases, used waters, waste management). The social aspect comprises social relationships, health (involved actors, prevention, safety, evolution of labour accidents), ability and job management (training, career management, education). The societal commitments have been acknowledged by several labels related to social inclusion and local activities, support of sporting and cultural activities

78 FR 48468 - Delphi Corporation, Electronics and Safety Division, Including On-Site Leased Workers From...

Science.gov (United States)

2013-08-08

..., Electronics and Safety Division, Including On-Site Leased Workers From Securitas, Bartech, Flint Janitorial... Adjustment Assistance on May 20, 2013, applicable to workers of Delphi Corporation, Electronics and Safety... on- site at the Flint, Michigan location of Delphi Corporation, Electronics and Safety Division. The...

Assessment of radiation impact on the environment components while preparing for construction site of centralized storage facility for spent nuclear fuel (CSSNF)

International Nuclear Information System (INIS)

Pavlovs'kij, L.Yi.; Gorodets'kij, D.V.; Syizov, A.O.; Kholodyuk, A.O.

2016-01-01

Predictive assessment of radiation impacts on the air environment, soil cover, staff, which is located in a residential area, staff of an adjacent to the CSSNF enterprises as a result of work to prepare the site for construction of CSSNF at the Chornobyl Exclusion Zone is presented. It is shown that radiation effects on components of the environment will not result in exceeding the reference levels of radiation safety

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

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

Tiger Team Assessment of the Savannah River Site: Appendices

International Nuclear Information System (INIS)

1990-06-01

This draft document contains findings identified during the Tiger Team Compliance Assessment of the US Department of Energy Savannah River Site (SRS), located in three countries (Aiken, Barnwell and Allendale), South Carolina. The Assessment was directed by the Department's Office of the Assistant Secretary for Environment, Safety, and Health (ES ampersand H) and was conducted from January 29 to March 23, 1990. The Savannah River Site Tiger Team Compliance Assessment was broad in scope covering the Environment, Safety and Health, and Management areas and was designed to determine the site's compliance with applicable Federal (including DOE), state, and local regulations and requirements. The scope of the Environmental assessment was sitewide while the Safety and Health assessments included site operating facilities (except reactors), and the sitewide elements of Aviation Safety, Emergency Preparedness, Medical Services, and Packaging and Transportation. This report contains the appendices to the assessment

Safety and Environment- Masterplan 2020 of DLR's Rocket Test Center Lampoldhausen

Science.gov (United States)

Haberzettl, Andreas; Dommers, Michael

2013-09-01

safety of the test center.The site of Lampoldshausen with its test and supply facilities is subject to the restrictions of the German law BundesImissionsSchutzGesetz (derived from the European SEVESO-II directive) and its relevant ordinances, especially the Hazardous Incident Ordinance. Because of the complex framework effort which guarantees safety and security, Lampoldshausen has invested in people and processes in order to respect the restrictions of all relevant laws and ordinances as well as to guarantee the protection of people and the environment.Therefor a very special Master plan has been developed, with the goal to rearrange the complete testing area in order to be able to divide the area in certain sectors (testing range, technology and bureau) so that future testing enterprises will not affect almost free testing activities inside the site as it is in the present status.The paper provides comprehensive information related to the planned innovations including detailed background facts related to the foreseen safety and security standard applications.

New Methodology for a Comprehensive Modular Safety Control System in a Cyclotron Site

International Nuclear Information System (INIS)

Kaufman, Y.; Kravitz, M.; Arad, M.; Osovizky, A.; Paran, J.; Sarussi, B.; Ellenbogen, M.; Tal, N.

2004-01-01

This Paper describes a new methodology for a comprehensive modular Safety Control System (SCS), for a cyclotron site. The developed SCS is a modular approach for controlling the production procedures, safety conditions and documentation aspects in the Cyclotron site. Usually, the safety conditions in cyclotron sites are maintained by a variety of sensors. The cyclotron is supplied from the manufacturer with a self-integrated control system for its operation, yet the comprehensive SCS has to be defined and setup by the customer. Therefore, customers face a lot of integration problems in trying to combine all the signals from the different safety systems such as radiation monitoring, environmental and access control, in order to maintain proper safety working conditions. The presented SCS design provides main user interface and the complete safety solution required by including preset control logic definitions and open logic for specific user applications. The knowledge for the preset control logic definitions was gathered in previous projects. Failure Mode and Effects Analysis (FMEA) method has been implemented on the SCS to analyze the potential failure modes and their impact on the product reliability

Safety leadership at construction sites: the importance of rule-oriented and participative leadership.

Science.gov (United States)

Grill, Martin; Pousette, Anders; Nielsen, Kent; Grytnes, Regine; Törner, Marianne

2017-07-01

Objectives The construction industry accounted for >20% of all fatal occupational accidents in Europe in 2014. Leadership is an essential antecedent to occupational safety. The aim of the present study was to assess the influence of transformational, active transactional, rule-oriented, participative, and laissez-faire leadership on safety climate, safety behavior, and accidents in the Swedish and Danish construction industry. Sweden and Denmark are similar countries but have a large difference in occupational accidents rates. Methods A questionnaire study was conducted among a random sample of construction workers in both countries: 811 construction workers from 85 sites responded, resulting in site and individual response rates of 73% and 64%, respectively. Results The results indicated that transformational, active transactional, rule-oriented and participative leadership predict positive safety outcomes, and laissez-faire leadership predict negative safety outcomes. For example, rule-oriented leadership predicts a superior safety climate (β=0.40, Pleadership on workers' safety behavior was moderated by the level of participative leadership (β=0.10, Pleadership behaviors on safety outcomes were largely similar in Sweden and Denmark. Rule-oriented and participative leadership were more common in the Swedish than Danish construction industry, which may partly explain the difference in occupational accident rates. Conclusions Applying less laissez-faire leadership and more transformational, active transactional, participative and rule-oriented leadership appears to be an effective way for construction site managers to improve occupational safety in the industry.

Data report for the safety assessment SR-Site

International Nuclear Information System (INIS)

2010-12-01

This report compiles, documents, and qualifies input data identified as essential for the long-term safety assessment of a KBS-3 repository, and forms an important part of the reporting of the safety assessment project SR-Site. The input data concern the repository system, broadly defined as the deposited spent nuclear fuel, the engineered barriers surrounding it, the host rock, and the biosphere in the proximity of the repository. The input data also concern external influences acting on the system, in terms of climate related data. Data are provided for a selection of relevant conditions and are qualified through traceable standardised procedures

Data report for the safety assessment SR-Site

Energy Technology Data Exchange (ETDEWEB)

2010-12-15

This report compiles, documents, and qualifies input data identified as essential for the long-term safety assessment of a KBS-3 repository, and forms an important part of the reporting of the safety assessment project SR-Site. The input data concern the repository system, broadly defined as the deposited spent nuclear fuel, the engineered barriers surrounding it, the host rock, and the biosphere in the proximity of the repository. The input data also concern external influences acting on the system, in terms of climate related data. Data are provided for a selection of relevant conditions and are qualified through traceable standardised procedures

Focusing on patient safety in the Neonatal Intensive Care Unit environment

Directory of Open Access Journals (Sweden)

Ilias Chatziioannidis

2017-02-01

Full Text Available Patient safety in the Neonatal Intensive Care Unit (NICU environment is an under-researched area, but recently seems to get high priority on the healthcare quality agenda worldwide. NICU, as a highly sensitive and technological driven environment, signals the importance for awareness in causation of mistakes and accidents. Adverse events and near misses that comprise the majority of human errors, cause morbidity often with devastating results, even death. Likewise in other organizations, errors causes are multiple and complex. Other high reliability organizations, such as air force and nuclear industry, offer examples of how standardized/homogenized work and removal of systems weaknesses can minimize errors. It is widely accepted that medical errors can be explained based on personal and/or system approach. The impact/effect of medical errors can be reduced when thorough/causative identification approach is followed by detailed analysis of consequences and prevention measures. NICU’s medical and nursing staff should be familiar with patient safety language, implement best practices, and support safety culture, maximizing efforts for reducing errors. Furthermore, top management commitment and support in developing patient safety culture is essential in order to assure the achievement of the desirable organizational safety outcomes. The aim of the paper is to review patient safety issues in the NICU environment, focusing on development and implementation of strategies, enhancing high quality standards for health care.

Use of a Web Site to Enhance Criticality Safety Training

International Nuclear Information System (INIS)

Huang, S T; Morman, J

2003-01-01

Currently, a website dedicated to enhancing communication and dissemination of criticality safety information is sponsored by the U.S. Department of Energy (DOE) Nuclear Criticality Safety Program (NCSP). This website was developed as part of the DOE response to the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 97-2, which reflected the need to make criticality safety information available to a wide audience. The website is the focal point for DOE nuclear criticality safety (NCS) activities, resources and references, including hyperlinks to other sites actively involved in the collection and dissemination of criticality safety information. The website is maintained by the Lawrence Livermore National Laboratory (LLNL) under auspices of the NCSP management. One area of the website contains a series of Nuclear Criticality Safety Engineer Training (NCSET) modules. During the past few years, many users worldwide have accessed the NCSET section of the NCSP website and have downloaded the training modules as an aid for their training programs. This trend was remarkable in that it points out a continuing need of the criticality safety community across the globe. It has long been recognized that training of criticality safety professionals is a continuing process involving both knowledge-based training and experience-based operations floor training. As more of the experienced criticality safety professionals reach retirement age, the opportunities for mentoring programs are reduced. It is essential that some method be provided to assist the training of young criticality safety professionals to replenish this limited human expert resource to support on-going and future nuclear operations. The main objective of this paper is to present the features of the NCSP website, including its mission, contents, and most importantly its use for the dissemination of training modules to the criticality safety community. We will discuss lessons learned and several ideas

Proceeding of Radiation Safety and Environment; Prosiding Presentasi Ilmiah Keselamatan Radiasi dan Lingkungan

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-07-01

Scientific Presentation of Radiation Safety and Environment was held on 20-21 august 1996 at Center of Research Atomic Energy Pasar Jum'at, Jakarta, Indonesia. Have presented 50 papers about Radiation Safety, dosimetry and standardization, environment protection and radiation effect.

Resolving the Ferrocyanide Safety Issue at the Hanford Site

International Nuclear Information System (INIS)

Meacham, J.E.; Cash, R.J.; Babad, H.

1994-02-01

Considerable data have been obtained on the chemical and physical properties of ferrocyanide waste stored in Hanford Site single-shell tanks (SSTs). Theoretical analyses and ferrocyanide waste simulant studies have led to the development of fuel, moisture, and temperature criteria that define continued safe storage. Developing the criteria provides the technical basis for closing the Ferrocyanide Unreviewed Safety Question (USQ). Using the safety criteria, the ferrocyanide tanks have been ranked into one of three safety categories: Safe, Conditionally Safe, and Unsafe. All the ferrocyanide tanks are currently ranked in either the Safe or Conditionally Safe categories. Analyses of core samples taken from three ferrocyanide tanks have shown cyanide concentrations about a factor of ten lower than predicted by the original flowsheets. Hydrolytic and radiolytic destruction (aging) of the ferrocyanide matrix has occurred during the 35 plus years the waste has been stored at the Hanford Site. Because of waste aging, it is possible that all of the ferrocyanide tanks may now contain less than the 8 wt % sodium nickel ferrocyanide specified in the fuel criterion for the Safe category. Ferrocyanide tanks that remain in the Conditionally Safe category may require monitoring and surveillance to verify that the waste remains in an unreactive state. Further characterization of the tanks by core sampling and analyses should lead to resolution of the Ferrocyanide Safety Issue by September 1997

Exploration and safety evaluations of salt formations and site selection procedures; Erkundung und Sicherheitsbewertung von Salzformationen und Standortauswahlverfahren

Energy Technology Data Exchange (ETDEWEB)

Krapf, Eva Barbara

2016-12-12

In 2011 the final decision for the withdrawal from the nuclear energy program was decided in the Federal Republic of Germany. The majority of the produced radioactive waste originate in the operation as well as in the decommissioning and dismantling of nuclear facilities. The long-term containment of especially heat-developing and high-level waste in an underground disposal facility is pursued. The Site Selection Act (StandAG), passed in 2013, defined further procedural steps as well as responsibilities and the way of public participation during the site selection. In this context the newly founded Commission Storage of Highly Radioactive Waste was assigned with the task of giving relevant recommendations based on their investigation of specific aspects and fundamental questions. The objective of this procedure is the selection of the site that can provide the best possible safety for humans and the environment during the defined period of one million years. The Commissions' final report was published in July 2016. In this thesis a possible approach for exploring sites in connection with safety investigations is recommended. The site selection procedure described in the StandAG represents the basis for the considerations. Geoscientific exclusion criteria, minimum requirements as well as weighing criteria can be developed regarding the relevant geoscientific and climatic changes during the defined period of one million years. In contrast to the recommendations made by the Commission Storage of Highly Radioactive Waste no previously existing report has been revised and adapted. Rather, all issues relevant for the long-term containment of radioactive waste in a disposal facility had been newly developed. The considerations are related to salt domes as host rock. Furthermore, according to the StandAG preliminary safety investigations are required in every step of the site selection. The recommendations made in this thesis concerning content and feasibility of

Hanford Site Wide Transportation Safety Document [SEC 1 Thru 3

Energy Technology Data Exchange (ETDEWEB)

MCCALL, D L

2002-06-01

This safety evaluation report (SER) documents the basis for the US Department of Energy (DOE), Richland Operations Office (RL) to approve the Hanford Sitewide Transportation Safety Document (TSD) for onsite Transportation and Packaging (T&P) at Hanford. Hanford contractors, on behalf of DOE-RL, prepared and submitted the Hanford Sitewide Transportation Safety Document, DOE/RL-2001-0036, Revision 0, (DOE/RL 2001), dated October 4, 2001, which is referred to throughout this report as the TSD. In the context of the TSD, Hanford onsite shipments are the activities of moving hazardous materials, substances, and wastes between DOE facilities and over roadways where public access is controlled or restricted and includes intra-area and inter-area movements. The TSD sets forth requirements and standards for onsite shipment of radioactive and hazardous materials and wastes within the confines of the Hanford Site on roadways where public access is restricted by signs, barricades, fences, or other means including road closures and moving convoys controlled by Hanford Site security forces.

A study on development strategy of atomic safety organization for atomic environment

Energy Technology Data Exchange (ETDEWEB)

Lee, Sung Bok; Jeong, Ji Hun; Kim Tae Hee; Lee, Seung Hyuk; Woo, Eun Jung [Konkuk Univ., Seoul (Korea, Republic of)

2005-02-15

The objective of this research is to suggest some strategies which can make the safety of atomic power possible and reinforce the nuclear regulatory system. It will contribute to the expansion and settlement of nuclear safety culture by making the public understand well about the safety of nuclear energy, and searching public relations and incentive strategies. In addition, since the nuclear environment is changing rapidly, the necessity of cooperation between the public and the private has veen mostly required. So we need to develop the effective administrative system based on their cooperation. Therefore, it will examine the function of organization established, operation system, and also social network closely connected with the nuclear safety. Moreover, by analyzing the change of regulatory environment and present safety confirmation of nuclear energy, it will devise the new safety confirmation system of nuclear energy.

Resolution of the Hanford site ferrocyanide safety issue

International Nuclear Information System (INIS)

Cash, R.J.; Lilga, M.A.; Babad, H.

1997-01-01

The Ferrocyanide Safety Issue at the Hanford Site was officially resolved in December 1996. This paper summarizes the key activities that led to final resolution of this safety hazard, a process that began in 1990 after it and other safety concerns were identified for the underground high-level waste storage tanks at the Hanford Site. At the time little was known about ferrocyanide-nitrate/nitrite reactions and their potential to cause offsite releases of radioactivity. The ferrocyanide hazard was a perceived problem, but it took six years of intense studies and analyses of tank samples to prove that the problem no longer exists. The issue revolved around the fact that ferrocyanide and nitrate mixtures can be made to explode violently if concentrated, dry, and heated to temperatures of at least 250 degrees C. The studies conducted over the last six years have shown that the combined effects of temperature, radiation, and pH during 40 or more years of storage have destroyed almost all of the ferrocyanide originally added to tanks. This was shown in laboratory experiments using simulant wastes and confirmed by actual samples taken from the ferrocyanide tanks. The tank waste sludges are now too dilute to support a sustained exothermic reaction, even if dried out and heated to high temperatures. 2 tabs., 18 refs

Independent regulatory control and monitoring of the environment at the uranium legacy sites under reclamation

International Nuclear Information System (INIS)

Shandala, N.K.; Titov, A.V.; Kiselev, S.M.; Isaev, D.V.; Aladova, R.A.

2012-01-01

Full text: Radiation safety at areas affected by the natural uranium mining and milling facilities is very important for the environment protection and human health. For this purpose the close operator-regulator contact is required during remedial operations. One of the key mechanisms of the operating regulatory supervision of radiation safety at uranium legacy sites is organization of independent radiation control and monitoring in the course of reclamation and after its completion. The main stages of this strategy include: detailed radiation survey at the area and in the vicinity of the former uranium mining sites; threat assessment in order to identify the regulatory priorities; environmental radiation control and monitoring. Tailings and shallow disposal sites of the uranium mining wastes are the most critical areas in terms of potential hazard for the environment. Tailings are the source of contamination of the near-land air due to the radionuclide dust resuspension from the tailing surface; surface and ground water due to washing out from by precipitation and surface streams of toxic and radioactive elements. Frequently, contamination of surface and ground waters results in some problems, especially when using the leaching fluids for the solution mining and draining hydraulic fluids. Radiation risk for the residents of areas near not operating uranium mining and milling facilities depends on the following factors: radon exhalation from the surface of dumps and tailing; radioactive dust transfer; using radioactive material in building; contamination of surface water streams and aquifers used for drinking water supply; contamination of open ponds used for fish breeding and catching; contamination of foodstuffs grown in the nuclear legacy areas. Radiation monitoring is necessary for the up-to-date response to changing radiation situation during reclamation and arrangement of adequate countermeasures. We mean here comprehensive dynamic surveillance including long

Site specific health and safety plan, 233-S decontamination and decommissioning

Energy Technology Data Exchange (ETDEWEB)

J. E. Fasso

1997-12-31

The deactivated 233-S Plutonium Concentration Facility, located in the 200 Area at the Hanford Site, is the subject of this Health and Safety Plan.The 233-S Facility operated from January 1952 until July 1967 at which time the building entered the U.S. Department of Energy`s Surplus Facility Management Program as a retired facility. The facility has since undergone severe degradation due to exposure to extreme weather conditions. Additionally, the weather caused existing cracks in concrete structures of the building to lengthen, thereby increasing the potential for failed confinement of the radioactive material in the building. Differential settlement has also occurred causing portions of the facility to separate from the main building structure, increasing the potential for release of radioactive material to the environment. An expedited response is proposed to remove this threat and ensure protection of human health and the environment. On this premise it is intended that the 233-S Facility removal action be performed as a Comprehensive Environmental Response, Compensation, and Liability Act of 1980 Time-Critical Project being conducted under the Pilot Hanford Environmental Restoration (ER) Initiative

Safety-related site characteristics - a relative comparison of the Forsmark reference areas

International Nuclear Information System (INIS)

Winberg, Anders

2010-12-01

SKB has over the years from 2002 to 2008 conducted site investigations in Forsmark and Laxemar, with associated site modeling, design and safety analysis. In mid-2009 Forsmark was selected on the basis of analysis made as site for a future repository for spent nuclear fuel. Based on defined safety-related geoscientific location factors data from Forsmark are compared in relative terms with data from a number of locations in Sweden, previously studied by SKB. The factors compared include: the rock's composition and structures, future climate evolution, rock mechanical conditions, earthquakes, groundwater flow, groundwater composition, delay of solutes, and the ability to characterize and describe the location. Past comparisons of these properties for the selected sites show that none of these sites collectively show any significant benefit over Forsmark site for a repository. This does not preclude that there may be places on the basis of an overall assessment of geoscientific location factors could be equivalent to Forsmark

Flamanville 3 EPR, Safety Assessment and On-site Inspections

International Nuclear Information System (INIS)

Piedagnel, Corinne; Tarallo, Francois; Monnot, Bernard

2011-01-01

As a Technical Support Organisation of the French Safety Authority (ASN), the IRSN carries out the safety assessment of EPR project design and participates in the ASN inspections performed at the construction site and in factories. The design assessment consists in defining the safety functions which should be ensured by civil structures, evaluating the EPR Technical Code for Civil works (ETC-C) in which EdF has defined design criteria and construction rules, and carrying out a detailed assessment of a selection of safety-related structures. Those detailed assessments do not consist of a technical control but of an analysis whose objectives are to ensure that design and demonstrations are robust, in accordance with safety and regulatory rules. Most assessments led IRSN to ask EdF to provide additional justification sometimes involving significant modifications. In the light of those complementary justifications and modifications, IRSN concluded that assessments carried out on design studies were globally satisfactory. The participation of IRSN to the on-site inspections led by ASN is a part of the global control of the compliance of the reactor with its safety objectives. For that purpose IRSN has defined a methodology and an inspection program intended to ASN: based on safety functions associated with civil works (confinement and resistance to aggressions), the corresponding behaviour requirements are identified and linked to a list of main civil works elements. During the inspections, deviations to the project's technical specifications or to the rules of the art were pointed out by IRSN. Those deviations cover various items, such as concrete fabrication, concrete pouring methodology, lack of reinforcement in some structures, unadapted welding procedures of the containment leak-tight steel liner and unsatisfactory treatment of concreting joints. The analysis of those problems has revealed flaws in the organisation of the contractors teams together with an

Administrative goals and safety standards for hazard control on forested recreation sites

Science.gov (United States)

Lee A. Paine

1973-01-01

For efficient control of tree hazard on recreation sites, a specific administrative goal must be selected. A safety standard designed to achieve the selected goal and a uniform hazard-rating procedure will then promote a consistent level of safety at an acceptable cost. Safety standards can be established with the aid of data for past years, and dollar evaluations are...

Nursing practice environment, job outcomes and safety climate: a structural equation modelling analysis.

Science.gov (United States)

Dos Santos Alves, Daniela Fernanda; da Silva, Dirceu; de Brito Guirardello, Edinêis

2017-01-01

To assess correlations between the characteristics of the nursing practice environment, job outcomes and safety climate. The nursing practice environment is critical to the well-being of professionals and to patient safety, as highlighted by national and international studies; however, there is a lack of evidence regarding this theme in paediatric units. A cross-sectional study, in two paediatric hospitals in Brazil, was conducted from December 2013 to February 2014. For data collection, we used the Nursing Work Index - Revised, Safety Attitudes Questionnaire - Short Form 2006 and the Maslach Burnout Inventory, and for analysis Spearman's correlation coefficient and structural equation modelling were used. Two hundred and sixty-seven professional nurses participated in the study. Autonomy, control over the work environment and the relationship between nursing and medical staff are factors associated with job outcomes and safety climate and can be considered their predictors. Professional nurses with greater autonomy, good working relationships and control over their work environment have lower levels of emotional exhaustion, higher job satisfaction, less intention of leaving the job and the safety climate is positive. Initiatives to improve the professional practice environment can improve the safety of paediatric patients and the well-being of professional nurses. © 2016 John Wiley & Sons Ltd.

Towards the Verification of Safety-critical Autonomous Systems in Dynamic Environments

Directory of Open Access Journals (Sweden)

Adina Aniculaesei

2016-12-01

Full Text Available There is an increasing necessity to deploy autonomous systems in highly heterogeneous, dynamic environments, e.g. service robots in hospitals or autonomous cars on highways. Due to the uncertainty in these environments, the verification results obtained with respect to the system and environment models at design-time might not be transferable to the system behavior at run time. For autonomous systems operating in dynamic environments, safety of motion and collision avoidance are critical requirements. With regard to these requirements, Macek et al. [6] define the passive safety property, which requires that no collision can occur while the autonomous system is moving. To verify this property, we adopt a two phase process which combines static verification methods, used at design time, with dynamic ones, used at run time. In the design phase, we exploit UPPAAL to formalize the autonomous system and its environment as timed automata and the safety property as TCTL formula and to verify the correctness of these models with respect to this property. For the runtime phase, we build a monitor to check whether the assumptions made at design time are also correct at run time. If the current system observations of the environment do not correspond to the initial system assumptions, the monitor sends feedback to the system and the system enters a passive safe state.

Waste Isolation Pilot Plant Site Environmental Report Calendar Year 2002

Energy Technology Data Exchange (ETDEWEB)

Washington Regulatory and Environmental Services

2003-09-17

The United States (U.S.) Department of Energy (DOE) Carlsbad Field Office (CBFO) and Washington TRU Solutions LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environment, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2002 Site Environmental Report summarizes environmental data from calendar year 2002 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, and Guidance for the Preparation of DOE Annual Site Environmental Reports (ASERs) for Calendar Year 2002 (DOE Memorandum EH-41: Natoli:6-1336, April 4, 2003). These Orders and the guidance document require that DOE facilities submit an annual site environmental report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health; and the New Mexico Environment Department (NMED).

Waste Isolation Pilot Plant Site Environmental Report Calendar Year 2002

International Nuclear Information System (INIS)

Washington Regulatory and Environmental Services

2003-01-01

The United States (U.S.) Department of Energy (DOE) Carlsbad Field Office (CBFO) and Washington TRU Solutions LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environment, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2002 Site Environmental Report summarizes environmental data from calendar year 2002 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, and Guidance for the Preparation of DOE Annual Site Environmental Reports (ASERs) for Calendar Year 2002 (DOE Memorandum EH-41: Natoli:6-1336, April 4, 2003). These Orders and the guidance document require that DOE facilities submit an annual site environmental report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health; and the New Mexico Environment Department (NMED)

Management of construction safety at RR site

International Nuclear Information System (INIS)

Pathak, B.C.; Khatsuriya, J.R.

2016-01-01

Construction industries are one of the most hazardous industries and hence, promotion of safety remains one of the greatest challenges facing construction industry today. According to ILO estimates: Each year at least 60,000 fatal accidents occur on construction sites around the world or one fatal accident every ten minutes. One in six fatal accidents at work occurs on a construction site. In industrialized countries, as many as 25-40 per cent of work related deaths occur on construction sites, even though the sector employs only 6-10 per cent of the workforce. The number of fatalities occurring from construction work in India is also quite disturbing. Though, the fall of person from height and through openings were the major causes for fatal /serious accidents, the risk of fatal accident involving material handling equipment, either during handling or its maintenance is also significantly high due to use of large number of material handling equipments during construction work. (author)

Radiation legacy of nuclear tests at the Semipalatinsk test site in the light of requirements ensuring radiation safety performance

International Nuclear Information System (INIS)

Logachev, V.A.; Logacheva, L.A.

2005-01-01

Peculiarities of nuclear tests radiation legacy at the Semipalatinsk test site (STS) are shown in the light of performance of requirements ensuring radiation safety, decrease radiation contamination levels in environment and minimize exposure of radiation for population residing contaminated areas by radioactive fallout. The paper provides data on characterization of peculiarities of the STS operation legacy based on review of archival data of the former 3-d General Administration under USSR Ministry of Health. (author)

Exploring the Influence of Nurse Work Environment and Patient Safety Culture on Attitudes Toward Incident Reporting.

Science.gov (United States)

Yoo, Moon Sook; Kim, Kyoung Ja

2017-09-01

The aim of this study was to explore the influence of nurse work environments and patient safety culture on attitudes toward incident reporting. Patient safety culture had been known as a factor of incident reporting by nurses. Positive work environment could be an important influencing factor for the safety behavior of nurses. A cross-sectional survey design was used. The structured questionnaire was administered to 191 nurses working at a tertiary university hospital in South Korea. Nurses' perception of work environment and patient safety culture were positively correlated with attitudes toward incident reporting. A regression model with clinical career, work area and nurse work environment, and patient safety culture against attitudes toward incident reporting was statistically significant. The model explained approximately 50.7% of attitudes toward incident reporting. Improving nurses' attitudes toward incident reporting can be achieved with a broad approach that includes improvements in work environment and patient safety culture.

Safety assessment of HLW geological disposal system

International Nuclear Information System (INIS)

Naito, Morimasa

2006-01-01

In accordance with the Japanese nuclear program, the liquid waste with a high level of radioactivity arising from reprocessing is solidified in a stable glass matrix (vitrification) in stainless steel fabrication containers. The vitrified waste is referred to as high-level radioactive waste (HLW), and is characterized by very high initial radioactivity which, even though it decreases with time, presents a potential long-term risk. It is therefore necessary to thoroughly manage HLW from human and his environment. After vitrification, HLW is stored for a period of 30 to 50 years to allow cooling, and finally disposed of in a stable geological environment at depths greater than 300 m below surface. The deep underground environment, in general, is considered to be stable over geological timescales compared with surface environment. By selecting an appropriate disposal site, therefore, it is considered to be feasible to isolate the waste in the repository from man and his environment until such time as radioactivity levels have decayed to insignificance. The concept of geological disposal in Japan is similar to that in other countries, being based on a multibarrier system which combines the natural geological environment with engineered barriers. It should be noted that geological disposal concept is based on a passive safety system that does not require any institutional control for assuring long term environmental safety. To demonstrate feasibility of safe HLW repository concept in Japan, following technical steps are essential. Selection of a geological environment which is sufficiently stable for disposal (site selection). Design and installation of the engineered barrier system in a stable geological environment (engineering measures). Confirmation of the safety of the constructed geological disposal system (safety assessment). For site selection, particular consideration is given to the long-term stability of the geological environment taking into account the fact

Safety Basis Report

International Nuclear Information System (INIS)

R.J. Garrett

2002-01-01

As part of the internal Integrated Safety Management Assessment verification process, it was determined that there was a lack of documentation that summarizes the safety basis of the current Yucca Mountain Project (YMP) site characterization activities. It was noted that a safety basis would make it possible to establish a technically justifiable graded approach to the implementation of the requirements identified in the Standards/Requirements Identification Document. The Standards/Requirements Identification Documents commit a facility to compliance with specific requirements and, together with the hazard baseline documentation, provide a technical basis for ensuring that the public and workers are protected. This Safety Basis Report has been developed to establish and document the safety basis of the current site characterization activities, establish and document the hazard baseline, and provide the technical basis for identifying structures, systems, and components (SSCs) that perform functions necessary to protect the public, the worker, and the environment from hazards unique to the YMP site characterization activities. This technical basis for identifying SSCs serves as a grading process for the implementation of programs such as Conduct of Operations (DOE Order 5480.19) and the Suspect/Counterfeit Items Program. In addition, this report provides a consolidated summary of the hazards analyses processes developed to support the design, construction, and operation of the YMP site characterization facilities and, therefore, provides a tool for evaluating the safety impacts of changes to the design and operation of the YMP site characterization activities

Safety Basis Report

Energy Technology Data Exchange (ETDEWEB)

R.J. Garrett

2002-01-14

As part of the internal Integrated Safety Management Assessment verification process, it was determined that there was a lack of documentation that summarizes the safety basis of the current Yucca Mountain Project (YMP) site characterization activities. It was noted that a safety basis would make it possible to establish a technically justifiable graded approach to the implementation of the requirements identified in the Standards/Requirements Identification Document. The Standards/Requirements Identification Documents commit a facility to compliance with specific requirements and, together with the hazard baseline documentation, provide a technical basis for ensuring that the public and workers are protected. This Safety Basis Report has been developed to establish and document the safety basis of the current site characterization activities, establish and document the hazard baseline, and provide the technical basis for identifying structures, systems, and components (SSCs) that perform functions necessary to protect the public, the worker, and the environment from hazards unique to the YMP site characterization activities. This technical basis for identifying SSCs serves as a grading process for the implementation of programs such as Conduct of Operations (DOE Order 5480.19) and the Suspect/Counterfeit Items Program. In addition, this report provides a consolidated summary of the hazards analyses processes developed to support the design, construction, and operation of the YMP site characterization facilities and, therefore, provides a tool for evaluating the safety impacts of changes to the design and operation of the YMP site characterization activities.

Evaluating the Clinical Learning Environment: Resident and Fellow Perceptions of Patient Safety Culture.

Science.gov (United States)

Bump, Gregory M; Calabria, Jaclyn; Gosman, Gabriella; Eckart, Catherine; Metro, David G; Jasti, Harish; McCausland, Julie B; Itri, Jason N; Patel, Rita M; Buchert, Andrew

2015-03-01

The Accreditation Council for Graduate Medical Education has begun to evaluate teaching institutions' learning environments with Clinical Learning Environment Review visits, including trainee involvement in institutions' patient safety and quality improvement efforts. We sought to address the dearth of metrics that assess trainee patient safety perceptions of the clinical environment. Using the Hospital Survey on Patient Safety Culture (HSOPSC), we measured resident and fellow perceptions of patient safety culture in 50 graduate medical education programs at 10 hospitals within an integrated health system. As institution-specific physician scores were not available, resident and fellow scores on the HSOPSC were compared with national data from 29 162 practicing providers at 543 hospitals. Of the 1337 residents and fellows surveyed, 955 (71.4%) responded. Compared with national practicing providers, trainees had lower perceptions of patient safety culture in 6 of 12 domains, including teamwork within units, organizational learning, management support for patient safety, overall perceptions of patient safety, feedback and communication about error, and communication openness. Higher perceptions were observed for manager/supervisor actions promoting patient safety and for staffing. Perceptions equaled national norms in 4 domains. Perceptions of patient safety culture did not improve with advancing postgraduate year. Trainees in a large integrated health system have variable perceptions of patient safety culture, as compared with national norms for some practicing providers. Administration of the HSOPSC was feasible and acceptable to trainees, and may be used to track perceptions over time.

Investigating the potential benefits of on-site food safety training for Folklorama, a temporary food service event.

Science.gov (United States)

Mancini, Roberto; Murray, Leigh; Chapman, Benjamin J; Powell, Douglas A

2012-10-01

Folklorama in Winnipeg, Manitoba, Canada, is a 14-day temporary food service event that explores the many different cultural realms of food, food preparation, and entertainment. In 2010, the Russian pavilion at Folklorama was implicated in a foodborne outbreak of Escherichia coli O157 that caused 37 illnesses and 18 hospitalizations. The ethnic nature and diversity of foods prepared within each pavilion presents a unique problem for food inspectors, as each culture prepares food in their own very unique way. The Manitoba Department of Health and Folklorama Board of Directors realized a need to implement a food safety information delivery program that would be more effective than a 2-h food safety course delivered via PowerPoint slides. The food operators and event coordinators of five randomly chosen pavilions selling potentially hazardous food were trained on-site, in their work environment, focusing on critical control points specific to their menu. A control group (five pavilions) did not receive on-site food safety training and were assessed concurrently. Public health inspections for all 10 pavilions were performed by Certified Public Health Inspectors employed with Manitoba Health. Critical infractions were assessed by means of standardized food protection inspection reports. The results suggest no statistically significant difference in food inspection scores between the trained and control groups. However, it was found that inspection report results increased for both the control and trained groups from the first inspection to the second, implying that public health inspections are necessary in correcting unsafe food safety practices. The results further show that in this case, the 2-h food safety course delivered via slides was sufficient to pass public health inspections. Further evaluations of alternative food safety training approaches are warranted.

Safety Considerations in the Selection of Nuclear Power Plant Candidate Sites in Johor State, Malaysia

International Nuclear Information System (INIS)

Ramli, A.T.; Basri, N.A.; Abu Hanifah, N.Z.H.

2014-01-01

Nuclear power is considered as one of the best options for future energy development in Malaysia. Since Malaysia has no experience in nuclear energy generation / production, commissioning the first nuclear power plant needs tremendous effort in various aspects. The most obvious challenges are to ensure the nation’s safety and to handle security issues that may arise from a nuclear power plant site. This paper aims to propose a site for nuclear power plant in Johor State, Malaysia as well as listing the possible safety challenges in the process. The site selection uses the Malaysian Atomic Energy Licensing Board (AELB) guideline document as the main reference, supported by documents from International Atomic Energy Agency (IAEA) and from various countries. Only five site characteristics are chosen as study parameters – geological features and seismic data, air dispersion analysis using meteorological data, population distribution, safety zones and emergency supports. This paper concluded that site number 2 (CS2) at Tanjung Tenggaroh, Mersing is the most suitable area for nuclear power plant in Johor state. It has the least possible risks, safety and security issues. (author)

Safety Considerations in the Selection of Nuclear Power Plant Candidate Sites in Johor State, Malaysia

Energy Technology Data Exchange (ETDEWEB)

Ramli, A. T.; Basri, N. A.; Abu Hanifah, N. Z.H., [Department of Physics, Faculty of Science Universiti Teknologi Malaysia Johor (Malaysia)

2014-10-15

Nuclear power is considered as one of the best options for future energy development in Malaysia. Since Malaysia has no experience in nuclear energy generation / production, commissioning the first nuclear power plant needs tremendous effort in various aspects. The most obvious challenges are to ensure the nation’s safety and to handle security issues that may arise from a nuclear power plant site. This paper aims to propose a site for nuclear power plant in Johor State, Malaysia as well as listing the possible safety challenges in the process. The site selection uses the Malaysian Atomic Energy Licensing Board (AELB) guideline document as the main reference, supported by documents from International Atomic Energy Agency (IAEA) and from various countries. Only five site characteristics are chosen as study parameters – geological features and seismic data, air dispersion analysis using meteorological data, population distribution, safety zones and emergency supports. This paper concluded that site number 2 (CS2) at Tanjung Tenggaroh, Mersing is the most suitable area for nuclear power plant in Johor state. It has the least possible risks, safety and security issues. (author)

Geoscientific long-term prognosis. Preliminary safety analysis for the site Gorleben

International Nuclear Information System (INIS)

Mrugalla, Sabine

2011-07-01

The preliminary safety analysis of the site Gorleben includes the following chapters: (1) Introduction; (2) Aim and content of the geoscientific long-term prognosis for the site Gorleben; (3) Boundary conditions at the site Gorleben: climate; geomorphology; overlying rocks and adjoining rocks; hydrogeology; salt deposit Gorleben. (4) Probable future geological developments at the site Gorleben: supraregional developments with effects on the site Gorleben; glacial period developments; developments of the geomorphology, overlying and adjoining rocks; future developments of the hydrological systems at the site Gorleben; future saliniferous specific developments of the salt deposit Gorleben. (5) Commentary on the unlikely or excludable developments of the site Gorleben.

The occupational safety on the construction sites of the farm production buildings in Finland

Directory of Open Access Journals (Sweden)

M. Hellstedt

2013-09-01

Full Text Available The size of farms has increased considerably during Finland's EU membership. The growth has meant big investments in the new production buildings. The buildings have been switched to big industrialhall- like constructions from small-scale ones which have contained own timber and own work contribution. The objective of the project financed by Farmers' Social Insurance Institution was to improve occupational safety on farm building construction and renovation sites by disseminating current safety practices and by developing ways of action which are better than the prevailing ones. The project consisted of a literature review, statistical analysis, as well as a farmer and designer interviews. In the statistical analysis the MATA occupational injuries insurance claims database on farmers’ claims during construction and renovation work for the years 2005 - 2008 was compared with the register of Federation of Accident Insurance Institutions on the construction workers' injuries. In comparing the reasons of the accidents a clear difference was found; poor scaffoldings and ladders are still the main culprits on farm accidents. Farmer interviews were used to assess occupational safety measures on the construction site, occurred injuries and their types, nearmiss situations and the underlying factors which have led to the injuries. Also construction safety deficiencies as well as the direct and indirect costs caused for instance because of the delay in completion of construction project were discussed. Designer interviews aimed to find out how occupational safety and health considerations are taken into account in farm building planning and counseling, and how this experience of the designers should be utilized in order to improve safety at the construction sites on farms. Farmers knew their obligations on occupational safety poorly. The situation was further worsened by the fact that on the site the supervisor tasks were only nominally executed. The

Safety inspections in construction sites: A systems thinking perspective.

Science.gov (United States)

Saurin, Tarcisio Abreu

2016-08-01

Although safety inspections carried out by government officers are important for the prevention of accidents, there is little in-depth knowledge on their outcomes and processes leading to these. This research deals with this gap by using systems thinking (ST) as a lens for obtaining insights into safety inspections in construction sites. Thirteen case studies of sites with prohibited works were carried out, discussing how four attributes of ST were used in the inspections. The studies were undertaken over 6 years, and sources of evidence involved participant observation, direct observations, analysis of documents and interviews. Two complementary ways for obtaining insights into inspections, based on ST, were identified: (i) the design of the study itself needs to be in line with ST; and (ii) data collection and analysis should focus on the agents involved in the inspections, the interactions between agents, the constraints and opportunities faced by agents, the outcomes of interactions, and the recommendations for influencing interactions. Copyright © 2015 Elsevier Ltd. All rights reserved.

Reactor safety under design basis flood condition for inland sites

International Nuclear Information System (INIS)

Hajela, S.; Bajaj, S.S.; Samota, A.; Verma, U.S.P.; Warudkar, A.S.

2002-01-01

Full text: In June 1994, there was an incident of flooding at Kakrapar Atomic Power Station (KAPS) due to combination of heavy rains and mechanical failure in the operation of gates at the adjoining weir. An indepth review of the incident was carried out and a number of flood protection measures were recommended and were implemented at site. As part of this review, a safety analysis was also done to demonstrate reactor safety with a series of failures considered in the flood protection features. For each inland NPP site, as part of design, different flood scenarios are analysed to arrive at design basis flood (DBF) level. This level is estimated based on worst combination of heavy local precipitation, flooding in river, failure of upstream/downstream water control structures

PROBLEMS OF APPLYING FIXED FORMULAE TO SAFETY CRITERIA AND SITE SELECTION

Energy Technology Data Exchange (ETDEWEB)

Davis, W. K.

1963-10-15

The problem of developing a formula or calculation procedure for that could more-or-less automatically indicate whether or not a nuclear plant would be considered safe at a particular location is discussed. The difficulties and impossibilities of any sach formula for making decisions on siting and safety involving large amounts of money and public safety are considered. (P.C.H.)

SITE-2, Power Plant Siting, Cost, Environment, Seismic and Meteorological Effects

International Nuclear Information System (INIS)

Frigerio, N.A.; Habegger, L.J.; King, R.F.; Hoover, L.J.; Clark, N.A.; Cobian, J.M.

1977-01-01

1 - Description of problem or function: SITE2 is designed to (1) screen candidate energy facility sites or areas within an electric utility region, based on the region's physical and socioeconomic attributes, the planned facility's characteristics, and impact assessments, and (2) evaluate the cumulative regional impacts associated with alternate energy supply options and inter-regional energy import/export practices, specifically, comparison of different energy technologies and their regional distribution in clustered or dispersed patterns. 2 - Method of solution: The SITE2 methodology is based on the quantification of three major site-related vectors. A cost vector is determined which identifies site-specific costs, such as transmission costs, cooling costs as related to water availability, and costs of specific controls needed to protect the surrounding environment. An impact vector is also computed for each potential site, using models of health and environmental impacts incurred in areas adjacent to the site. Finally, a site attribute vector is developed which reflects such characteristics as population, seismic conditions, meteorology, land use, and local ecological systems. This vector can be used to eliminate certain sites because of their inability to satisfy specific constraints. These three vectors can be displayed as density maps and combined in a simple overlay approach, similar to that developed by I. L. McHarg in reference 2, to identify candidate sites. Alternatively, the vector elements can be computationally combined into a weighted sum to obtain quantitative indicators of site suitability

SITE-2, Power Plant Siting, Cost, Environment, Seismic and Meteorological Effects

Energy Technology Data Exchange (ETDEWEB)

Frigerio, N A [Environmental Impact Studies, Argonne National Laboratory 9700 South Cass Avenue, Argonne, Illinois 60439 (United States); Habegger, L J; King, R F; Hoover, L J [Energy and Environmental Systems Division, Argonne National Laboratory 9700 South Cass Avenue, Argonne, Illinois 60439 (United States); Clark, N A [Applied Mathematics Division, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439 (United States); Cobian, J M [Northwestern University, Evanston, Illinois 60201 (United States)

1977-08-01

1 - Description of problem or function: SITE2 is designed to (1) screen candidate energy facility sites or areas within an electric utility region, based on the region's physical and socioeconomic attributes, the planned facility's characteristics, and impact assessments, and (2) evaluate the cumulative regional impacts associated with alternate energy supply options and inter-regional energy import/export practices, specifically, comparison of different energy technologies and their regional distribution in clustered or dispersed patterns. 2 - Method of solution: The SITE2 methodology is based on the quantification of three major site-related vectors. A cost vector is determined which identifies site-specific costs, such as transmission costs, cooling costs as related to water availability, and costs of specific controls needed to protect the surrounding environment. An impact vector is also computed for each potential site, using models of health and environmental impacts incurred in areas adjacent to the site. Finally, a site attribute vector is developed which reflects such characteristics as population, seismic conditions, meteorology, land use, and local ecological systems. This vector can be used to eliminate certain sites because of their inability to satisfy specific constraints. These three vectors can be displayed as density maps and combined in a simple overlay approach, similar to that developed by I. L. McHarg in reference 2, to identify candidate sites. Alternatively, the vector elements can be computationally combined into a weighted sum to obtain quantitative indicators of site suitability.

Confined Site Construction: A qualitative investigation of critical issues affecting management of Health and Safety

OpenAIRE

Spillane, John P.; Oyedele, Lukumon O.; Von Meding, Jason; Konanahalli, Ashwini; Jaiyeoba, Babatunde E.; Tijani, Iyabo K.

2011-01-01

The construction industry is inherently risky, with a significant number of accidents and disasters occurring, particularly on confined construction sites. This research investigates and identifies the various issues affecting successful management of health and safety in confined construction sites. The rationale is that identifying the issues would assist the management of health and safety particularly in inner city centres which are mostly confined sites. Using empiricism epistemology, th...

Temelin 3,4 Siting

International Nuclear Information System (INIS)

Kubanova, Iva; Fuzer, Jiri

2011-01-01

will follow. Siting process is three-step process in the Czech Republic. Finished EIA process managed by Ministry of Environment is a prerequisite for siting approval issued by State Office for Nuclear Safety. Then the final territorial decision is issued by building (construction) authority which can be located either in the relevant close city or in Southern Bohemia Region Office. Temelin site is a proven site, so siting of Temelin 3,4 is focused mainly on verification of available site data and methods used, verification of site suitability for new generation reactors and application of current licensing requirements. As a basis Initial Safety Report must be prepared and covers topics prescribed by the Czech Atomic Law: general project information, site evaluation, technical concept description, preliminary evaluation of operation impact on population, environment (with reference to EIA process), future decommissioning method, physical protection analyses and siting quality assurance evaluation and principles for next stages. CEZ, a. s. currently prepares Initial Safety Report in format pre-agreed with State Office for Nuclear Safety

Safety and the environment: Key to total quality

International Nuclear Information System (INIS)

Scott, J.N.

1991-01-01

The author briefly discusses the principles that guide the safety and environmental efforts of the petroleum industry. Specific examples are given of things that the industry is doing to carry out those principles. There are 12 principles which say that the petroleum industry will be responsive to the communities in which they operate. In general they say that waste will try to be eliminated; the industry will handle raw materials, products and waste in a safe manner; and that the petroleum industry will work with government to draft regulations that will improve the safety of the workplace and the environment

Site selection for deep geologic repositories - Consequences for society, economy and environment; was kommt auf die regionen zu? Auswirkungen geologischer tiefenlager auf gesellschaft, wirtschaft und lebensraum

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-03-15

In a few years, Switzerland will make the decision regarding site selection for geological underground repositories for the storage of radioactive wastes. Besides the safety issue, many citizens are interested in how such a repository will affect environment, economy and society in the selected site's region. This brochure summarizes the results of many studies on the socio-economic impacts of nuclear waste repositories. Radioactive wastes must be stored in such a way that mankind and environment are safely protected for a long period of time. How this goal may be achieved, is already known: geologic deep repositories warrant long-term safety. For the oncoming years in Switzerland the question is where the repository will be built. The search for an appropriate site for a repository in the proposed regions will launch discussions. Within the participative framework the regions may bring their requests. The demonstration of the safety of potential repository sites has the highest priority in the selection process. In the third procedural step additional rock investigations will be made. The socio-economic studies and the experience with existing plants show that radioactive waste management plants can be built and operated in good agreement with environmental requirements. The radioactive wastes in a deep underground repository are stored many hundred meters below the Earth's surface. There, they are isolated from our vital space. Technical barriers and the surrounding dense rock confinement prevent the release of radioactive materials into the environment. A deep repository has positive consequences for the regional economy. It increases trade and value creation and creates work places. The socio-economic impacts practically extend over one century, but strongly vary with time; they are the largest during the building period. High life quality and a positive population development in the selected site region are compatible with a deep repository. A fair

Safety aspects of geological studies around nuclear installations sites

International Nuclear Information System (INIS)

Faure, J.

1988-01-01

The experience of geological studies of about forty french nuclear sites allows to set out the objectives, the phases and the geographic extensions of workings to be realized for confirming a site. The data to be collected for the safety analysis are specified; they concern the local and regional geology, the geotechnical characteristics and the essential elements for evaluating the hazards related to the soil liquefaction, the surface fracturing and in some cases the volcanic risks. It is necessary to follow up the geology during the installation construction and life. 8 refs. (F.M.)

Real-time safety risk assessment based on a real-time location system for hydropower construction sites.

Science.gov (United States)

Jiang, Hanchen; Lin, Peng; Fan, Qixiang; Qiang, Maoshan

2014-01-01

The concern for workers' safety in construction industry is reflected in many studies focusing on static safety risk identification and assessment. However, studies on real-time safety risk assessment aimed at reducing uncertainty and supporting quick response are rare. A method for real-time safety risk assessment (RTSRA) to implement a dynamic evaluation of worker safety states on construction site has been proposed in this paper. The method provides construction managers who are in charge of safety with more abundant information to reduce the uncertainty of the site. A quantitative calculation formula, integrating the influence of static and dynamic hazards and that of safety supervisors, is established to link the safety risk of workers with the locations of on-site assets. By employing the hidden Markov model (HMM), the RTSRA provides a mechanism for processing location data provided by the real-time location system (RTLS) and analyzing the probability distributions of different states in terms of false positives and negatives. Simulation analysis demonstrated the logic of the proposed method and how it works. Application case shows that the proposed RTSRA is both feasible and effective in managing construction project safety concerns.

Health and safety annual report 1988

International Nuclear Information System (INIS)

1989-01-01

This report on health and safety provides a review of the impact of the Comapny's activities on its workforce, the public and the environment. New sections include safety auditing, emergency planning and health and safety research. BNFL operates five sites in north west England and southern Scotland. The head office and Engineering Design Centre is at Risley, near Warrington. Fuel is manufactured at Springfields near Preston, uranium is enriched for modern nuclear power stations at Capenhurst near Chester and spent fuel is reprocessed at Sellafield. BNFL also operate Calder Hall (Sellafield) and Chapelcross (Scotland) power stations and a disposal site for low-level radioactive wastes at Drigg near Sellafield. Radiation sources and BNFL's radioactive discharge are first explained generally and then specifically for each BNFL site. Industrial and radiological safety within BNFL are described. (UK)

78 FR 76391 - Proposed Enhancements to the Motor Carrier Safety Measurement System (SMS) Public Web Site

Science.gov (United States)

2013-12-17

...-0392] Proposed Enhancements to the Motor Carrier Safety Measurement System (SMS) Public Web Site AGENCY... proposed enhancements to the display of information on the Agency's Safety Measurement System (SMS) public Web site. On December 6, 2013, Advocates [[Page 76392

Criticality Safety Evaluation of Hanford Site High Level Waste Storage Tanks

Energy Technology Data Exchange (ETDEWEB)

ROGERS, C.A.

2000-02-17

This criticality safety evaluation covers operations for waste in underground storage tanks at the high-level waste tank farms on the Hanford site. This evaluation provides the bases for criticality safety limits and controls to govern receipt, transfer, and long-term storage of tank waste. Justification is provided that a nuclear criticality accident cannot occur for tank farms operations, based on current fissile material and operating conditions.

Criticality Safety Evaluation of Hanford Site High-Level Waste Storage Tanks

International Nuclear Information System (INIS)

ROGERS, C.A.

2000-01-01

This criticality safety evaluation covers operations for waste in underground storage tanks at the high-level waste tank farms on the Hanford site. This evaluation provides the bases for criticality safety limits and controls to govern receipt, transfer, and long-term storage of tank waste. Justification is provided that a nuclear criticality accident cannot occur for tank farms operations, based on current fissile material and operating conditions

Integrated model of port oil piping transportation system safety including operating environment threats

Directory of Open Access Journals (Sweden)

Kołowrocki Krzysztof

2017-06-01

Full Text Available The paper presents an integrated general model of complex technical system, linking its multistate safety model and the model of its operation process including operating environment threats and considering variable at different operation states its safety structures and its components safety parameters. Under the assumption that the system has exponential safety function, the safety characteristics of the port oil piping transportation system are determined.

Integrated model of port oil piping transportation system safety including operating environment threats

OpenAIRE

Kołowrocki, Krzysztof; Kuligowska, Ewa; Soszyńska-Budny, Joanna

2017-01-01

The paper presents an integrated general model of complex technical system, linking its multistate safety model and the model of its operation process including operating environment threats and considering variable at different operation states its safety structures and its components safety parameters. Under the assumption that the system has exponential safety function, the safety characteristics of the port oil piping transportation system are determined.

Environment, health and safety progress report 1997

International Nuclear Information System (INIS)

1998-01-01

Imperial Oil is Canada's largest producer of crude oil and a major producer of natural gas. It is also the largest refiner and marketer of petroleum products, sold mainly under the Esso brand. Imperial Oil, in participation with Syncrude Canada, is also a major developer of the oil sands reserves in Cold Lake, Alberta. This review of environmental and health and safety performance in 1997 highlights the Company's comprehensive approach to risk management to reduce risk to safety, health and the environment. It is noted that in 1997, the Company's employee and contractor safety performance continued to be among the best in the industry. Potentially hazardous incidents decreased as a consequence of Imperial Oil's more stringent health and safety management system. Environmental compliance notifications fell by more than half in 1997. During the year there was a slight increase in hazardous wastes, due to the loss of outlets for recycling some materials. The National Pollutants Release Inventory indicates that Imperial has reduced emissions and offsite transfers by 25 per cent since 1993. Volatile organic compounds have been reduced by 60 per cent since 1993. According to the report all Imperial Oil facilities operate well within the guidelines for sulphur dioxide emissions. 1 tab., 10 figs

Area 5 Radioactive Waste Management Site Safety Assessment Document

International Nuclear Information System (INIS)

Horton, K.K.; Kendall, E.W.; Brown, J.J.

1980-02-01

The Area 5 Radioactive Waste Management Safety Assessment Document evaluates site characteristics, facilities and operating practices which contribute to the safe handling and storage/disposal of radioactive wastes at the Nevada Test Site. Physical geography, cultural factors, climate and meteorology, geology, hydrology (with emphasis on radionuclide migration), ecology, natural phenomena, and natural resources are discussed and determined to be suitable for effective containment of radionuclides. Also considered, as a separate section, are facilities and operating practices such as monitoring; storage/disposal criteria; site maintenance, equipment, and support; transportation and waste handling; and others which are adequate for the safe handling and storage/disposal of radioactive wastes. In conclusion, the Area 5 Radioactive Waste Management Site is suitable for radioactive waste handling and storage/disposal for a maximum of twenty more years at the present rate of utilization

End of mission report on seismic safety review mission for Belene NPP site

International Nuclear Information System (INIS)

Gurpinar, A.; Mohammadioun, B.; Schneider, H.; Serva, L.

1995-01-01

Upon the invitation of the Bulgarian government through the Committee for the Peaceful Uses of Atomic Energy and within the framework of the implementation of the Technical Cooperation project BUL/9/012 related to site and seismic of NPPs, a mission visited Sofia 3 - 7 July 1995. The mission constituted a follow-up of the interim review of subjects related to tectonic stability and seismic hazard characterization of the site which was performed in September 1993. The main objective of the mission was the final review of the subjects already reviewed in September 1993 as well as issues related to geotechnical engineering and foundation safety. The main terms of reference of the present mission was to verify the implementation of the recommendations of the Site Safety Review Mission of June 1990. This document gives findings on geology-tectonics, seismology and foundation safety. In the end conclusions and recommendations of the mission are presented

Corrosion calculations report for the safety assessment SR-Site

International Nuclear Information System (INIS)

2010-12-01

This report is a compilation of the quantitative assessments of corrosion of the copper canisters in a KBS-3 repository. The calculations are part of the safety assessment SR-Site that is the long-term safety assessment to support the license application for building a final repository for spent nuclear fuel at Forsmark, Sweden. The safety assessment methodology gives the frame for the structured and documented approach to assess all conceivable corrosion processes. The quantitative assessments are done in different ways depending on the nature of the process and on the implications for the long-term safety. The starting point for the handling of the corrosion processes is the description of all known corrosion processes for copper with the current knowledge base and applied to the specific system and geology. Already at this stage some processes are excluded for further analysis, for example if the repository environment is not a sufficient prerequisite for the process to occur. The next step is to identify processes where the extent of corrosion could be bounded, e.g. by a mass balance approach. For processes where a mass balance is not limiting, the mass transport of corrodants (or corrosion products) is taken into account. A simple approach would be just to calculate the diffusive transport of corrodants through the bentonite, but generally the transport resistance for the interface between groundwater in a rock fracture intersecting the deposition hole and the bentonite buffer is more important. In SR-Site, the concept of equivalent flowrate, Q eq , is used. This assessment is done integrated with the evaluation of the geochemical and hydrogeological evolution of the repository. For most of the corrosion processes analysed, the corrosion depth is much smaller than the copper shell thickness, even for the assessment time of 10 6 years. Several processes give corrosion depths less than 100 μm, but no process give corrosion depths larger than a few millimetres

Corrosion calculations report for the safety assessment SR-Site

Energy Technology Data Exchange (ETDEWEB)

2010-12-15

This report is a compilation of the quantitative assessments of corrosion of the copper canisters in a KBS-3 repository. The calculations are part of the safety assessment SR-Site that is the long-term safety assessment to support the license application for building a final repository for spent nuclear fuel at Forsmark, Sweden. The safety assessment methodology gives the frame for the structured and documented approach to assess all conceivable corrosion processes. The quantitative assessments are done in different ways depending on the nature of the process and on the implications for the long-term safety. The starting point for the handling of the corrosion processes is the description of all known corrosion processes for copper with the current knowledge base and applied to the specific system and geology. Already at this stage some processes are excluded for further analysis, for example if the repository environment is not a sufficient prerequisite for the process to occur. The next step is to identify processes where the extent of corrosion could be bounded, e.g. by a mass balance approach. For processes where a mass balance is not limiting, the mass transport of corrodants (or corrosion products) is taken into account. A simple approach would be just to calculate the diffusive transport of corrodants through the bentonite, but generally the transport resistance for the interface between groundwater in a rock fracture intersecting the deposition hole and the bentonite buffer is more important. In SR-Site, the concept of equivalent flowrate, Q{sub eq}, is used. This assessment is done integrated with the evaluation of the geochemical and hydrogeological evolution of the repository. For most of the corrosion processes analysed, the corrosion depth is much smaller than the copper shell thickness, even for the assessment time of 106 years. Several processes give corrosion depths less than 100 mum, but no process give corrosion depths larger than a few

Information report of AREVA La Hague site, written in compliance with article L. 125-15 of the French environment code - 2015 Edition

International Nuclear Information System (INIS)

2016-01-01

Published in compliance with the French code of the environment, this report presents, first, the Areva La Hague site with its facilities and activities in relation with spent fuel reprocessing and radioactive waste management. Then, it takes stock of the dispositions implemented for the limitation and prevention of risks and summarizes the events declared in 2015. Next, it presents the management of the site effluents and wastes and the environmental monitoring. Finally, the actions of public information are presented. The recommendations of the Health and safety Committee are included in appendix

Environment, Safety, and Health Self-Assessment Report, Fiscal Year 2008

Energy Technology Data Exchange (ETDEWEB)

Chernowski, John

2009-02-27

Lawrence Berkeley National Laboratory's Environment, Safety, and Health (ES&H) Self-Assessment Program ensures that Integrated Safety Management (ISM) is implemented institutionally and by all divisions. The Self-Assessment Program, managed by the Office of Contract Assurance (OCA), provides for an internal evaluation of all ES&H programs and systems at LBNL. The functions of the program are to ensure that work is conducted safely, and with minimal negative impact to workers, the public, and the environment. The Self-Assessment Program is also the mechanism used to institute continuous improvements to the Laboratory's ES&H programs. The program is described in LBNL/PUB 5344, Environment, Safety, and Health Self-Assessment Program and is composed of four distinct assessments: the Division Self-Assessment, the Management of Environment, Safety, and Health (MESH) review, ES&H Technical Assurance, and the Appendix B Self-Assessment. The Division Self-Assessment uses the five core functions and seven guiding principles of ISM as the basis of evaluation. Metrics are created to measure performance in fulfilling ISM core functions and guiding principles, as well as promoting compliance with applicable regulations. The five core functions of ISM are as follows: (1) Define the Scope of Work; (2) Identify and Analyze Hazards; (3) Control the Hazards; (4) Perform the Work; and (5) Feedback and Improvement. The seven guiding principles of ISM are as follows: (1) Line Management Responsibility for ES&H; (2) Clear Roles and Responsibilities; (3) Competence Commensurate with Responsibilities; (4) Balanced Priorities; (5) Identification of ES&H Standards and Requirements; (6) Hazard Controls Tailored to the Work Performed; and (7) Operations Authorization. Performance indicators are developed by consensus with OCA, representatives from each division, and Environment, Health, and Safety (EH&S) Division program managers. Line management of each division performs the

Preliminary safety evaluation for the Forsmark area. Based on data and site descriptions after the initial site investigation stage

International Nuclear Information System (INIS)

Andersson, Johan

2005-08-01

The main objectives of this Preliminary Safety Evaluation (PSE) of the Forsmark area have been to determine, with limited efforts, whether the feasibility study's judgement of the suitability of the candidate area with respect to long-term safety holds up in the light of the actual site investigation data; to provide feedback to continued site investigations and site-specific repository design and to identify site-specific scenarios and geoscientific issues for further analyses. The PSE focuses on comparing the attained knowledge of the sites with the suitability criteria as set out by SKB. The PSE does not aim at comparing sites and does not assess compliance with safety and radiation protection criteria. The evaluation shows that, even considering remaining uncertainties, the Forsmark area meets all stated safety requirements and preferences. Consequently, from a safety point of view, there is no reason not to continue the Site Investigations of the Forsmark area. There are still uncertainties to resolve and the safety would eventually need to be verified through a full safety assessment. Nevertheless, this Preliminary Safety Evaluation demonstrates that it is likely that a safe repository for spent nuclear fuel of the KBS-3 type could be constructed at the site. The following feedback is provided to the site investigations and the associated site modelling: Reducing the uncertainty on the deformation zone geometry inside the target area would be needed to more firmly define locations of the suitable deposition volumes. There is substantial uncertainty in the Discrete Fracture Network model. Further reduction of the uncertainties, if needed, would probably only be possible from the underground, detailed investigation phase. Efforts need also be spent on improving the DFN-modelling. There are assumptions made in current models that could be challenged and there seems to be room for better use of the borehole information. It is particularly important to provide

Preliminary safety evaluation for the Forsmark area. Based on data and site descriptions after the initial site investigation stage

Energy Technology Data Exchange (ETDEWEB)

Andersson, Johan [JA Streamflow AB, Aelvsjoe (Sweden)

2005-08-01

The main objectives of this Preliminary Safety Evaluation (PSE) of the Forsmark area have been to determine, with limited efforts, whether the feasibility study's judgement of the suitability of the candidate area with respect to long-term safety holds up in the light of the actual site investigation data; to provide feedback to continued site investigations and site-specific repository design and to identify site-specific scenarios and geoscientific issues for further analyses. The PSE focuses on comparing the attained knowledge of the sites with the suitability criteria as set out by SKB. The PSE does not aim at comparing sites and does not assess compliance with safety and radiation protection criteria. The evaluation shows that, even considering remaining uncertainties, the Forsmark area meets all stated safety requirements and preferences. Consequently, from a safety point of view, there is no reason not to continue the Site Investigations of the Forsmark area. There are still uncertainties to resolve and the safety would eventually need to be verified through a full safety assessment. Nevertheless, this Preliminary Safety Evaluation demonstrates that it is likely that a safe repository for spent nuclear fuel of the KBS-3 type could be constructed at the site. The following feedback is provided to the site investigations and the associated site modelling: Reducing the uncertainty on the deformation zone geometry inside the target area would be needed to more firmly define locations of the suitable deposition volumes. There is substantial uncertainty in the Discrete Fracture Network model. Further reduction of the uncertainties, if needed, would probably only be possible from the underground, detailed investigation phase. Efforts need also be spent on improving the DFN-modelling. There are assumptions made in current models that could be challenged and there seems to be room for better use of the borehole information. It is particularly important to

Plutonium working group report on environmental, safety and health vulnerabilities associated with the department's plutonium storage. Volume II, Appendix B, Part 9: Oak Ridge site site team report

International Nuclear Information System (INIS)

1994-09-01

This report provides the input to and results of the Department of Energy (DOE) - Oak Ridge Operations (ORO) DOE Plutonium Environment, Safety and Health (ES ampersand H) Vulnerability Assessment (VA) self-assessment performed by the Site Assessment Team (SAT) for the Oak Ridge National Laboratory (ORNL or X-10) and the Oak Ridge Y-12 Plant (Y-12) sites that are managed by Martin Marietta Energy Systems, Inc. (MMES). As initiated (March 15, 1994) by the Secretary of Energy, the objective of the VA is to identify and rank-order DOE-ES ampersand H vulnerabilities associated for the purpose of decision making on the interim safe management and ultimate disposition of fissile materials. This assessment is directed at plutonium and other co-located transuranics in various forms

Safety in numbers: does perceived safety mediate associations between the neighborhood social environment and physical activity among women living in disadvantaged neighborhoods?

Science.gov (United States)

Timperio, Anna; Veitch, Jenny; Carver, Alison

2015-05-01

The aim of this study is to examine associations between the neighborhood social environment and leisure-time physical activity (LTPA)(1) and walking among women, and whether these associations are mediated by perceived personal safety. Women (n = 3784) living in disadvantaged urban and rural neighborhoods within Victoria, Australia completed a self-administered survey on five social environment variables (neighborhood crime, neighborhood violence, seeing others walking and exercising in the neighborhood, social trust/cohesion), perceived personal safety, and their physical activity in 2007/8. Linear regression analyses examined associations between social environment variables and LTPA and walking. Potential mediating pathways were assessed using the product-of-coefficients test. Moderated mediation by urban/rural residence was examined. Each social environment variable was positively associated with engaging in at least 150 min/week of LTPA (OR = 1.16 to 1.56). Only two social environment variables, seeing others walking (OR = 1.45) and exercising (OR = 1.31), were associated with ≥ 150 min/week of walking. Perceived personal safety mediated all associations. Stronger mediation was found in urban areas for crime, violence and social trust/cohesion. The neighborhood social environment is an important influence on physical activity among women living in disadvantaged areas. Feelings of personal safety should not be included in composite or aggregate scores relating to the social environment. Copyright © 2015 Elsevier Inc. All rights reserved.

Waset Isolation Pilot Plant Annual Site Environmental Report for 2006

Energy Technology Data Exchange (ETDEWEB)

Washington Regulatory and Environmental Services; Washington TRU Solutions LLC

2007-09-26

The purpose of the Waste Isolation Pilot Plant Annual Site Environmental Report for 2006 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1A, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data that: (a) Characterize site environmental management performance; (b) Summarize environmental occurrences and responses reported during the calendar year; (c) Confirm compliance with environmental standards and requirements; and (d) Highlight significant facility programs and efforts. The DOE Carlsbad Field Office (CBFO) and Washington TRU Solutions LLC (WTS) maintain and preserve the environmental resources at the WIPP site. DOE Order 231.1A; DOE Order 450.1, Environmental Protection Program; and DOE Order 5400.5, Radiation Protection of the Public and Environment, require that the affected environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This report was prepared in accordance with DOE Order 231.1A. This order requires that DOE facilities submit an ASER to the DOE Headquarters Office of the Assistant Secretary for Environment, Safety, and Health. The WIPP Hazardous Waste Facility Permit (HWFP) (No. NM4890139088-TSDF [treatment, storage, and disposal facility]) further requires that the ASER be provided to the New Mexico Environment Department (NMED).

Waset Isolation Pilot Plant Annual Site Environmental Report for 2006

International Nuclear Information System (INIS)

2007-01-01

The purpose of the Waste Isolation Pilot Plant Annual Site Environmental Report for 2006 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1A, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data that: (a) Characterize site environmental management performance; (b) Summarize environmental occurrences and responses reported during the calendar year; (c) Confirm compliance with environmental standards and requirements; and (d) Highlight significant facility programs and efforts. The DOE Carlsbad Field Office (CBFO) and Washington TRU Solutions LLC (WTS) maintain and preserve the environmental resources at the WIPP site. DOE Order 231.1A; DOE Order 450.1, Environmental Protection Program; and DOE Order 5400.5, Radiation Protection of the Public and Environment, require that the affected environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This report was prepared in accordance with DOE Order 231.1A. This order requires that DOE facilities submit an ASER to the DOE Headquarters Office of the Assistant Secretary for Environment, Safety, and Health. The WIPP Hazardous Waste Facility Permit (HWFP) (No. NM4890139088-TSDF [treatment, storage, and disposal facility]) further requires that the ASER be provided to the New Mexico Environment Department (NMED).

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.

Central repository for low- and intermediate-level waste (ALMA) conceptual design, siting and safety study

International Nuclear Information System (INIS)

Kjellbert, N.; Haeggblom, H.; Cederstroem, M.; Lundgren, T.

1980-07-01

A generic design, siting and safety study of a proposed repository for low- and intermediate-level waste has been made. Special emphasis has been placed on safety characterostics. The conceptual design and the generic site, on which the study is based, are realistically chosen in accordance with present construction techniques and the existing geohydrological conditions in Sweden. (Auth.)

Siting of geological disposal facilities

International Nuclear Information System (INIS)

1994-01-01

Radioactive waste is generated from the production of nuclear energy and from the use of radioactive materials in industrial applications, research and medicine. The importance of safe management of radioactive waste for the protection of human health and the environment has long been recognized and considerable experience has been gained in this field. The Radioactive Waste Safety Standards (RADWASS) programme is the IAEA's contribution to establishing and promoting the basic safety philosophy for radioactive waste management and the steps necessary to ensure its implementation. This Safety Guide defines the process to be used and guidelines to be considered in selecting sites for deep geological disposal of radioactive wastes. It reflects the collective experience of eleven Member States having programmes to dispose of spent fuel, high level and long lived radioactive waste. In addition to the technical factors important to site performance, the Safety Guide also addresses the social, economic and environmental factors to be considered in site selection. 3 refs

Occupational health and environment research 1983: Health, Safety, and Environment Division. Progress report

International Nuclear Information System (INIS)

Voelz, G.L.

1985-05-01

The primary responsibility of the Health, Safety, and Environment (HSE) Division at the Los Alamos National Laboratory is to provide comprehensive occupational health and safety programs, waste processing, and environmental protection. These activities are designed to protect the workers, the public, and the environment. Evaluation of respiratory protective equipment included the XM-30 and M17A1 military masks, use of MAG-1 spectacles in respirators, and eight self-contained units. The latter units were used in an evaluation of test procedures used for Bureau of Mines approval of breathing apparatuses. Analyses of air samples from field studies of a modified in situ oil shale retorting facility were performed for total cyclohexane extractables and selected polynuclear aromatic hydrocarbons. Aerosols generation and characterization of effluents from oil shale processing were continued as part of an inhalation toxicology study. Additional data on plutonium excretion in urine are presented and point up problems in using the Langham equation to predict plutonium deposition in the body from long-term excretion data. Environmental surveillance at Los Alamos during 1983 showed the highest estimated radiation dose from Laboratory operations to be about 26% of the natural background radiation dose. Several studies on radionuclides and their transport in the Los Alamos environment are described. The chemical quality of surface and ground water near the geothermal hot dry rock facility is described. Short- and long-term consequences to man from releases of radionuclides into the environment can be simulated by the BIOTRAN computer model, which is discussed brirfly

The USERDA transport R and D program for environment and safety

International Nuclear Information System (INIS)

Sisler, J.A.

1976-01-01

This paper describes the U.S. Energy Research and Development Administration's (ERDA) transportation environment and safety research and development program for energy fuels and wastes, including background, current activities, and future plans. It will serve as an overview and integrating factor for the several related technical papers to be presented at this meeting which will enlarge on the detail of specific projects. The transportation R and D program provides for the environmental and safety review of transport systems and procedures; standards development; and package, vehicle, and systems testing for nuclear materials transport. A primary output of the program is the collection, processing, and dissemination of transport environment and safety data, shipment statistics, and technical information. Special transport projects which do not easily fit elsewhere in ERDA are usually done as a part of this program. (author)

Supporting Multiprocessors in the Icecap Safety-Critical Java Run-Time Environment

DEFF Research Database (Denmark)

Zhao, Shuai; Wellings, Andy; Korsholm, Stephan Erbs

The current version of the Safety Critical Java (SCJ) specification defines three compliance levels. Level 0 targets single processor programs while Level 1 and 2 can support multiprocessor platforms. Level 1 programs must be fully partitioned but Level 2 programs can also be more globally...... scheduled. As of yet, there is no official Reference Implementation for SCJ. However, the icecap project has produced a Safety-Critical Java Run-time Environment based on the Hardware-near Virtual Machine (HVM). This supports SCJ at all compliance levels and provides an implementation of the safety......-critical Java (javax.safetycritical) package. This is still work-in-progress and lacks certain key features. Among these is the ability to support multiprocessor platforms. In this paper, we explore two possible options to adding multiprocessor support to this environment: the “green thread” and the “native...

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...

Radioactivity in food and the environment, 1998

International Nuclear Information System (INIS)

1999-09-01

The safety of food and protection of the environment continue to be important issues on the Government's agenda. Radioactivity in food and the environment, a source of potential harm, therefore receives continuous surveillance to ensure that public safety targets and international commitments are met and ensure that the environment is effectively protected. The Government makes the results of such surveillance widely available through publication of this report and through regular updates on the MAFF Web site. This technical report presents the scope and results of our radiological surveillance programmes for 1998. It is complemented in England and Wales by the Environment Agency's surveillance report on non-food pathways. Sponsored by the Joint Food Safety and Standards Group of the Ministry of Agriculture, Fisheries and Food and the Scottish Environment Protection Agency, measurements of radioactivity have been carried out in a wide range of foodstuffs and in the environment around nuclear sites and other potential sources of elevated radioactivity throughout the United Kingdom, and also at locations remote from these sources. This report demonstrates that the public is being protected against unacceptable contamination of the food chain and that the UK is fully meeting public safety targets. We remain committed to ensuring that a proper and rigorous surveillance programme is continued to ensure that this remains the case. (author)

Safety Aspects of Sustainable Storage Dams and Earthquake Safety of Existing Dams

Directory of Open Access Journals (Sweden)

Martin Wieland

2016-09-01

Full Text Available The basic element in any sustainable dam project is safety, which includes the following safety elements: ① structural safety, ② dam safety monitoring, ③ operational safety and maintenance, and ④ emergency planning. Long-term safety primarily includes the analysis of all hazards affecting the project; that is, hazards from the natural environment, hazards from the man-made environment, and project-specific and site-specific hazards. The special features of the seismic safety of dams are discussed. Large dams were the first structures to be systematically designed against earthquakes, starting in the 1930s. However, the seismic safety of older dams is unknown, as most were designed using seismic design criteria and methods of dynamic analysis that are considered obsolete today. Therefore, we need to reevaluate the seismic safety of existing dams based on current state-of-the-art practices and rehabilitate deficient dams. For large dams, a site-specific seismic hazard analysis is usually recommended. Today, large dams and the safety-relevant elements used for controlling the reservoir after a strong earthquake must be able to withstand the ground motions of a safety evaluation earthquake. The ground motion parameters can be determined either by a probabilistic or a deterministic seismic hazard analysis. During strong earthquakes, inelastic deformations may occur in a dam; therefore, the seismic analysis has to be carried out in the time domain. Furthermore, earthquakes create multiple seismic hazards for dams such as ground shaking, fault movements, mass movements, and others. The ground motions needed by the dam engineer are not real earthquake ground motions but models of the ground motion, which allow the safe design of dams. It must also be kept in mind that dam safety evaluations must be carried out several times during the long life of large storage dams. These features are discussed in this paper.

Environment, safety and health compliance assessment, Feed Materials Production Center, Fernald, Ohio

Energy Technology Data Exchange (ETDEWEB)

1989-09-01

The Secretary of Energy established independent Tiger Teams to conduct environment, safety, and health (ES H) compliance assessments at US Department of Energy (DOE) facilities. This report presents the assessment of the Feed Materials Production Center (FMPC) at Fernald, Ohio. The purpose of the assessment at FMPC is to provide the Secretary with information regarding current ES H compliance status, specific ES H noncompliance items, evaluation of the adequacy of the ES H organizations and resources (DOE and contractor), and root causes for noncompliance items. Areas reviewed included performance under Federal, state, and local agreements and permits; compliance with Federal, state and DOE orders and requirements; adequacy of operations and other site activities, such as training, procedures, document control, quality assurance, and emergency preparedness; and management and staff, including resources, planning, and interactions with outside agencies.

Alberta Environment's weir safety program : options for rehabilitation to improve public safety : a case study of the Calgary weir

Energy Technology Data Exchange (ETDEWEB)

Blakely, D [Alberta Environment, Edmonton, AB (Canada)

2009-07-01

Alberta Environment Water Management Operations (WMO) owns and operates 46 dams and 800 kilometres of canals in Alberta. The WMO consists of 120 staff and several contract operators to take care of this infrastructure. Most of the infrastructure supplies water for irrigation use, which adds 5 billion dollars to the provincial economy annually. Other water uses include stock watering, domestic use, municipal use, recreational use and habitat. Alberta Environment's weir safety program was also discussed along with options for rehabilitation to improve public safety. A case study of Calgary's Weir Dam on the Bow River was highlighted. A brief history of the dam was offered and safety programs around provincially-owned weirs were discussed. Photographs were included to illustrate some of the additional safety measures at the Calgary weir, such as suspended safety buoys upstream of the boom directing paddlers to the portage trail, and signage on the river that can be activated when the boom is out. Typical river users on the Calgary Bow River and safety history at the Calgary Weir were discussed along with other topics such as the Calgary Bow River weir project criteria; project design progress; pre-feasibility options; scale modelling; final design analysis; construction funding; and proposed changes to the safety program for the new weir configuration. figs.

Environment report 1990 of the Federal Minister for the Environment, Nature Protection and Reactor Safety

International Nuclear Information System (INIS)

1990-01-01

The 'Environment Report 1990' describes the environmental situation in the Federal Republic of Germany; draws a balance of environmental policy measures taken and introduced; gives information on future fields of action in environmental policy. The 'Environment Report 1990' also deals with the 'Environment Expert Opinion 1987', produced by the board of experts on environmental questions. It contains surveys of the following sectors: Protection against hazardous materials air pollution abatement, water management, waste management, nature protection and preservation of the countryside, soil conservation, noise abatement, radiation protection, reactor safety. A separate part of the 'Environment Report 1990' deals with the progress made in 'interdisciplinary fields' (general law on the protection of the environment, instruments of environmental policy, environmental information and environmental research, transfrontier environmental policy). (orig./HP) [de

Savannah River Site Environmental Implentation Plan

International Nuclear Information System (INIS)

1989-01-01

This report describes the organizational responsibilities for the Savannah River Site Environmental program. Operations, Engineering and projects, Environment, safety, and health, Quality assurance, and the Savannah River Laboratory are described

ICT support safety, health and environment management system (e-SHEMS)

International Nuclear Information System (INIS)

Amy Hamijah Ab Hamid; Hasfazilah Hassan; Siti Massari Amran; Norzalina Nasirudin; Azimawati Ahmad; Mohd Suhaimi Kassim; Shaharum Ramli; Musa Ibrahim; Mohd Sidek Othman

2009-01-01

Safety program is compulsory for a nuclear technology related research and development institution like Nuclear Malaysia. It has been implemented in various safety standard systems including Act 514, Act 304, ISO 14000, OSHAS 18001 and IAEA. This paper began with Nuclear Malaysia history in initiating our own safety standard system since 1982. Currently, Nuclear Malaysia's Safety Health and Environment Management System (SHE-MS) was stipulated for similar purpose. Furthermore, it has implemented guidelines by AELB, IAEA, DOSH, Fire Brigade and Police Force. This paper briefly describes the overall structure of SHE-MS, how it functions and being managed, and lessons learned. The findings which are based on the issues and challenges, then it can be analysed to propose a development of SHE-MS ICT-support application for future improvement and enhancement in inculcating and nurturing safety culture among Nuclear Malaysia staff. (Author)

WNA's Policy Document : sustaining global best practices in uranium, mining and processing, principles for managing radiation, health and safety, waste and the environment

International Nuclear Information System (INIS)

Saint-Pierre, S.; Waste Management and Decommissioning Working Group-WM and DW

2008-01-01

The worldwide community of uranium mining and processing recognizes that managing radiation, health and safety, waste and the environment is paramount. Such responsible management applies at all stages of planning and activities. Today we are acting to ensure that all parties directly involved in uranium mining and processing strive to achieve the highest levels of excellence in these fields. We are doing so by sustaining a strong safety culture based on a commitment to common, internationally shared principles. This paper sets out principles for the management of radiation, health and safety, waste and the environment applicable to sites throughout the world. In national and regional settings where nuclear fuel cycle activities are well developed, these principles already serve as the underpinning for 'Codes of Practice' that govern uranium mining and processing. In any given setting, a Code of Practice is needed to guide practical implementation of these principles according to the regional, national or site-specific context. These principles are published in the belief that they hold special relevance for emerging uranium producing countries that do not yet have fully developed regulations for the control of radiation, health and safety, waste and the environment associated with uranium mining and processing. The principles are equally relevant for operators, contractors, and regulators newly engaged in uranium mining and processing. Once national regulations are fully developed, they can be expected to embody these principles. Each principle affirmed here will not apply to the same extent for each party. Ultimately, the precise allocation of responsibilities must be set at the national and local levels. This document holds the status of a policy and ethical declaration by the full WNA membership, which the global nuclear industry. The principles affirmed here are supported by key relevant international organizations, including the IAEA and the global mining

Alternative biosphere modeling for safety assessment of HLW disposal taking account of geosphere-biosphere interface of marine environment

International Nuclear Information System (INIS)

Kato, Tomoko; Ishiguro, Katsuhiko; Naito, Morimasa; Ikeda, Takao; Little, Richard

2001-03-01

In the safety assessment of a high-level radioactive waste (HLW) disposal system, it is required to estimate radiological impacts on future human beings arising from potential radionuclide releases from a deep repository into the surface environment. In order to estimated the impacts, a biosphere model is developed by reasonably assuming radionuclide migration processes in the surface environment and relevant human lifestyles. It is important to modify the present biosphere models or to develop alternative biosphere models applying the biosphere models according to quality and quantify of the information acquired through the siting process for constructing the repository. In this study, alternative biosphere models were developed taking geosphere-biosphere interface of marine environment into account. Moreover, the flux to dose conversion factors calculated by these alternative biosphere models was compared with those by the present basic biosphere models. (author)

MOBILITY, ENVIRONMENT AND SAFETY IN MEGACITIES

Directory of Open Access Journals (Sweden)

Dinesh MOHAN

2000-01-01

Full Text Available This paper focuses on issues concerning mobility, pollution and safety in megacities of less motorised countries (LMCs using Delhi (India as an example. Issues discussed are: Urban transport and land use patterns, planning, systems management and infrastructure development, fuel quality and alternate fuels, control of car ownership, in-use maintenance and inspection, fuel efficiency and technologies, pedestrian and bicycle environments and road safety. The patterns of traffic and management issues in LMCs are very complex and some of their problems have not been faced by the richer countries in the past. In LMC cities' non-motorised modes of transport and some form of public transport/para-transit already constitute a significant proportion of all trips. It will be difficult to increase this share unless these modes are made much more convenient and safer. Unless people actually perceive that they are not inconvenienced or exposed to greater risks as bicyclists, pedestrians and bus commuters it will be difficult to reduce private vehicle use. Buses and non-motorised modes of transport will remain the backbone of mobility in LMC mega-cities. To control pollution both bus use and non-motorised forms of transport have to be given importance without increasing the rate of road accidents. These issues have to be considered in an overall context where safety and environmental research efforts are not conducted in complete isolation.

30 CFR 250.107 - What must I do to protect health, safety, property, and the environment?

Science.gov (United States)

2010-07-01

..., property, and the environment? 250.107 Section 250.107 Mineral Resources MINERALS MANAGEMENT SERVICE... Performance Standards § 250.107 What must I do to protect health, safety, property, and the environment? (a) You must protect health, safety, property, and the environment by: (1) Performing all operations in a...

Site environmental report for 1996

International Nuclear Information System (INIS)

Holland, R.C.

1997-08-01

To help verify effective protection of public safety and preservation of the environment, Sandia National Laboratories (SNL)/California maintains an extensive, ongoing environmental monitoring program. This program monitors all significant airborne and liquid effluents and the environment at the SNL/California site perimeter. Lawrence Livermore National Laboratory (LLNL) performs off-site environmental monitoring for both sites. These monitoring efforts ensure that emission controls are effective in preventing contamination of the environment. As part of SNL/California's Environmental Monitoring Program, an environmental surveillance system measures the possible presence of radioactive and hazardous materials in ambient air, surface water, groundwater, sewage, soil, vegetation, and locally produced food-stuffs. The program also includes an extensive environmental dosimetry program, which measures external radiation levels around the Livermore site and nearby vicinity. Each year, the results of the Environmental Monitoring Program are published in this report, the Site Environmental Report. This executive summary focuses on impacts to the environment and estimated radiation doses to the public from site emissions. Chapter 3, open-quotes Compliance Summary,close quotes reviews the site's various environmental protection activities and compliance status, with applicable environmental regulations. The effluent monitoring and environmental surveillance results for 1996 show that SNL/California operations had no harmful effects on the environment or the public. 37 figs., 12 tabs

Plutonium working group report on environmental, safety and health vulnerabilities associated with the department`s plutonium storage. Volume II, Appendix B, Part 9: Oak Ridge site site team report

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-09-01

This report provides the input to and results of the Department of Energy (DOE) - Oak Ridge Operations (ORO) DOE Plutonium Environment, Safety and Health (ES & H) Vulnerability Assessment (VA) self-assessment performed by the Site Assessment Team (SAT) for the Oak Ridge National Laboratory (ORNL or X-10) and the Oak Ridge Y-12 Plant (Y-12) sites that are managed by Martin Marietta Energy Systems, Inc. (MMES). As initiated (March 15, 1994) by the Secretary of Energy, the objective of the VA is to identify and rank-order DOE-ES&H vulnerabilities associated for the purpose of decision making on the interim safe management and ultimate disposition of fissile materials. This assessment is directed at plutonium and other co-located transuranics in various forms.

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

Institute for Environment, Health and Safety

International Nuclear Information System (INIS)

Loos, M.

2007-01-01

The article describes the key activities of the Institute for Environment, Health and Safety of the Belgian Nuclear Research Centre SCK-CEN. Through the performance of experiments, the development of models and the integration of human sciences in our R and D, propose new durable methods, computer codes and measuring instruments for radiation protection, management and disposal of radioactive waste and dismantling of nuclear installations. These developments belong to the disciplines environmental chemistry, radiobiology and radioecology and include the transfer of radio nuclides in the geosphere and biosphere, as also the behaviour of micro-organisms in space

Introduction to good practice in health, environment and safety management in enterprises

NARCIS (Netherlands)

Baranski, B.; Zwetsloot, G.

2000-01-01

Purpose of this paper, presented on the fifth annual meeting of the Baltic Sea Network on Occupational Health and Safety (Berlin, 18-19 November 1999), is to outline conceptual models of good practice (GP) in Health, Environment and Safety Management in Enterprises (HESME), present major components

Management of health, safety and environment in process industry

DEFF Research Database (Denmark)

Duijm, Nijs Jan; Fiévez, C.; Gerbec, M.

2008-01-01

The present status of industrial HSE management in a number of EU member states is reviewed, with a focus on the integration of health, safety and environment in single management systems. The review provides insight into the standards and paradigms adopted by industry, and it identifies trends...

Information report of AREVA Malvesi site - 2015 Edition. This report is written in compliance with article L. 125-15 of the French environment code

International Nuclear Information System (INIS)

2016-01-01

Published in compliance with the French code of the environment, this report presents, first, the AREVA Malvesi site with its facilities and activities in the domain of uranium conversion. Then, it takes stock of the dispositions implemented for the limitation and prevention of risks and summarizes the events declared in 2015. Next, it presents the management of the site effluents and wastes and the environmental monitoring. Finally, the actions of public information are presented. The recommendations of the Health and safety Committee are included in appendix

Information report of AREVA Melox site - 2015 Edition. This report is written in compliance with article L. 125-15 of the French environment code

International Nuclear Information System (INIS)

2016-01-01

Published in compliance with the French code of the environment, this report presents, first, the AREVA Melox site with its facilities and activities in the domain of MOX fuel fabrication. Then, it takes stock of the dispositions implemented for the limitation and prevention of risks and summarizes the events declared in 2015. Next, it presents the management of the site effluents and wastes and the environmental monitoring. Finally, the actions of public information are presented. The recommendations of the Health and safety Committee are included in appendix

Information report of AREVA Romans site - 2015 Edition. This report is written in compliance with article L. 125-15 of the French environment code

International Nuclear Information System (INIS)

2016-01-01

Published in compliance with the French code of the environment, this report presents, first, the AREVA Romans site with its facilities and activities in the domain of fuel assembly fabrication. Then, it takes stock of the dispositions implemented for the limitation and prevention of risks and summarizes the events declared in 2015. Next, it presents the management of the site effluents and wastes and the environmental monitoring. Finally, the actions of public information are presented. The recommendations of the Health and safety Committee are included in appendix

NGNP Site Selection Status Report

International Nuclear Information System (INIS)

Holbrook, Mark

2006-01-01

This report provides an overview of the Nuclear Regulatory Commission (NRC) licensing process, the preliminary site activities that have taken place in the current fiscal year (FY-06), and the site-related plans for FY-07. The NRC maintains oversight of the construction and operation of a facility throughout its lifetime to assure compliance with the Commission's regulations for the protection of public health and safety, the common defense and security, and the environment. To implement this process, all nuclear power plant applications must undergo a safety review, an environmental review, and antitrust review by the NRC.

Siting of near surface disposal facilities

International Nuclear Information System (INIS)

1994-01-01

Radioactive waste is generated from the production of nuclear energy and from the use of radioactive materials in industrial applications, research and medicine. The importance of safe management of radioactive waste for the protection of human health and the environment has long been recognized and considerable experience has been gained in this field. The Radioactive Waste Safety Standards (RADWASS) programme is the IAEA's contribution to establishing and promoting, in a coherent and comprehensive manner, the basic safety philosophy for radioactive waste management and the steps necessary to ensure its implementation. The Safety Standards are supplemented by a number of Safety Guides and Safety Practices. This Safety Guide defines the site selection process and criteria for identifying suitable near surface disposal facilities for low and intermediate level solid wastes. Management of the siting process and data needed to apply the criteria are also specified. 4 refs

Final disposal of spent fuel in the Finnish bedrock. Scope and requirements for site-specific safety analysis

International Nuclear Information System (INIS)

1996-12-01

The report is a summary of the research conducted in the period 1993 to 1996 into safety of spent fuel final disposal. The principal goal of the research in this period, as set in 1993, was to develop a strategy for site-specific safety analysis. At the same time efforts were to be continued to gather data and validate the technical approach for the analysis. The work aimed at having the data needed for the analysis available at the end of year 1998. A safety assessment update, TILA-96, prepared by VTT Energy, is published as a separate report. The assessment is based on the TVO-92 safety analysis, but takes into account the knowledge acquired after 1992 on safety aspects of the disposal system and the data gathered from the site investigations made by TVO and from the beginning of 1996, by Posiva. Since the site investigations are still ongoing and much of the data gathered still pending interpretation, only limited amount of new site-specific information has been available for the present assessment. (172 refs.)

Program plan for evaluation of the Ferrocyanide Waste Tank safety issue at the Hanford Site

International Nuclear Information System (INIS)

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

1994-03-01

This document describes the background, priorities, strategy and logic, and task descriptions for the Ferrocyanide Waste Tank Safety Program. The Ferrocyanide Safety Program was established in 1990 to provide resolution of a major safety issue identified for 24 high-level radioactive waste tanks at the Hanford Site

Preparation of site emergency preparedness plans for nuclear installations

International Nuclear Information System (INIS)

1999-10-01

Safety of public, occupational workers and the protection of environment should be assured while activities for economic and social progress are pursued. These activities include the establishment and utilisation of nuclear facilities and use of radioactive sources. This safety guidelines is issued as a lead document to facilitate preparation of specific site manuals by the responsible organisation for emergency response plans at each site to ensure their preparedness to meet any eventuality due to site emergency in order to mitigate its consequences on the health and safety of site personnel. It takes cognizance of an earlier AERB publications on the subject: Safety manual on site emergency plan on nuclear installations. AERB/SM/NISD-1, 1986 and also takes into consideration the urgent need for promoting public awareness and drawing up revised emergency response plans, which has come about in a significant manner after the accidents at Chernobyl and Bhopal

Development of Onsite Transportation Safety Documents for Nevada Test Site

International Nuclear Information System (INIS)

Frank Hand; Willard Thomas; Frank Sciacca; Manny Negrete; Susan Kelley

2008-01-01

Department of Energy (DOE) Orders require each DOE site to develop onsite transportation safety documents (OTSDs). The Nevada Test Site approach divided all onsite transfers into two groups with each group covered by a standalone OTSD identified as Non-Nuclear and Nuclear. The Non-Nuclear transfers involve all radioactive hazardous material in less than Hazard Category (HC)-3 quantities and all chemically hazardous materials. The Nuclear transfers involve all radioactive material equal to or greater than HC-3 quantities and radioactive material mated with high explosives regardless of quantity. Both OTSDs comply with DOE O 460.1B requirements. The Nuclear OTSD also complies with DOE O 461.1A requirements and includes a DOE-STD-3009 approach to hazard analysis (HA) and accident analysis as needed. All Nuclear OTSD proposed transfers were determined to be non-equivalent and a methodology was developed to determine if 'equivalent safety' to a fully compliant Department of Transportation (DOT) transfer was achieved. For each HA scenario, three hypothetical transfers were evaluated: a DOT-compliant, uncontrolled, and controlled transfer. Equivalent safety is demonstrated when the risk level for each controlled transfer is equal to or less than the corresponding DOT-compliant transfer risk level. In this comparison the typical DOE-STD-3009 risk matrix was modified to reflect transportation requirements. Design basis conditions (DBCs) were developed for each non-equivalent transfer. Initial DBCs were based solely upon the amount of material present. Route-, transfer-, and site-specific conditions were evaluated and the initial DBCs revised as needed. Final DBCs were evaluated for each transfer's packaging and its contents

The impact of nursing work environments on patient safety outcomes: the mediating role of burnout/engagement.

Science.gov (United States)

Spence Laschinger, Heather K; Leiter, Michael P

2006-05-01

To test a theoretical model of professional nurse work environments linking conditions for professional nursing practice to burnout and, subsequently, patient safety outcomes. The 2004 Institute of Medicine report raised serious concerns about the impact of hospital restructuring on nursing work environments and patient safety outcomes. Few studies have used a theoretical framework to study the nature of the relationships between nursing work environments and patient safety outcomes. Hospital-based nurses in Canada (N = 8,597) completed measures of worklife (Practice Environment Scale of the Nursing Work Index), burnout (Maslach Burnout Inventory-Human Service Scale), and their report of frequency of adverse patient events. Structural equation modeling analysis supported an extension of Leiter and Laschinger's Nursing Worklife Model. Nursing leadership played a fundamental role in the quality of worklife regarding policy involvement, staffing levels, support for a nursing model of care (vs medical), and nurse/physician relationships. Staffing adequacy directly affected emotional exhaustion, and use of a nursing model of care had a direct effect on nurses' personal accomplishment. Both directly affected patient safety outcomes. The results suggest that patient safety outcomes are related to the quality of the nursing practice work environment and nursing leadership's role in changing the work environment to decrease nurse burnout.

SAVANNAH RIVER SITE ENVIRONMENTAL REPORT FOR 2007

International Nuclear Information System (INIS)

Mamatey, A

2008-01-01

The Savannah River Site Environmental Report for 2007 (WSRC-STI-2008-00057) prepared for the US Department of Energy (DOE) according to requirements of DOE Order 231.1A, 'Environment, Safety and Health Reporting', and DOE Order 5400.5, 'Radiation Protection of the Public and Environment'. The report's purpose is to: (1) present summary environmental data that characterize site environmental management performance; (2) confirm compliance with environmental standards and requirements; (3) highlight significant programs and efforts; (4) assess the impact of SRS operations on the public and the environment

Savannah River Site Environmental Report for 2004

International Nuclear Information System (INIS)

Mamatey, Albert R.

2005-01-01

The Savannah River Site Environmental Report for 2004 (WSRC-TR-2005-00005) is prepared for the U.S. Department of Energy (DOE) according to requirements of DOE Order 231.1A, ''Environment, Safety and Health Reporting,'' and DOE Order 5400.5, ''Radiation Protection of the Public and Environment''. The report's purpose is to present summary environmental data that characterize site environmental management performance; confirm compliance with environmental standards and requirements; highlight significant programs and efforts; and assess the impact of SRS operations on the public and the environment

SAVANNAH RIVER SITE ENVIRONMENTAL REPORT FOR 2007

Energy Technology Data Exchange (ETDEWEB)

Mamatey, A

2008-08-27

The Savannah River Site Environmental Report for 2007 (WSRC-STI-2008-00057) prepared for the US Department of Energy (DOE) according to requirements of DOE Order 231.1A, 'Environment, Safety and Health Reporting', and DOE Order 5400.5, 'Radiation Protection of the Public and Environment'. The report's purpose is to: (1) present summary environmental data that characterize site environmental management performance; (2) confirm compliance with environmental standards and requirements; (3) highlight significant programs and efforts; (4) assess the impact of SRS operations on the public and the environment.

Occupational health and environment research 1984: Health, Safety, and environmental Division. Progress report

International Nuclear Information System (INIS)

Voelz, G.L.

1986-05-01

The primary responsibility of the Health, Safety, and Environment (HSE) Division is to provide comprehensive occupational health and safety programs, waste processing, and environment protection. Two supplied-air suits tested for their functional protection were considered to be unacceptable because of low fit factors. Respiratory protective equipment testing for the uS Air Force, Navy, and Army was performed during 1984. The laser aerosol spectrometer (LAS-X) has been shown to operate successfully for measuring and sizing aerosols used for quality assurance testing of high-efficiency particulate air filters used at DOE facilities. Radioanalyses for 239 Pu and 241 Am are presented for the complete skeletal parts of two persons. Air samples from work areas in a coal gasification plant in Yugoslavia show minimal concentration of organic vapors, amines, polynuclear aromatic hydrocarbons, and phenols. Aerosol characteristics of oil shale vapors and manmade vitreous fibers used in ongoing inhalation toxicology studies are presented. Epidemiologic studies of smoking patterns among Los Alamos employees reveal 24.3% smokers compared with the US rate of 32.5%. Environmental surveillance at Los Alamos during 1984 showed the highest estimated radiation dose to an individual at or outside the Laboratory boundary to be about 25% of the natural background radiation dose. Surveillance studies on water and sediment transport of radionuclides, depleted uranium, and silver are described. Bibliographic review of the rooting depth of native plants indicates that even many grass species will root to depths greater than the earth overburden depths to cover low-level radioactive waste sites

Safety in nuclear power plant siting. A code of practice

International Nuclear Information System (INIS)

1978-01-01

This publication is brought out within the framework of establishing Codes of Practice and Safety Guides for nuclear power plants: NUSS programme. The scope of the document encompasses site and site-plant interaction factors related to operational states and accident conditions. The purpose of the Code is to give criteria and procedures to be applied as appropriate to operational states and accident conditions, including those which could lead to emergency situations. This Code is mainly concerned with severe events of low probability which relate to the siting of nuclear power plants and have to be considered in designing a particular nuclear power plant. Annex: Examples of natural and man-made events relevant for design basis evaluation

Comparison of APR1400 safety between brake site and shin-Kori site Due to the difference in the climate conditions

International Nuclear Information System (INIS)

Yoon, Ho Joon; Lee, Jeong Ik; Lee, Jeong Ik

2012-01-01

Brake Nuclear Power Plant (BNPP) is now under the construction based on APR1400 designed by Korean Electric Power Corporation (KEPCO). APR1400 is a two loop pressurized water reactor, the nuclear steam supply system (NSSS) US designed for about put of 4,000 MWt, with a corresponding electrical output of approximately 1,390 MWe. The first APR1400 (SKN 3 and 4) constructed in Shin-Kori, Korea has been modified according to the surrounding environment of the United Arab Emirates. In this paper, authors would like to compare safety issues between B NPP and Skin due to the changes of surroundings, since the site characteristics are very different. For instance, the mean annual air temperature in the UAE is 28 .deg. C and the peak air temperature was recorded as 48.8 .deg. C. Sea temperatures are varying from 17. deg. C in January to 35. deg. C in August, while that of Korea is in 9-16. deg. C range. Hot climate of UAE and the malfunction of HVAC system can lead the increasing of the water temperature in safety injection system (SIS). The heated water in SIS may affect the safety margin of the peak cladding temperature (PCT). The change of PCT and response time according to design basis accident scenarios such as large break LOCA are analyzed in detail. To evaluate such effect, Mars code was utilized to evaluate assumed condition by KAIST and the analyses of the results were carried out by Khalifa Univ.

Types of safety assessments of near surface repository for radioactive waste

International Nuclear Information System (INIS)

Mateeva, M.

2004-01-01

The purpose of this article is to presents the classification of different types safety assessments of near surface repository for low and intermediate level radioactive waste substantiated with results of safety assessments generated in Bulgaria. The different approach of safety assessments applied for old existing repository as well as for site selection for construction new repository is outlined. The regulatory requirements in Bulgaria define three main types of assessments: Safety assessment; Technical substation of repository safety; Assessment of repository influence on environment that is in form of report prepared from the Ministry of environment and waters on the base of results obtained in two first types of assessments. Additionally first type is subdivided in three categories - preliminary safety assessment, safety assessment and post closure safety assessment, which are generated using deterministic approach. The technical substation of repository safety is generated using probabilistic approach. Safety assessment results that are presented here are based on evaluation of existing old repository type 'Radon' in Novi Han and real site selection procedure for new near surface repository for low and intermediate level radioactive waste from nuclear power station in Kozloduy. The important role of safety assessment for improvement the repository safety as well as for repository licensing, correct site selection and right choice of engineer barriers and repository design is discussed using generated results. (author)

Workers’ Age and the Impact of Psychological Factors on the Perception of Safety at Construction Sites

Directory of Open Access Journals (Sweden)

Muhammad Dawood Idrees

2017-05-01

Full Text Available The safety of construction workers is always a major concern at construction sites as the construction industry is inherently dangerous with many factors influencing worker safety. Several studies concluded that psychological factors such as workload, organizational relationships, mental stress, job security, and job satisfaction have significant effects on workers’ safety. However, research on psychological factors that are characteristic of different age groups have been limited. The aim of this study was to examine the impact of psychological factors on the perception of worker safety for two different age groups. After an extensive literature review, different psychological factors were identified, and a hypothetical research model was developed based on psychological factors that could affect workers’ perception of safety. A survey instrument was developed, and data were collected from seven different construction sites in Pakistan. Structural equation modeling (SEM was employed to test the hypothetical model for both age groups. The results revealed that workload and job satisfaction are significantly dominant factors on workers’ perception of safety in older workers, whereas organizational relationships, mental stress, and job security are dominant factors for younger workers at construction sites.

2014 Site Environmental Report

Energy Technology Data Exchange (ETDEWEB)

Paquette, Douglas [Brookhaven National Lab. (BNL), Upton, NY (United States); Remien, Jason [Brookhaven National Lab. (BNL), Upton, NY (United States); Foley, Brian [Brookhaven National Lab. (BNL), Upton, NY (United States); Burke, John [Brookhaven National Lab. (BNL), Upton, NY (United States); Dorsch, William [Brookhaven National Lab. (BNL), Upton, NY (United States); Ratel, Karen [Brookhaven National Lab. (BNL), Upton, NY (United States); Howe, Robert [Brookhaven National Lab. (BNL), Upton, NY (United States); Welty, Tim [Brookhaven National Lab. (BNL), Upton, NY (United States); Williams, Jeffrey [Brookhaven National Lab. (BNL), Upton, NY (United States); Pohlpt, Peter [Brookhaven National Lab. (BNL), Upton, NY (United States); Lagattolla, Richard [Brookhaven National Lab. (BNL), Upton, NY (United States); Metz, Robert [Brookhaven National Lab. (BNL), Upton, NY (United States); Milligan, James [Brookhaven National Lab. (BNL), Upton, NY (United States); Lettieri, Lawrence [Brookhaven National Lab. (BNL), Upton, NY (United States)

2015-10-01

BNL prepares an annual Site Environmental Report (SER) in accordance with DOE Order 231.1B, Environment, Safety and Health Reporting. The report is written to inform the public, regulators, employees, and other stakeholders of the Laboratory’s environmental performance during the calendar year in review.

The work environment and empowerment as predictors of patient safety culture in Turkey.

Science.gov (United States)

Dirik, Hasan Fehmi; Intepeler, Seyda Seren

2017-05-01

As scant research based information is available regarding the work environment, empowerment and patient safety culture, this study from a developing country (Turkey) in which health care institutions are in a state of transition, aimed to investigate further the relationships between these three variables. A cross-sectional descriptive design was employed. The sample comprised 274 nurse participants working in a university hospital located in Izmir (Turkey). In data evaluation, descriptive statistics and hierarchical regression analyses were applied. The work environment and structural empowerment were related to the patient safety culture and explained 55% of the variance in patient safety culture perceptions. 'Support for optimal patient care', 'nurse/physician relationships' and 'staff involvement in organisational affairs' were the significant predictors. An enhancement of the work environment and providing access to empowerment structures may help health care organisations improve the patient safety culture. In light of the findings, the following actions can be recommended to inform health care leaders: providing necessary resources for nursing practise, encouraging nurses' participation in decision-making, strengthening communication within the team and giving nurses the opportunities to cope with challenging work problems to learn and grow. © 2017 John Wiley & Sons Ltd.

Association of Safety Culture with Surgical Site Infection Outcomes.

Science.gov (United States)

Fan, Caleb J; Pawlik, Timothy M; Daniels, Tania; Vernon, Nora; Banks, Katie; Westby, Peggy; Wick, Elizabeth C; Sexton, J Bryan; Makary, Martin A

2016-02-01

Hospital workplace culture may have an impact on surgical outcomes; however, this association has not been established. We designed a study to evaluate the association between safety culture and surgical site infection (SSI). Using the Hospital Survey on Patient Safety Culture and National Healthcare Safety Network definitions, we measured 12 dimensions of safety culture and colon SSI rates, respectively, in the surgical units of Minnesota community hospitals. A Pearson's r correlation was calculated for each of 12 dimensions of surgical unit safety culture and SSI rate and then adjusted for surgical volume and American Society of Anesthesiologists (ASA) classification. Seven hospitals participated in the study, with a mean survey response rate of 43%. The SSI rates ranged from 0% to 30%, and surgical unit safety culture scores ranged from 16 to 92 on a scale of 0 to 100. Ten dimensions of surgical unit safety culture were associated with colon SSI rates: teamwork across units (r = -0.96; 95% CI [-0.76, -0.99]), organizational learning (r = -0.95; 95% CI [-0.71, -0.99]), feedback and communication about error (r = -0.92; 95% CI [-0.56, -0.99]), overall perceptions of safety (r = -0.90; 95% CI [-0.45, -0.99]), management support for patient safety (r = -0.90; 95% CI [-0.44, -0.98]), teamwork within units (r = -0.88; 95% CI [-0.38, -0.98]), communication openness (r = -0.85; 95% CI [-0.26, -0.98]), supervisor/manager expectations and actions promoting safety (r = -0.85; 95% CI [-0.25, -0.98]), non-punitive response to error (r = -0.78; 95% CI [-0.07, -0.97]), and frequency of events reported (r = -0.76; 95% CI [-0.01, -0.96]). After adjusting for surgical volume and ASA classification, 9 of 12 dimensions of surgical unit safety culture were significantly associated with lower colon SSI rates. These data suggest an important role for positive safety and teamwork culture and engaged hospital management in producing high-quality surgical

Pacific Northwest Laboratory annual report for 1989 to the Assistant Secretary for Environment, Safety, and Health - Part 5: Environment, Safety, Health, and Quality Assurance

Energy Technology Data Exchange (ETDEWEB)

Faust, L.G.; Doctor, P.G.; Selby, J.M.

1990-04-01

Part 5 of the 1989 Annual Report to the US Department of Energy's Assistant Secretary for Environment, Safety, and Health presents Pacific Northwest Laboratory's progress on work performed for the Office of Environmental Guidance and Compliance, the Office of Environmental Audit, the Office of National Environmental Policy Act Project Assistance, the Office of Nuclear Safety, the Office of Safety Compliance, and the Office of Policy and Standards. For each project, as identified by the Field Work Proposal, there is an article describing progress made during fiscal year 1989. Authors of these articles represent a broad spectrum of capabilities derived from five of the seven technical centers of the Laboratory, reflecting the interdisciplinary nature of the work. 35 refs., 1 fig.

Assessment of the living and workplace health and safety conditions of site-resident construction workers in Tehran, Iran.

Science.gov (United States)

Mohseni, Peyman Hossein; Farshad, Ali Asghar; Mirkazemi, Roksana; Orak, Rouhangiz Jamshidi

2015-01-01

The purpose of this study was to assess living and workplace safety conditions of construction workers in Tehran, Iran. This cross-sectional study was conducted among 410 construction sites in a municipal area of Tehran whose municipal building permits were issued in 2011. Data on ventilation, workplace safety and hygiene were collected by direct observation and interviews with site foremen. Noise levels were estimated from 10 sound-level-meter stations in the municipality area. Lack of ventilation in the workers' rooms was abundant. Bathrooms were unhygienic and minimum requirements such as lighting and ventilation did not exist in 80% of the cases. In nearly 50% of large construction sites, sewage and garbage disposal were inappropriate. Elevator safety was poor at all sites and no measures for fall prevention were present in over 88% of active construction sites. This study showed that the mean 24-h equivalent continuous sound level Leq was over 70 dB in 80% of the sites during weekdays. The results of this study revealed poor health and safety living and working conditions of construction workers in Tehran.

A comparison between the IAEA Safety Series 6 thermal environment and a proposed alternative thermal environment

International Nuclear Information System (INIS)

Wix, S.D.; Koski, J.A.

1994-01-01

The present regulations for packaging and transportation of radioactive materials, IAEA Safety Series No. 6; 1985, establish specific criteria for the thermal environment of a hypothetical accident. The regulation states: The scope of this paper is to examine the effects on modeling that result with the Fry proposed thermal boundary conditions. The examination is accomplished by comparing thermal model results using the current IAEA specified thermal environment and the Fry proposed thermal boundary conditions

Improving the safety of remote site emergency airway management.

Science.gov (United States)

Wijesuriya, Julian; Brand, Jonathan

2014-01-01

Airway management, particularly in non-theatre settings, is an area of anaesthesia and critical care associated with significant risk of morbidity & mortality, as highlighted during the 4th National Audit Project of the Royal College of Anaesthetists (NAP4). A survey of junior anaesthetists at our hospital highlighted a lack of confidence and perceived lack of safety in emergency airway management, especially in non-theatre settings. We developed and implemented a multifaceted airway package designed to improve the safety of remote site airway management. A Rapid Sequence Induction (RSI) checklist was developed; this was combined with new advanced airway equipment and drugs bags. Additionally, new carbon dioxide detector filters were procured in order to comply with NAP4 monitoring recommendations. The RSI checklists were placed in key locations throughout the hospital and the drugs and advanced airway equipment bags were centralised in the Intensive Care Unit (ICU). It was agreed with the senior nursing staff that an appropriately trained ICU nurse would attend all emergency situations with new airway resources upon request. Departmental guidelines were updated to include details of the new resources and the on-call anaesthetist's responsibilities regarding checks and maintenance. Following our intervention trainees reported higher confidence levels regarding remote site emergency airway management. Nine trusts within the Northern Region were surveyed and we found large variations in the provision of remote site airway management resources. Complications in remote site airway management due lack of available appropriate drugs, equipment or trained staff are potentially life threatening and completely avoidable. Utilising the intervention package an anaesthetist would be able to safely plan and prepare for airway management in any setting. They would subsequently have the drugs, equipment, and trained assistance required to manage any difficulties or complications

Cold Vacuum Drying Safety Class Instrumentation and Control System Design Description

International Nuclear Information System (INIS)

WHITEHURST, R.

1999-01-01

This document describes the Cold Vacuum Drying Facility (CVDF) Safety Class Instrumentation and Control system (SCIC). The SCIC provides safety functions and features to protect the environment, off-site and on-site personnel and equipment. The function of the SCIC is to provide automatic trip features, valve interlocks, alarms, indication and control for the cold vacuum drying process

Occupational health and safety issues in the informal economic segment of Pakistan: a survey of construction sites.

Science.gov (United States)

Ahmed, Ishfaq; Shaukat, Muhammad Zeeshan; Usman, Ahmad; Nawaz, Muhammad Musarrat; Nazir, Mian Sajid

2018-06-01

This research covers the current status of occupational health and safety (OHS)-related practices in the informal construction segment of Pakistan. Data were collected, through interviews, from 316 construction sites employing 3577 workers. The results of the study reveal that both employers and workers lack knowledge of OHS laws/standards and no practices of this nature are enacted at these construction sites. Alarmingly, work-related accidents, whenever they happen, are not given due attention and there is no formal injury-report system. The informal construction industry employs a huge portion of the informal workforce, and lack of OHS happens at tremendous human cost. These research findings may thus play their role in strengthening the case for reforms in the sector. This study, if properly utilized, may also enable employers of the sector by increasing their knowledge about OHS practices and, as a result, trying to offer safer environments for their workers.

Environment, safety and health progress assessment manual

International Nuclear Information System (INIS)

1992-12-01

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

General siting study 95. Siting of a deep repository for spent nuclear fuel

International Nuclear Information System (INIS)

1995-10-01

General Siting Study 95 is a detailed description of the work carried out to put the siting of a deep repository in a national and regional context. The report is based on SKB's siting factors, which have been applied on a national scale. Different factors of importance or of possible importance for the long-term radiological safety, technology, land and environment as well as society are described and evaluated. This report is the overall description on general siting studies which the government considered that SKB should report in connection with the RD and D Programme 95. 121 refs, 40 figs

General siting study 95. Siting of a deep repository for spent nuclear fuel

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-10-01

General Siting Study 95 is a detailed description of the work carried out to put the siting of a deep repository in a national and regional context. The report is based on SKB`s siting factors, which have been applied on a national scale. Different factors of importance or of possible importance for the long-term radiological safety, technology, land and environment as well as society are described and evaluated. This report is the overall description on general siting studies which the government considered that SKB should report in connection with the RD and D Programme 95. 121 refs, 40 figs.

Use of a web site to enhance criticality safety training

International Nuclear Information System (INIS)

Huang, Song T.; Morman, James A.

2003-01-01

Establishment of the NCSP (Nuclear Criticality Safety Program) website represents one attempt by the NCS (Nuclear Criticality Safety) community to meet the need to enhance communication and disseminate NCS information to a wider audience. With the aging work force in this important technical field, there is a common recognition of the need to capture the corporate knowledge of these people and provide an easily accessible, web-based training opportunity to those people just entering the field of criticality safety. A multimedia-based site can provide a wide range of possibilities for criticality safety training. Training modules could range from simple text-based material, similar to the NCSET (Nuclear Criticality Safety Engineer Training) modules, to interactive web-based training classes, to video lecture series. For example, the Los Alamos National Laboratory video series of interviews with pioneers of criticality safety could easily be incorporated into training modules. Obviously, the development of such a program depends largely upon the need and participation of experts who share the same vision and enthusiasm of training the next generation of criticality safety engineers. The NCSP website is just one example of the potential benefits that web-based training can offer. You are encouraged to browse the NCSP website at http://ncsp.llnl.gov. We solicit your ideas in the training of future NCS engineers and welcome your participation with us in developing future multimedia training modules. (author)

WIPP 2004 Site Environmental Report

Energy Technology Data Exchange (ETDEWEB)

None, None

2005-09-30

The mission of Waste Isolation Pilot Plant (WIPP) is to safely and permanently dispose of transuranic (TRU) radioactive waste generated by the production of nuclear weapons and other activities related to the national defense of the United States (U.S.). In 2004, 8,839 cubic meters (m3) of TRU waste were emplaced at WIPP. From the first receipt of waste in March 1999 through the end of 2004, 25,809 m3 of TRU waste had been emplaced at WIPP. The U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) and Washington TRU Solutions LLC (WTS) are dedicated to maintaining high quality management of WIPP environmental resources. DOE Order 450.1, Environmental Protection Program; DOE Order 231.1A, Environment, Safety, and Health Reporting; and DOE Order 5400.5, Radiation Protection of the Public and Environment, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2004 Site Environmental Report (SER) summarizes environmental data from 2004 that characterize environmental management performance and demonstrate compliance with applicable federal and state regulations. This report was prepared in accordance with DOE Order 231.1A, and Guidance for the Preparation of DOE Annual Site Environmental Reports (ASERs) for Calendar Year 2004 (DOE, 2005). The order and the guidance require that DOE facilities submit an annual SER to the DOE Headquarters Office of the Assistant Secretary for Environment, Safety, and Health. The WIPP Hazardous Waste Facility Permit (HWFP) further requires that the SER be provided to the New Mexico Environment Department (NMED).

WIPP 2004 Site Environmental Report

International Nuclear Information System (INIS)

2005-01-01

The mission of Waste Isolation Pilot Plant (WIPP) is to safely and permanently dispose of transuranic (TRU) radioactive waste generated by the production of nuclear weapons and other activities related to the national defense of the United States (U.S.). In 2004, 8,839 cubic meters (m3) of TRU waste were emplaced at WIPP. From the first receipt of waste in March 1999 through the end of 2004, 25,809 m3 of TRU waste had been emplaced at WIPP. The U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) and Washington TRU Solutions LLC (WTS) are dedicated to maintaining high quality management of WIPP environmental resources. DOE Order 450.1, Environmental Protection Program; DOE Order 231.1A, Environment, Safety, and Health Reporting; and DOE Order 5400.5, Radiation Protection of the Public and Environment, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2004 Site Environmental Report (SER) summarizes environmental data from 2004 that characterize environmental management performance and demonstrate compliance with applicable federal and state regulations. This report was prepared in accordance with DOE Order 231.1A, and Guidance for the Preparation of DOE Annual Site Environmental Reports (ASERs) for Calendar Year 2004 (DOE, 2005). The order and the guidance require that DOE facilities submit an annual SER to the DOE Headquarters Office of the Assistant Secretary for Environment, Safety, and Health. The WIPP Hazardous Waste Facility Permit (HWFP) further requires that the SER be provided to the New Mexico Environment Department (NMED).

Safety assessment document for the environmental test complex (Building 834) at Site 300

International Nuclear Information System (INIS)

Odell, B.N.; Pfeifer, H.E.

1981-01-01

A safety assessment was performed to determine if accidents occurring at the 834 Complex at Site 300 could present undue hazards to the general public, personnel at Site 300, or have an adverse effect on the environment. The credible accidents that might have an effect on these facilities or have off-site consequences were considered. These were earthquake, extreme wind (including missiles), lightning, flood, criticality, high explosive (HE) detonation that disperses uranium and beryllium, spontaneous oxidation of plutonium, explosions due to finely divided particles, and a fire. Seismic and extreme wind (including missiles) analyses indicate that the buildings are basically sound. (However, there are a few recommendations to further enhance the structural integrity of these facilities). Additional lightning protection for these facilities is being installed. These buildings are located high above the dry creek bed so that a flood is improbable. A criticality or a high explosive detonation involving plutonium is very remote since the radioactive materials are encased and plutonium and HE are not permitted concurrently in the same area at Site 300. (The exceptions to this policy are that explosive actuating devices are sometimes located in assemblies containing fissile materials. However, a planned or accidental actuation will not effect the safe containment of the fissile material within the assembly). Even though the possibility of an HE explosion involving uranium and beryllium is remote, the off-site lung doses were calculated and found to be below the accepted standards. It was determined that a fire was unlikely due to the low fire loading and the absence of ignition sources. It was also determined that the consequences of any accidents were reduced by the remote location of these facilities, their design, and by administrative controls

AEA Technology report on safety and the environment 1991/92

International Nuclear Information System (INIS)

1992-01-01

Safety management has been a key activity for AEA throughout our history. This will continue to be the case as our commercial strategy is developed to meet the needs of our customers. The provision of high quality service is central to AEA's objectives - and safety is an important part of our quality management system. This report describes AEA's safety arrangements and performance over the last year. The considerable resources which we have devoted to radiological protection - and increasingly to general industrial safety matters - show that we have a good record in managing the safety of our employees and of the public. We set objectives and targets consistent with our aim to have a demonstrably high level of safety performance. This report also highlights our commitment to protection of the environment. The careful attention which we have paid for many years to limiting the environmental effects of our radiological operations has been broadened to a more generally based environmental protection policy. AEA is pleased to be associated - both in regard to our own operations and as a supplier of consultancy services in environmental protection - with the increasing efforts made in this area by the business world. (UK)

Cesium in the Savannah River Site environment

International Nuclear Information System (INIS)

Carlton, W.H.; Bauer, L.R.; Evans, A.G.; Geary, L.A.; Murphy, C.E. Jr.; Pinder, J.E.; Strom, R.N.

1992-03-01

Cesium in the Savannah River Site Environment is published as a part of the Radiological Assessment Program (RAP). It is the fourth in a series of eight documents on individual radioisotopes released to the environment as a result of Savannah River Site (SRS) operations. The earlier documents describe the environmental consequences of tritium, iodine, and uranium. Documents on plutonium, strontium, carbon, and technetium will be published in the future. These are dynamic documents and current plans call for revising and updating each one on a two-year schedule.Radiocesium exists in the environment as a result of above-ground nuclear weapons tests, the Chernobyl accident, the destruction of satellite Cosmos 954, small releases from reactors and reprocessing plants, and the operation of industrial, medical, and educational facilities. Radiocesium has been produced at SRS during the operation of five production reactors. Several hundred curies of 137 Cs was released into streams in the late 50s and 60s from leaking fuel elements. Smaller quantities were released from the fuel reprocessing operations. About 1400 Ci of 137 Cs was released to seepage basins where it was tightly bound by clay in the soil. A much smaller quantity, about four Ci. was released to the atmosphere. Radiocesium concentration and mechanisms for atmospheric, surface water, and groundwater have been extensively studied by Savannah River Technology Center (SRTC) and ecological mechanisms have been studied by Savannah River Ecology Laboratory (SREL). The overall radiological impact of SRS releases on the offsite maximum individual can be characterized by total doses of 033 mrem (atmospheric) and 60 mrem (liquid), compared with a dose of 12,960 mrem from non-SRS sources during the same period of time. Isotope 137 Cs releases have resulted in a negligible risk to the environment and the population it supports

Cesium in the Savannah River Site environment

Energy Technology Data Exchange (ETDEWEB)

Carlton, W.H.; Bauer, L.R.; Evans, A.G.; Geary, L.A.; Murphy, C.E. Jr.; Pinder, J.E.; Strom, R.N.

1992-03-01

Cesium in the Savannah River Site Environment is published as a part of the Radiological Assessment Program (RAP). It is the fourth in a series of eight documents on individual radioisotopes released to the environment as a result of Savannah River Site (SRS) operations. The earlier documents describe the environmental consequences of tritium, iodine, and uranium. Documents on plutonium, strontium, carbon, and technetium will be published in the future. These are dynamic documents and current plans call for revising and updating each one on a two-year schedule.Radiocesium exists in the environment as a result of above-ground nuclear weapons tests, the Chernobyl accident, the destruction of satellite Cosmos 954, small releases from reactors and reprocessing plants, and the operation of industrial, medical, and educational facilities. Radiocesium has been produced at SRS during the operation of five production reactors. Several hundred curies of [sup 137]Cs was released into streams in the late 50s and 60s from leaking fuel elements. Smaller quantities were released from the fuel reprocessing operations. About 1400 Ci of [sup 137]Cs was released to seepage basins where it was tightly bound by clay in the soil. A much smaller quantity, about four Ci. was released to the atmosphere. Radiocesium concentration and mechanisms for atmospheric, surface water, and groundwater have been extensively studied by Savannah River Technology Center (SRTC) and ecological mechanisms have been studied by Savannah River Ecology Laboratory (SREL). The overall radiological impact of SRS releases on the offsite maximum individual can be characterized by total doses of 033 mrem (atmospheric) and 60 mrem (liquid), compared with a dose of 12,960 mrem from non-SRS sources during the same period of time. Isotope [sup 137]Cs releases have resulted in a negligible risk to the environment and the population it supports.

Cesium in the Savannah River Site environment

Energy Technology Data Exchange (ETDEWEB)

Carlton, W.H.; Bauer, L.R.; Evans, A.G.; Geary, L.A.; Murphy, C.E. Jr.; Pinder, J.E.; Strom, R.N.

1992-03-01

Cesium in the Savannah River Site Environment is published as a part of the Radiological Assessment Program (RAP). It is the fourth in a series of eight documents on individual radioisotopes released to the environment as a result of Savannah River Site (SRS) operations. The earlier documents describe the environmental consequences of tritium, iodine, and uranium. Documents on plutonium, strontium, carbon, and technetium will be published in the future. These are dynamic documents and current plans call for revising and updating each one on a two-year schedule.Radiocesium exists in the environment as a result of above-ground nuclear weapons tests, the Chernobyl accident, the destruction of satellite Cosmos 954, small releases from reactors and reprocessing plants, and the operation of industrial, medical, and educational facilities. Radiocesium has been produced at SRS during the operation of five production reactors. Several hundred curies of {sup 137}Cs was released into streams in the late 50s and 60s from leaking fuel elements. Smaller quantities were released from the fuel reprocessing operations. About 1400 Ci of {sup 137}Cs was released to seepage basins where it was tightly bound by clay in the soil. A much smaller quantity, about four Ci. was released to the atmosphere. Radiocesium concentration and mechanisms for atmospheric, surface water, and groundwater have been extensively studied by Savannah River Technology Center (SRTC) and ecological mechanisms have been studied by Savannah River Ecology Laboratory (SREL). The overall radiological impact of SRS releases on the offsite maximum individual can be characterized by total doses of 033 mrem (atmospheric) and 60 mrem (liquid), compared with a dose of 12,960 mrem from non-SRS sources during the same period of time. Isotope {sup 137}Cs releases have resulted in a negligible risk to the environment and the population it supports.

Savannah River Site Environmental Report for 2004

Energy Technology Data Exchange (ETDEWEB)

Mamatey, Albert R.

2005-06-07

The Savannah River Site Environmental Report for 2004 (WSRC-TR-2005-00005) is prepared for the U.S. Department of Energy (DOE) according to requirements of DOE Order 231.1A, ''Environment, Safety and Health Reporting,'' and DOE Order 5400.5, ''Radiation Protection of the Public and Environment''. The report's purpose is to present summary environmental data that characterize site environmental management performance; confirm compliance with environmental standards and requirements; highlight significant programs and efforts; and assess the impact of SRS operations on the public and the environment.

SAVANNAH RIVER SITE ENVIRONMENTAL REPORT FOR 2005

Energy Technology Data Exchange (ETDEWEB)

Mamatey, A

2006-07-18

The ''Savannah River Site Environmental Report for 2005'' (WSRC-TR-2006-00007) is prepared for the U.S. Department of Energy (DOE) according to requirements of DOE Order 231.1A, ''Environment, Safety and Health Reporting'', and DOE Order 5400.5, ''Radiation Protection of the Public and Environment''. The report's purpose is to: present summary environmental data that characterize site environmental management performance; confirm compliance with environmental standards and requirements; highlight significant programs and efforts; and assess the impact of SRS operations on the public and the environment.

Pacific Northwest Laboratory annual report for 1987 to the Assistant Secretary for Environment, Safety, and Health: Part 5: Environment, safety, health, and quality assurance

International Nuclear Information System (INIS)

Faust, L.G.; Steelman, B.L.; Selby, J.M.

1988-02-01

Part 5 of the 1987 Annual Report to the US Department of Energy's Assistant Secretary for Environment, Safety, and Health presents Pacific Northwest Laboratory's progress on work performed for the Office of Nuclear Safety, the Office of Environmental Guidance and Compliance, the Office of Environmental Audit, and the Office of National Environmental Policy Act Project Assistance. For each project, as identified by the Field Work Proposal, articles describe progress made during fiscal year 1987. Authors of these articles represent a broad spectrum of capabilities derived from five of the seven technical centers of the Laboratory, reflecting the interdisciplinary nature of the work

Safety and Environment aspects of Tokamak- type Fusion Power Reactor- An Overview

Science.gov (United States)

Doshi, Bharat; Reddy, D. Chenna

2017-04-01

Naturally occurring thermonuclear fusion reaction (of light atoms to form a heavier nucleus) in the sun and every star in the universe, releases incredible amounts of energy. Demonstrating the controlled and sustained reaction of deuterium-tritium plasma should enable the development of fusion as an energy source here on Earth. The promising fusion power reactors could be operated on the deuterium-tritium fuel cycle with fuel self-sufficiency. The potential impact of fusion power on the environment and the possible risks associated with operating large-scale fusion power plants is being studied by different countries. The results show that fusion can be a very safe and sustainable energy source. A fusion power plant possesses not only intrinsic advantages with respect to safety compared to other sources of energy, but also a negligible long term impact on the environment provided certain precautions are taken in its design. One of the important considerations is in the selection of low activation structural materials for reactor vessel. Selection of the materials for first wall and breeding blanket components is also important from safety issues. It is possible to fully benefit from the advantages of fusion energy if safety and environmental concerns are taken into account when considering the conceptual studies of a reactor design. The significant safety hazards are due to the tritium inventory and energetic neutron fluence induced activity in the reactor vessel, first wall components, blanket system etc. The potential of release of radioactivity under operational and accident conditions needs attention while designing the fusion reactor. Appropriate safety analysis for the quantification of the risk shall be done following different methods such as FFMEA (Functional Failure Modes and Effects Analysis) and HAZOP (Hazards and operability). Level of safety and safety classification such as nuclear safety and non-nuclear safety is very important for the FPR (Fusion

Monitoring human factor risk characteristics at nuclear legacy sites in northwest Russia in support of radiation safety regulation.

Science.gov (United States)

Scheblanov, V Y; Sneve, M K; Bobrov, A F

2012-12-01

This paper describes research aimed at improving regulatory supervision of radiation safety during work associated with the management of spent nuclear fuel and radioactive waste at legacy sites in northwest Russia through timely identification of employees presenting unfavourable human factor risk characteristics. The legacy sites of interest include sites of temporary storage now operated by SevRAO on behalf of Rosatom. The sites were previously operational bases for servicing nuclear powered submarines and are now subject to major remediation activities. These activities include hazardous operations for recovery of spent nuclear fuel and radioactive waste from sub-optimal storage conditions. The paper describes the results of analysis of methods, procedures, techniques and informational issues leading to the development of an expert-diagnostic information system for monitoring of workers involved in carrying out the most hazardous operations. The system serves as a tool for human factor and professional reliability risk monitoring and has been tested in practical working environments and implemented as part of regulatory supervision. The work has been carried out by the Burnasyan Federal Medical Biophysical Center, within the framework of the regulatory cooperation programme between the Federal Medical-Biological Agency of Russia and the Norwegian Radiation Protection Authority.

LLNL Site 200 Risk Management Plan

International Nuclear Information System (INIS)

Pinkston, D.; Johnson, M.

2008-01-01

detailed explanation of the worst case accident analyses for these processes. For the process involving regulated quantities of nitric acid, worst case accident analysis predicts a hazard zone well within areas under the jurisdiction of the Department of Energy. This analysis documents that the nearest public receptor is beyond the distance to a toxic or flammable endpoint. Refer to the LLNL Site 200 RMP Supporting Information document for a more detailed explanation of the worst case accident analysis for this process. LLNL maintains an active program to protect workers, the public, and the environment from harm resulting from its activities. Its policies and technical directions for controlling all hazards that are present as a result of its operations are described in the LLNL Environment, Health, and Safety Manual (referenced above)

Site Environmental Report for 1998

International Nuclear Information System (INIS)

Holland, R.C.

1999-01-01

Sandia National Laboratories (SNL) is committed to conducting its operations in an environmentally safe and sound manner. It is mandatory that activities at SNL/California comply with all applicable environmental statutes, regulations, and standards. Moreover, SNL/California continuously strives to reduce risks to employees, the public, and the environment to the lowest levels reasonably possible. To help verify effective protection of public safety and preservation of the environment, SNL/California maintains an extensive, ongoing environmental monitoring program. This program monitors all significant effluents and the environment at the SNL/California site perimeter. Lawrence Livermore National Laboratory (LLNL) performs off-site external radiation monitoring for both sites. These monitoring efforts ensure that emission controls are effective in preventing contamination of the environment. As part of SNL/California's Environmental Monitoring Program, an environmental surveillance system measures the possible presence of hazardous materials in groundwater, stormwater, and sewage. The program also includes an extensive environmental dosimetry program, which measures external radiation levels around the Livermore site and nearby vicinity. Each year, the results of the Environmental Monitoring Program are published in this report, the Site Environmental Report. This executive summary focuses on impacts to the environment. Chapter 3, ''Compliance Summary,'' reviews the site's various environmental protection activities and compliance status with applicable environmental regulations. The effluent monitoring and environmental surveillance results for 1998 show that SNL/California operations had no harmful effects on the environment or the public

Site Environmental Report for 1998

Energy Technology Data Exchange (ETDEWEB)

Holland, R.C.

1999-06-01

Sandia National Laboratories (SNL) is committed to conducting its operations in an environmentally safe and sound manner. It is mandatory that activities at SNL/California comply with all applicable environmental statutes, regulations, and standards. Moreover, SNL/California continuously strives to reduce risks to employees, the public, and the environment to the lowest levels reasonably possible. To help verify effective protection of public safety and preservation of the environment, SNL/California maintains an extensive, ongoing environmental monitoring program. This program monitors all significant effluents and the environment at the SNL/California site perimeter. Lawrence Livermore National Laboratory (LLNL) performs off-site external radiation monitoring for both sites. These monitoring efforts ensure that emission controls are effective in preventing contamination of the environment. As part of SNL/California's Environmental Monitoring Program, an environmental surveillance system measures the possible presence of hazardous materials in groundwater, stormwater, and sewage. The program also includes an extensive environmental dosimetry program, which measures external radiation levels around the Livermore site and nearby vicinity. Each year, the results of the Environmental Monitoring Program are published in this report, the Site Environmental Report. This executive summary focuses on impacts to the environment. Chapter 3, ''Compliance Summary,'' reviews the site's various environmental protection activities and compliance status with applicable environmental regulations. The effluent monitoring and environmental surveillance results for 1998 show that SNL/California operations had no harmful effects on the environment or the public.

Cadmium control/safety rod disposal at the Savannah River Site

International Nuclear Information System (INIS)

McInnis, S.H.

1995-01-01

Four heavy-water-moderated reactors at the Savannah River Site will undergo the removal of 862 activated cadmium control/safety rods. Although these reactors are 40 years old, they offer 4 basic advantages for decommissioning: the equipment is still in some sort of operable state; the reactor is blow the floor in a large process room, allowing access; Control/safety rods can be handled remotely by existing equipment; a radiologically shielded removal path exists. Drawbacks include the following: age of reactors; improvements in technology have caused incompatibility problems; more strigent standards; compliance with environmental regulations. This article details how the removal was carried out and the current status of the project, keeping in mind the above considerations

Biosphere analyses for the safety assessment SR-Site - synthesis and summary of results

International Nuclear Information System (INIS)

Saetre, Peter

2010-12-01

This report summarises nearly 20 biosphere reports and gives a synthesis of the work performed within the SR-Site Biosphere project, i.e. the biosphere part of SR-Site. SR-Site Biosphere provides the main project with dose conversion factors (LDFs), given a unit release rate, for calculation of human doses under different release scenarios, and assesses if a potential release from the repository would have detrimental effects on the environment. The intention of this report is to give sufficient details for an overview of methods, results and major conclusions, with references to the biosphere reports where methods, data and results are presented and discussed in detail. The philosophy of the biosphere assessment was to make estimations of the radiological risk for humans and the environment as realistic as possible, based on the knowledge of present-day conditions at Forsmark and the past and expected future development of the site. This was achieved by using the best available knowledge, understanding and data from extensive site investigations from two sites. When sufficient information was not available, uncertainties were handled cautiously. A systematic identification and evaluation of features and processes that affect transport and accumulation of radionuclides at the site was conducted, and the results were summarised in an interaction matrix. Data and understanding from the site investigation was an integral part of this work, the interaction matrix underpinned the development of the radionuclide model used in the biosphere assessment. Understanding of the marine, lake and river and terrestrial ecosystems at the site was summarized in a conceptual model, and relevant features and process have been characterized to capture site specific parameter values. Detailed investigations of the structure and history of the regolith at the site and simulations of regolith dynamics were used to describe the present day state at Forsmark and the expected development of

Information report of AREVA Tricastin site - 2015 Edition. This report is written in compliance with article L. 125-15 of the French environment code

International Nuclear Information System (INIS)

2016-01-01

Published in compliance with the French code of the environment, this report presents, first, the AREVA Tricastin site with its facilities (AREVA NC, EURODIF Production, SET, SOCATRI and AREVA NP Pierrelatte) and activities in the domain of uranium conversion and enrichment. Then, it takes stock of the dispositions implemented for the limitation and prevention of risks and summarizes the events declared in 2015. Next, it presents the management of the site effluents and wastes and the environmental monitoring. Finally, the actions of public information are presented. The recommendations of the Health and safety Committee are included in appendix

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

International Nuclear Information System (INIS)

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

1995-05-01

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

Assessment of site-scale hydrogeological modelling possibilities in crystalline hard rock for safety appraisal

Energy Technology Data Exchange (ETDEWEB)

Geier, J. [Cleanwater Hardrock Consulting, Corvallis, OR (United States); Luukkonen, A.

2012-09-15

This review describes the state-of-the-art in hydrogeological modelling for safety-case studies related to spent-fuel repositories in crystalline hard rock, focusing on issues of relevance for the KBS-3 disposal concept in Nordic environments. The review includes a survey of model capabilities and assumptions regarding groundwater flow processes, geological and excavation-related features, and boundary conditions for temperate, periglacial, and glacial climates. Modelling approaches are compared for research sites including the Stripa mine (Sweden), the Grimsel Test Site (Switzerland), the Whiteshell Underground Research Laboratory (Canada), the Aspo Hard Rock Laboratory and Simpevarp-Laxemar site (Sweden), the Forsmark site (Sweden), the Waste Isolation Pilot Plant site (USA), and Olkiluoto (Finland). Current hydrogeological models allow realistic representations, but are limited by availability of data to constrain their properties. Examples of calibrations of stochastic representations of heterogeneity are still scarce. Integrated models that couple flow and non-reactive transport are now well established, particularly those based on continuum representations. Models that include reactive transport are still mainly in the realm of research tools. Thus far, no single software tool allows fully coupled treatment of all relevant thermal, hydraulic, mechanical, and chemical transport processes in the bedrock, together with climate-related physical processes at the ground surface, and with explicit treatment of bedrock heterogeneity. Hence practical applications require combinations of models based on different simplifications. Key improvements can be expected in treatment of the unsaturated zone, simulation of heterogeneous infiltration at the surface, and hydromechanical coupling. Significant advances have already been made in the amounts and types of data that can be used in site-scale models, including large datasets to define topography and other surface

Environment, safety and Health Progress Assessment of the Rocky Flats Plant

International Nuclear Information System (INIS)

1993-05-01

This report documents the result of the US Department of Energy's (DOE) Environment, Safety and Health (ES ampersand H) Progress Assessment of the DOE Rocky Flats Plant (RFP) in Golden, Colorado. The assessment, which was conducted during the period of May 17 through May 28, 1993, included a selective review of the ES ampersand H management systems and programs of the responsible DOE Headquarters Program Offices (Defense Programs (DP) and Environmental Restoration and Waste Management (EM)), the DOE Rocky Flats Office (RFO), and the site contractor, EG ampersand G Rocky Flats, Inc. (EG ampersand G). Despite the near constant state of flux under which RFP has been required to operate, the Progress Assessment Team has concluded that significant progress has been made in correcting the deficiencies identified in the 1989 Assessment and in responding responsibly to regulations, and DOE directives and guidance that have been issued since that time. The Team concluded that the improvements have been concentrated in the activities associated with plutonium facilities and in regulatory driven programs. Much remains to be done with respect to implementing on a sitewide basis those management systems that anchor an organization's pursuit of continuous ES ampersand H improvement. Furthermore the Team concluded that the pace of improvement has been constrained by a combination of factors that have limited the site's ability to manage change in the pursuit of sitewide ES ampersand H excellence

A multidisciplinary approach to site remediation and management in a bedrock environment

Energy Technology Data Exchange (ETDEWEB)

Millard, G. [Shell Canada Ltd., Calgary, AB (Canada); Micklethwaite, R.; Digel, S.; Lyons, E. [O' Connor Associates Environmental Inc., Calgary, AB (Canada)

2006-07-01

A multidisciplinary approach to site remediation and management in a bedrock environment was presented. This presentation provided a description of the site which was a former service station from 1985 to 2003 in Calgary. Illustrations of the subject site and stratigraphic section were presented along with initial environmental conditions. The project objectives included: managing the site so that a tenant could re-develop and occupy the site; minimizing management costs until long-term, remediation could be achieved; and, developing and implementing a plan to assess, mitigate, and manage the risk in a manner accepted by Alberta Environment and the City of Calgary. The presentation also addressed issues regarding a risk-assessment, high vacuum extraction system, and refining HVE operations. The regulatory, business and ancillary outcomes of the risk assessment were also outlined. Last, the presentation identified how the results were achieved. tabs., figs.

Representation a Framwork for Contractors Selection Via of Health, Safety and Environment

Directory of Open Access Journals (Sweden)

Shahram Mahmoudi

2016-12-01

Full Text Available Introduction: Quality and efficiency of health, safety, and environment (HSE management systems play a vital role in achieving their goals. Considering outputs and objective achievement make continuous improvement of services and products, internal and external customer satisfaction, adopting a systematic way for performing various tasks, system performance and analysis very important. The present study was conducted to construct a proper framework for assessing MAPNA group contractors in terms of their health, safety, and environment performance.  . Method: In the first step of the study, all documents and literature associated with performance assessment were reviewed. In the second step, using a focus group approach, a basic model for assessing HSE management system was designed. Lastly, the framework was tested and credited on three major contractors of MAPNA group. Results: The proposed framework was composed of five criteria. The main criteria was the pattern of HSE process implementation which had seven sub-criteria and 120 guiding hints. Moreover, the five criteria were able to assess the organizational capabilities in terms of health, safety, and environment management.. Conclusion: The proposed framework make contractors able to promote their HSE performances by identifying organizational strong and weak points, prioritizing improvement projects, and also monitoring the pace of improvement in achieving organizational excellence..

Alberta Environment's weir safety program : options for rehabilitation to improve public safety : a case study of the Calgary weir

Energy Technology Data Exchange (ETDEWEB)

Blakely, D. [Alberta Environment, Edmonton, AB (Canada)

2009-07-01

Alberta Environment Water Management Operations (WMO) owns and operates 46 dams and 800 kilometres of canals in Alberta. The WMO consists of 120 staff and several contract operators to take care of this infrastructure. Most of the infrastructure supplies water for irrigation use, which adds 5 billion dollars to the provincial economy annually. Other water uses include stock watering, domestic use, municipal use, recreational use and habitat. Alberta Environment's weir safety program was also discussed along with options for rehabilitation to improve public safety. A case study of Calgary's Weir Dam on the Bow River was highlighted. A brief history of the dam was offered and safety programs around provincially-owned weirs were discussed. Photographs were included to illustrate some of the additional safety measures at the Calgary weir, such as suspended safety buoys upstream of the boom directing paddlers to the portage trail, and signage on the river that can be activated when the boom is out. Typical river users on the Calgary Bow River and safety history at the Calgary Weir were discussed along with other topics such as the Calgary Bow River weir project criteria; project design progress; pre-feasibility options; scale modelling; final design analysis; construction funding; and proposed changes to the safety program for the new weir configuration. figs.

The effect of Health, Safety and Environment Management System (HSE-MS on the improvement of safety performance indices in Urea and Ammonia Kermanshah Petrochemical Company

Directory of Open Access Journals (Sweden)

M. S. Poursoleiman

2015-09-01

Full Text Available Introduction: Work-related accidents may cause damage to people, environment and lead to waste of time and money. Health, Safety and Environment Management System has been developed in order to reduce accidents. This study aimed to investigate the effect of implementation of this system on reduction of the accidents and its consequences and also on the safety performance indices in Kermanshah Petrochemical Company. Material and Method: In this study, records of accidents were collected by OSHA incident report form 301 over 4 years. Following, the mean annual accidents and its consequences and safety performance indices were calculated and reported. Then, using statistical analysis, the impacts of two years implementation of this system on the accidents and its consequences and safety performance indices were evaluated. Result: The results showed that the implementation of HSE system was significantly correlated with Frequency Severity Indicator, Accident Severity Rate, lost days, minor accidents and total incidents (P-value 0.05. Conclusion: The implementation of Health, Safety and the Environment Management System caused a reduction in accidents and its consequences and most of the safety performance indices in the entire process cycle of Kermanshah Petrochemical Company. Overall, safety condition has been improved considerably.

Safety analysis of JMTR LEU fuel core, (3)

International Nuclear Information System (INIS)

Tsuchida, Noboru; Shiraishi, Tadao; Takahashi, Yutaka; Inada, Seiji; Saito, Minoru; Futamura, Yoshiaki; Kitano, Kyoshiro.

1992-10-01

Dose analysis in the safety evaluation and the site evaluation were performed for the JMTR core conversion from MEU fuel to LEU fuel. In the safety evaluation, the effective dose equivalents for the public surrounding the site were estimated in fuel handling accident and flow blockage to coolant channel which were selected as the design basis accidents with release of radioactive fission products to the environment. In the site evaluation, the flow blockage to coolant channel was selected as siting basis events, since this accident had the possibility of spreading radioactive release. Maximum exposure doses for the public were estimated assuming large amounts of fission products to release. It was confirmed that risk of radiation exposure of the public is negligible and the siting is appropriate. (author)

Management of nanomaterials safety in research environment

Directory of Open Access Journals (Sweden)

Riediker Michael

2010-12-01

Full Text Available Abstract Despite numerous discussions, workshops, reviews and reports about responsible development of nanotechnology, information describing health and environmental risk of engineered nanoparticles or nanomaterials is severely lacking and thus insufficient for completing rigorous risk assessment on their use. However, since preliminary scientific evaluations indicate that there are reasonable suspicions that activities involving nanomaterials might have damaging effects on human health; the precautionary principle must be applied. Public and private institutions as well as industries have the duty to adopt preventive and protective measures proportionate to the risk intensity and the desired level of protection. In this work, we present a practical, 'user-friendly' procedure for a university-wide safety and health management of nanomaterials, developed as a multi-stakeholder effort (government, accident insurance, researchers and experts for occupational safety and health. The process starts using a schematic decision tree that allows classifying the nano laboratory into three hazard classes similar to a control banding approach (from Nano 3 - highest hazard to Nano1 - lowest hazard. Classifying laboratories into risk classes would require considering actual or potential exposure to the nanomaterial as well as statistical data on health effects of exposure. Due to the fact that these data (as well as exposure limits for each individual material are not available, risk classes could not be determined. For each hazard level we then provide a list of required risk mitigation measures (technical, organizational and personal. The target 'users' of this safety and health methodology are researchers and safety officers. They can rapidly access the precautionary hazard class of their activities and the corresponding adequate safety and health measures. We succeed in convincing scientist dealing with nano-activities that adequate safety measures and

Management of nanomaterials safety in research environment.

Science.gov (United States)

Groso, Amela; Petri-Fink, Alke; Magrez, Arnaud; Riediker, Michael; Meyer, Thierry

2010-12-10

Despite numerous discussions, workshops, reviews and reports about responsible development of nanotechnology, information describing health and environmental risk of engineered nanoparticles or nanomaterials is severely lacking and thus insufficient for completing rigorous risk assessment on their use. However, since preliminary scientific evaluations indicate that there are reasonable suspicions that activities involving nanomaterials might have damaging effects on human health; the precautionary principle must be applied. Public and private institutions as well as industries have the duty to adopt preventive and protective measures proportionate to the risk intensity and the desired level of protection. In this work, we present a practical, 'user-friendly' procedure for a university-wide safety and health management of nanomaterials, developed as a multi-stakeholder effort (government, accident insurance, researchers and experts for occupational safety and health). The process starts using a schematic decision tree that allows classifying the nano laboratory into three hazard classes similar to a control banding approach (from Nano 3--highest hazard to Nano1--lowest hazard). Classifying laboratories into risk classes would require considering actual or potential exposure to the nanomaterial as well as statistical data on health effects of exposure. Due to the fact that these data (as well as exposure limits for each individual material) are not available, risk classes could not be determined. For each hazard level we then provide a list of required risk mitigation measures (technical, organizational and personal). The target 'users' of this safety and health methodology are researchers and safety officers. They can rapidly access the precautionary hazard class of their activities and the corresponding adequate safety and health measures. We succeed in convincing scientist dealing with nano-activities that adequate safety measures and management are promoting

MODERN THREATS OF SOCIAL SAFETY OF THE EDUCATION ENVIRONMENT AND THEIR PREVENTION

Directory of Open Access Journals (Sweden)

Павел Александрович Кисляков

2013-04-01

Full Text Available Purpose: identify modern threats of safety of the school and substantiate the direction of their prevention.Methodology: a theoretical analysis of psychological and pedagogical literature on the issues of safety of students.Results: on the basis of theoretical and empirical analysis identified the following threats of social safety of the education environment: criminal threats, threats of extremism and terrorism, physical and mental abuse, interpersonal conflicts, addictive behavior of students. Substantiates the necessity the design of social safety protection, including space of health, space of tolerance, psychologically comfortable space without violence also providing appropriate training of educators.Practical implications: the system of education.DOI: http://dx.doi.org/10.12731/2218-7405-2013-2-2

Buffer, backfill and closure process report for the safety assessment SR-Site

International Nuclear Information System (INIS)

Sellin, Patrik

2010-11-01

This report gives an account of how processes in buffer, deposition tunnel backfill and the closure important for the long-term evolution of a KBS-3 repository for spent nuclear fuel, will be documented in the safety assessment SR-Site

Buffer, backfill and closure process report for the safety assessment SR-Site

Energy Technology Data Exchange (ETDEWEB)

Sellin, Patrik (ed.)

2010-11-15

This report gives an account of how processes in buffer, deposition tunnel backfill and the closure important for the long-term evolution of a KBS-3 repository for spent nuclear fuel, will be documented in the safety assessment SR-Site

Exploring the Influence of Nursing Work Environment and Patient Safety Culture on Missed Nursing Care in Korea.

Science.gov (United States)

Kim, Kyoung-Ja; Yoo, Moon Sook; Seo, Eun Ji

2018-04-20

This study aimed to explore the influence of nurse work environment and patient safety culture in hospital on instances of missed nursing care in South Korea. A cross-sectional design was used, in which a structured questionnaire was administered to 186 nurses working at a tertiary university hospital. Data were analyzed using descriptive statistics, t-test or ANOVA, Pearson correlation and multiple regression analysis. Missed nursing care was found to be correlated with clinical career, nursing work environment and patient safety culture. The regression model explained approximately 30.3 % of missed nursing care. Meanwhile, staffing and resource adequacy (β = -.31, p = .001), nurse manager ability, leadership and support of nurses (β = -.26, p = .004), clinical career (β = -.21, p = .004), and perception on patient safety culture within unit (β = -.19, p = .041) were determined to be influencing factors on missed nursing care. This study has significance as it suggested that missed nursing care is affected by work environment factors within unit. This means that missed nursing care is a unit outcome affected by nurse work environment factors and patient safety culture. Therefore, missed nursing care can be managed through the implementation of interventions that promote a positive nursing work environment and patient safety culture. Copyright © 2018. Published by Elsevier B.V.

The Vredefort Dome World Heritage Site: Client satisfaction with ...

African Journals Online (AJOL)

Given the substantial growth of whitewater rafting in the Vredefort Dome World Heritage Site (VDWHS), it quickly grew into an unregulated adventure tourism commodity. With the area being a World Heritage Site, concerns have arisen about the impact it could have on the environment, service quality and public safety.

Site environmental report for 1994

Energy Technology Data Exchange (ETDEWEB)

Brekke, D.D.; Holland, R.C.; Gordon, K.W. [ed.

1995-12-01

Sandia National Laboratories (SNL) is committed to conducting its operations in an environmentally safe and sound manner. It is mandatory that activities at SNL/California comply with all applicable environmental statutes, regulations, and standards. Moreover, SNL/California continuously strives to reduce risks to employees, the public, and the environment to the lowest levels reasonably possible. To help verify effective protection of public safety and preservation of the environment, SNL/California maintains an extensive, ongoing environmental monitoring program. This program monitors all significant airborne and liquid effluents and the environment at the SNL/California site perimeter. Lawrence Livermore National Laboratory (LLNL) performs off-site environmental monitoring for both sites. These monitoring efforts ensure that emission controls are effective in preventing contamination of the environment. As part of SNL/California`s Environmental Monitoring Program, an environmental surveillance system measures the possible presence of radioactive and hazardous materials in ambient air, surface water, groundwater, sewage, soil, vegetation, and locally-produced food-stuffs. The program also includes an extensive environmental dosimetry program, which measures external radiation levels around the Livermore site and nearby vicinity. Each year, the results of the Environmental Monitoring Program are published in this report, the Site Environmental Report This executive summary focuses on impacts to the environment and estimated radiation doses to the public from site emissions. Chapter 3, {open_quotes}Compliance Summary,{close_quotes} reviews the site`s various environmental protection activities and compliance status with applicable environmental regulations. The effluent monitoring and environmental surveillance results for 1994 show that SNL/California operations had no harmful effects on the environment or the public. A summary of the findings is provided below.

Geotechnical aspects of site evaluation and foundations for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2003-01-01

This publication is a revision of the former safety standards of IAEA Safety Series No. 50-SG-S8. The scope has been extended to cover not only foundations but also design questions related to geotechnical science and engineering, such as the bearing capacity of foundations, design of earth structures and design of buried structures. Seismic aspects also play an important role in this field, and consequently the Safety Guide on Evaluation of Seismic Hazards for Nuclear Power Plants, Safety Standards Series No. NS-G-3.3, which discusses the determination of seismic input motion, is referenced on several occasions. The present Safety Guide provides an interpretation of the Safety Requirements on Site Evaluation for Nuclear Installations and guidance on how to implement them. It is intended for the use of safety assessors or regulators involved in the licensing process as well as the designers of nuclear power plants, and it provides them with guidance on the methods and procedures for analyses to support the assessment of the geotechnical aspects of the safety of nuclear power plants

Geotechnical aspects of site evaluation and foundations for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2006-01-01

This publication is a revision of the former safety standards of IAEA Safety Series No. 50-SG-S8. The scope has been extended to cover not only foundations but also design questions related to geotechnical science and engineering, such as the bearing capacity of foundations, design of earth structures and design of buried structures Seismic aspects also play an important role in this field, and consequently the Safety Guide on Evaluation of Seismic Hazards for Nuclear Power Plants, Safety Standards Series No. NS-G-3.3, which discusses the determination of seismic input motion, is referenced on several occasions. The present Safety Guide provides an interpretation of the Safety Requirements on Site Evaluation for Nuclear Installations and guidance on how to implement them. It is intended for the use of safety assessors or regulators involved in the licensing process as well as the designers of nuclear power plants, and it provides them with guidance on the methods and procedures for analyses to support the assessment of the geotechnical aspects of the safety of nuclear power plants

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

Health science students and their learning environment: a comparison of perceptions of on-site, remote-site, and traditional classroom students.

Science.gov (United States)

Elison-Bowers, P; Snelson, Chareen; Casa de Calvo, Mario; Thompson, Heather

2008-02-05

This study compared the responses of on-site, remote-site, and traditional classroom students on measures of student/teacher interaction, course structure, physical learning environment, and overall course enjoyment/satisfaction. The sample population consisted of students taking undergraduate courses in medical terminology at two western colleges. The survey instrument was derived from Thomerson's questionnaire, which included closed- and open-ended questions assessing perceptions of students toward their courses. Controlling for grade expectations, results revealed no significant differences among the on-site, remote-site, and traditional classroom students in any of the four cluster domains. However, a nonsignificant (and continuing) trend suggested that students preferred the traditional classroom environment. When results were controlled for age, significant differences emerged between traditional and nontraditional students on measures of student/teacher interaction, physical learning environment, and overall enjoyment/satisfaction, as nontraditional students exhibited higher scores. Students' responses to open-ended questions indicated they enjoyed the convenience of online instruction, but reported finding frustration with technology itself.

Safety Evaluation Report Restart of K-Reactor Savannah River Site

International Nuclear Information System (INIS)

1991-10-01

In April 1991, the Department of Energy (DOE) issued DOE/DP-0084T, ''Safety Evaluation Report Restart of K-Reactor Savannah River Site.'' The Safety Evaluation Report (SER) documents the results of DOE reviews and evaluations of the programmatic aspects of a large number of issues necessary to be satisfactorily addressed before restart. The issues were evaluated for compliance with the restart criteria included in the SER. The results of those evaluations determined that the restart criteria had been satisfied for some of the issues. However, for most of the issues at least part of the applicable restart criteria had not been found to be satisfied at the time the evaluations were prepared. For those issues, open or confirmatory items were identified that required resolution. In August 1991, DOE issued DOE/DP-0090T, ''Safety Evaluation Report Restart of K-Reactor Savannah River Site Supplement 1.'' That document was the first Supplement to the April 1991 SER, and documented the resolution of 62 of the open items identified in the SER. This document is the second Supplement to the April 1991 SER. This second SER Supplement documents the resolution of additional open times identified in the SER, and includes a complete list of all remaining SER open items. The resolution of those remaining open items will be documented in future SER Supplements. Resolution of all open items for an issue indicates that its associated restart criteria have been satisfied, and that DOE concludes that the programmatic aspects of the issue have been satisfactorily addressed

Plutonium working group report on environmental, safety and health vulnerabilities associated with the Department's plutonium storage. Volume 2, Appendix B, Part 4: Savannah River Site site assessment team report

International Nuclear Information System (INIS)

1994-09-01

The Plutonium Environmental, Safety, and Health (ES and H) Vulnerability Assessment is being conducted by the DOE Office of Environment, Safety, and Health (DOE-EH) to evaluate the ES and H vulnerabilities arising from the Department's storage and handling of its holdings of plutonium and other transuranic isotopes. This report on Savannah River Site (SRS) facilities and materials provides the results of a self-assessment for the purpose of identifying issues as potential vulnerabilities. The report provides data and analyses for the DOE-EH and independent Working Group Assessment Team, which will make the final determination as to ES and H vulnerabilities at SRS. The term ES and H vulnerabilities is defined for the purpose of this assessment to mean conditions that could lead to unnecessary or increased radiation exposure of workers, release of radioactive materials to the environment, or radiation exposure of the public. The self-assessment identifies and prioritizes candidate or potential vulnerabilities and issues for consideration by the Working Group Assessment Team, and will serve as an information base for identifying interim corrective actions and options for the safe management of fissile materials. It will also establish a foundation for decision making regarding the safe management and disposition of DOE plutonium

Replacement cross-site transfer system project W-058 safety class upgrade summary report

International Nuclear Information System (INIS)

Schlosser, R.L.

1998-01-01

This report evaluates the design of the replacement cross-site transfer system structures, systems, and components for safety related applications as defined in the Tank Waste Remediation Systems Basis for Interim Operations

Waste Isolation Pilot Plant 2001 Site Environmental Report

Energy Technology Data Exchange (ETDEWEB)

Westinghouse TRU Solutions, Inc.

2002-09-20

The United States (U.S.) Department of Energy's (DOE) Carlsbad Field Office (CBFO) and Westinghouse TRU Solutions LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2001 Site Environmental Report summarizes environmental data from calendar year (CY) 2001 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH- 0173T), and the Waste Isolation Pilot Plant Environmental Protection Implementation Plan (DOE/WIPP 96-2199). The above Orders and guidance documents require that DOE facilities submit an annual site environmental report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health; and the New Mexico Environment Department (NMED). The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during CY 2001. WIPP received its first shipment of waste on March 26, 1999. In 2001, no evidence was found of any adverse effects from WIPP on the surrounding environment.

Waste Isolation Pilot Plant 2001 Site Environmental Report

International Nuclear Information System (INIS)

Westinghouse TRU Solutions, Inc.

2002-01-01

The United States (U.S.) Department of Energy's (DOE) Carlsbad Field Office (CBFO) and Westinghouse TRU Solutions LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2001 Site Environmental Report summarizes environmental data from calendar year (CY) 2001 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH- 0173T), and the Waste Isolation Pilot Plant Environmental Protection Implementation Plan (DOE/WIPP 96-2199). The above Orders and guidance documents require that DOE facilities submit an annual site environmental report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health; and the New Mexico Environment Department (NMED). The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during CY 2001. WIPP received its first shipment of waste on March 26, 1999. In 2001, no evidence was found of any adverse effects from WIPP on the surrounding environment

Waste Isolation Pilot Plant 1999 Site Environmental Report

Energy Technology Data Exchange (ETDEWEB)

Evans, Roy B.; Adams, Amy; Martin, Don; Morris, Randall C.; Reynolds, Timothy D.; Warren, Ronald W.

2000-09-30

The U.S. Department of Energy's (DOE)Carlsbad Area Office and the Westinghouse Waste Isolation Division (WID) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 1999 Site Environmental Report summarizes environmental data from calendar year 1999 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH- 0173T), and the Waste Isolation Pilot Plant Environmental Protection Implementation Plan (DOE/WIPP 96-2199). The above orders and guidance documents require that DOE facilities submit an Annual Site Environmental Report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health. The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during calendar year 1999. WIPP received its first shipment of waste on March 26, 1999. In 1999, no evidence was found of any adverse effects from WIPP on the surrounding environment. Radionuclide concentrations in the environment surrounding WIPP were not statistically higher in 1999 than in 1998.

Site Environmental Report for 2015

Energy Technology Data Exchange (ETDEWEB)

Pauer, Ron O. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Baskin, David A. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Borglin, Ned K. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Fox, Robert A. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Harvey, Zachary R. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Jelinski, John A. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Kassis, Maram M. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Muhlholland, Brendan J. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Thorson, Patrick A. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Xu, Suying Y. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Sutherland, Nancy L. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Wehle, Petra C. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

2016-09-30

The annual Site Environmental Report documents Lawrence Berkeley National Laboratory’s performance in reducing its environmental impacts, progress toward cleaning up groundwater contamination, and compliance with applicable Department of Energy, federal, state, and local environmental regulations. The report is required by DOE Order 231.1B, Environment, Safety, and Health Reporting.

The effect of Health, Safety and Environment Management System (HSE-MS on the improvement of safety performance indices in Urea and Ammonia Kermanshah Petrochemical Company

Directory of Open Access Journals (Sweden)

M. S. Poursoleiman

2015-09-01

.Conclusion: The implementation of Health, Safety and the Environment Management System caused a reduction in accidents and its consequences and most of the safety performance indices in the entire process cycle of Kermanshah Petrochemical Company. Overall, safety condition has been improved considerably.

Criticality safety engineering at the Savannah River Site - the 1990s

International Nuclear Information System (INIS)

Chandler, J.R.; Apperson, C.E. Jr.

1996-01-01

The privatization and downsizing effort that is ongoing within the U.S. Department of Energy (DOE) is requiring a change in the management of criticality safety engineering resources at the Savannah River Site (SRS). Downsizing affects the number of criticality engineers employed by the prime contractor, Westinghouse Savannah River Company (WSRC), and privatization affects the manner in which business is conducted. In the past, criticality engineers at the SRS have been part of the engineering organizations that support each facility handling fissile material. This practice led to different criticality safety engineering organizations dedicated to fuel fabrication activities, reactor loading and unloading activities, separation and waste management operations, and research and development

Radiation Safety Management Guidelines for PET-CT: Focus on Behavior and Environment

International Nuclear Information System (INIS)

Jung, Jin Wook; Han, Eun Ok

2011-01-01

Our purpose is to specify behavior and environmental factors aimed at reducing the exposed dosage caused by PET-CT and to develop radiation safety management guidelines adequate for domestic circumstances. We have used a multistep-multimethod as the methodological approach to design and to carry out the research both in quality and quantity, including an analysis on previous studies, professional consultations and a survey. The survey includes responses from 139 practitioners in charged of 109 PET-CTs installed throughout Korea(reported by the Korean Society of Nuclear Medicine, 2010). The research use 156 questions using Cronbach's α (alpha) coefficients which were: 0.818 for 'the necessity of setting and installing the radiation protective environment'; 0.916 for 'the necessity of radiation protection', 'setting and installing the radiation protective environment'; and 0.885 for 'radiation protection'. The check list, derived from the radiation safety management guidelines focused on behavior and environment, was composed of 20 items for the radiation protective environment: including 5 items for the patient; 4 items for the guardian; 3 items for the radiologist; and 8 items applied to everyone involved; for a total of 26 items for the radiation protective behavior including: 12 items for the patient; 1 item for the guardian, 7 items for the radiologist; and 6 items applied to everyone involved. The specific check list is shown in (Table 5-6). Since our country has no safety management guidelines of its own to reduce the exposed dosage caused by PET-CTs, we believe the guidelines developed through this study means great deal to the field as it is not only appropriate for domestic circumstances, but also contains specific check lists for each target who may be exposed to radiation in regards to behavior and environment.

The pursuit of health, safety and environment objectives

International Nuclear Information System (INIS)

Armstrong, K.

1994-01-01

The conference paper examines certain issues facing E and P companies with respect to health, safety and environment (HSE) management and costs. It reviews some of the pressures forcing companies to increase their HSE cost reductions. It discusses the critical role that risk management plays in efforts to resolve these competing pressures so as to best protect shareholder value, and it identifies some areas for potential improvement. Finally, it examines the contribution industry partnerships with government can make in promoting cost-effective HSE risk management. 8 refs

The pursuit of health, safety and environment objectives

Energy Technology Data Exchange (ETDEWEB)

Armstrong, K [Chevron Overseas Petroleum, Inc. (United States)

1994-12-31

The conference paper examines certain issues facing E and P companies with respect to health, safety and environment (HSE) management and costs. It reviews some of the pressures forcing companies to increase their HSE cost reductions. It discusses the critical role that risk management plays in efforts to resolve these competing pressures so as to best protect shareholder value, and it identifies some areas for potential improvement. Finally, it examines the contribution industry partnerships with government can make in promoting cost-effective HSE risk management. 8 refs.

Safety class methodology

International Nuclear Information System (INIS)

Donner, E.B.; Low, J.M.; Lux, C.R.

1992-01-01

DOE Order 6430.1A, General Design Criteria (GDC), requires that DOE facilities be evaluated with respect to ''safety class items.'' Although the GDC defines safety class items, it does not provide a methodology for selecting safety class items. The methodology described in this paper was developed to assure that Safety Class Items at the Savannah River Site (SRS) are selected in a consistent and technically defensible manner. Safety class items are those in the highest of four categories determined to be of special importance to nuclear safety and, merit appropriately higher-quality design, fabrication, and industrial test standards and codes. The identification of safety class items is approached using a cascading strategy that begins at the 'safety function' level (i.e., a cooling function, ventilation function, etc.) and proceeds down to the system, component, or structure level. Thus, the items that are required to support a safety function are SCls. The basic steps in this procedure apply to the determination of SCls for both new project activities, and for operating facilities. The GDC lists six characteristics of SCls to be considered as a starting point for safety item classification. They are as follows: 1. Those items whose failure would produce exposure consequences that would exceed the guidelines in Section 1300-1.4, ''Guidance on Limiting Exposure of the Public,'' at the site boundary or nearest point of public access 2. Those items required to maintain operating parameters within the safety limits specified in the Operational Safety Requirements during normal operations and anticipated operational occurrences. 3. Those items required for nuclear criticality safety. 4. Those items required to monitor the release of radioactive material to the environment during and after a Design Basis Accident. Those items required to achieve, and maintain the facility in a safe shutdown condition 6. Those items that control Safety Class Item listed above

Cooperation of the site and public fire and safety services in case of an incident

International Nuclear Information System (INIS)

Bauch, M.

1997-01-01

This report describes the cooperation between the site and the public fire and safety services in case of an incident. As an example, the measures and facilities of the Hoechst site of the Hoechst AG and the organisational and technical background are presented. (orig.) [de

Effect of Practice Ownership on Work Environment, Learning Culture, Psychological Safety, and Burnout.

Science.gov (United States)

Cuellar, Alison; Krist, Alex H; Nichols, Len M; Kuzel, Anton J

2018-04-01

Physicians have joined larger groups and hospital systems in the face of multiple environmental challenges. We examine whether there are differences across practice ownership in self-reported work environment, a practice culture of learning, psychological safety, and burnout. Using cross-sectional data from staff surveys of small and medium-size practices that participated in EvidenceNOW in Virginia, we tested for differences in work environment, culture of learning, psychological safety, and burnout by practice type. We conducted weighted multivariate linear regression of outcomes on ownership, controlling for practice size, specialty mix, payer mix, and whether the practice was located in a medically underserved area. We further analyzed clinician and staff responses separately. Participating were 104 hospital-owned and 61 independent practices and 24 federally qualified health centers (FQHCs). We analyzed 2,005 responses from practice clinicians and staff, a response rate of 49%. Working in a hospital-owned practice was associated with favorable ratings of work environment, psychological safety, and burnout compared with independent practices. When we examined separately the responses of clinicians vs staff, however, the association appears to be largely driven by staff. Hospital ownership was associated with positive perceptions of practice work environment and lower burnout for staff relative to independent ownership, whereas clinicians in FQHCs perceive a more negative, less joyful work environment and burnout. Our findings are suggestive that clinician and nonclinician staff perceive practice adaptive reserve differently, which may have implications for creating the energy for ongoing quality improvement work. © 2018 Annals of Family Medicine, Inc.

Site environmental report for 1994

International Nuclear Information System (INIS)

Brekke, D.D.; Holland, R.C.; Gordon, K.W.

1995-01-01

Sandia National Laboratories (SNL) is committed to conducting its operations in an environmentally safe and sound manner. It is mandatory that activities at SNL/California comply with all applicable environmental statutes, regulations, and standards. Moreover, SNL/California continuously strives to reduce risks to employees, the public, and the environment to the lowest levels reasonably possible. To help verify effective protection of public safety and preservation of the environment, SNL/California maintains an extensive, ongoing environmental monitoring program. This program monitors all significant airborne and liquid effluents and the environment at the SNL/California site perimeter. Lawrence Livermore National Laboratory (LLNL) performs off-site environmental monitoring for both sites. These monitoring efforts ensure that emission controls are effective in preventing contamination of the environment. As part of SNL/California's Environmental Monitoring Program, an environmental surveillance system measures the possible presence of radioactive and hazardous materials in ambient air, surface water, groundwater, sewage, soil, vegetation, and locally-produced food-stuffs. The program also includes an extensive environmental dosimetry program, which measures external radiation levels around the Livermore site and nearby vicinity. Each year, the results of the Environmental Monitoring Program are published in this report, the Site Environmental Report This executive summary focuses on impacts to the environment and estimated radiation doses to the public from site emissions. Chapter 3, open-quotes Compliance Summary,close quotes reviews the site's various environmental protection activities and compliance status with applicable environmental regulations. The effluent monitoring and environmental surveillance results for 1994 show that SNL/California operations had no harmful effects on the environment or the public. A summary of the findings is provided below

A study on development of monitoring and assessment module for sites

International Nuclear Information System (INIS)

Park, Se Moon; Yoon, Bong Yo; Kim, Dae Jung; Park, Joo Wan; Kim, Chang Lak

2006-01-01

As the development of total management systems for sites along with site environmental information is becoming standard, the system known as the Site Information and Total Environmental database management System (SITES) has been developed over the last two years. The first result was a database management system for storing data obtained from facilities, and a site characterization in addition to an environmental assessment of a site. The SITES database is designed to be effective and practical for use with facility management and safety assessment in relation to Geographic Information Systems. SITES is a total management program, which includes its database, its data analysis system required for site characterization, a safety assessment modeling system and an environment monitoring system. I can contribute to the institutional management of the facility and to its safety reassessment. SITES is composed of two main modules: the SITES Database Module (SDM) and the Monitoring and Assessment (M and A) module. The M and A module is subdivided into two sub-modules: the Safety Assessment System (SAS) and the Site Environmental Monitoring System (SEMS). SAS controls the data (input and output) from the SITES DB for the site safety assessment, whereas SEMS controls the data obtained from the records of the measuring sensors and facilities. The on-line site and environmental monitoring data is managed in SEMS. The present paper introduces the procedure and function of the M and A modules

Preparation of off-site emergency preparedness plans for nuclear installations

International Nuclear Information System (INIS)

1999-10-01

Safety of public, occupational workers and the protection of environment should be assured while activities for economic and social progress are pursued. These activities include the establishment and utilisation of nuclear facilities and use of radioactive sources. This document is issued as a lead document to facilitate preparation of specific site manuals by the Responsible Organisation for emergency response plans at each site to ensure their preparedness to meet any eventuality due to site emergency in order to mitigate its consequences on the health and safety of site personnel. It takes cognizance of an earlier AERB publication on the subject: Safety Manual on Off-Site Emergency Plan for Nuclear Installations, AERB/SM/NISD-2, 1988 and also takes into consideration the urgent need for promoting public awareness and drawing up revised emergency response plans, which has come out in a significant manner after the accidents at Chernobyl and Bhopal

Resolution of the ferrocyanide safety issue for the Hanford site high-level waste tanks

International Nuclear Information System (INIS)

Cash, R.J.

1996-01-01

This paper describes the approach used to resolve the ferrocyanide safety issue, a process that began in 1990 after heightened concern was expressed by various government agencies about the safety of Hanford site high-level waste tanks. At the time, little was known about ferrocyanide-nitrate/nitrite reactions and the potential for offsite releases of radioactivity from the Hanford Site. Recent studies have shown that the combined effects of temperature, radiation, and pH during more than 38 years of storage have destroyed most of the ferrocyanide originally added to tanks. This has been proven in the laboratory using flowsheet-derived waste simulants and confirmed by waste samples obtained from the ferrocyanide tanks. The resulting tank waste sludges are too dilute to support a sustained exothermic reaction, even if dried out and heated to temperatures of at least 250 C. The US Department of Energy (DOE) has been requested to close the ferrocyanide safety issue

Cold Vacuum Drying Safety Class Instrumentation and Control System Design Description SYS 93-2

International Nuclear Information System (INIS)

WHITEHURST, R.

1999-01-01

This document describes the Cold Vacuum Drying Facility (CVDF) Safety Class Instrumentation and Control system (SCIC). The SCIC provides safety functions and features to protect the environment, off-site and on-site personnel and equipment. The function of the SCIC is to provide automatic trip features, valve interlocks, alarms, indication and control for the cold vacuum drying process

Chemical conditions in present and future ecosystems in Forsmark - implications for selected radionuclides in the safety assessment SR-Site

International Nuclear Information System (INIS)

Troejbom, Mats; Grolander, Sara

2010-12-01

This report is a background report for the biosphere analysis of the SR-Site Safety Assessment. This work aims to describe the future development of the chemical conditions at Forsmark, based on the present chemical conditions at landscape level taking landscape development and climate cases into consideration. The results presented contribute to the overall understanding of the present and future chemistry in the Forsmark area, and specifically, to the understanding of the behaviour of some selected radionuclides in the surface system. The future development of the chemistry at the site is qualitatively discussed with focus on the interglacial within the next 10,000 years. The effects on the chemical environment of future climate cases as Global Warming and cold permafrost climates are also briefly discussed. The work is presented in two independent parts describing background radionuclide activities in the Forsmark area and the distribution and behaviour of a large number of stable elements in the landscape. In a concluding section, implications of the future chemical environment of a selection of radionuclides important in the Safety Assessment are discussed based on the knowledge of stable elements. The broad range of elements studied show that there are general and expected patterns for the distribution and behaviour in the landscape of different groups of elements. Mass balances reveal major sources and sinks, pool estimations show where elements are accumulated in the landscape and estimations of time-scales give indications of the potential future development. This general knowledge is transferred to radionuclides not measured in order to estimate their behaviour and distribution in the landscape. It could be concluded that the future development of the chemical environment in the Forsmark area might affect element specific parameters used in de radionuclide model in different directions depending on element. The alternative climate cases, Global Warming

Chemical conditions in present and future ecosystems in Forsmark - implications for selected radionuclides in the safety assessment SR-Site

Energy Technology Data Exchange (ETDEWEB)

Troejbom, Mats (Mats Troejbom Konsult AB (Sweden)); Grolander, Sara (Facilia AB (Sweden))

2010-12-15

This report is a background report for the biosphere analysis of the SR-Site Safety Assessment. This work aims to describe the future development of the chemical conditions at Forsmark, based on the present chemical conditions at landscape level taking landscape development and climate cases into consideration. The results presented contribute to the overall understanding of the present and future chemistry in the Forsmark area, and specifically, to the understanding of the behaviour of some selected radionuclides in the surface system. The future development of the chemistry at the site is qualitatively discussed with focus on the interglacial within the next 10,000 years. The effects on the chemical environment of future climate cases as Global Warming and cold permafrost climates are also briefly discussed. The work is presented in two independent parts describing background radionuclide activities in the Forsmark area and the distribution and behaviour of a large number of stable elements in the landscape. In a concluding section, implications of the future chemical environment of a selection of radionuclides important in the Safety Assessment are discussed based on the knowledge of stable elements. The broad range of elements studied show that there are general and expected patterns for the distribution and behaviour in the landscape of different groups of elements. Mass balances reveal major sources and sinks, pool estimations show where elements are accumulated in the landscape and estimations of time-scales give indications of the potential future development. This general knowledge is transferred to radionuclides not measured in order to estimate their behaviour and distribution in the landscape. It could be concluded that the future development of the chemical environment in the Forsmark area might affect element specific parameters used in de radionuclide model in different directions depending on element. The alternative climate cases, Global Warming

Monitoring human factor risk characteristics at nuclear legacy sites in northwest Russia in support of radiation safety regulation

International Nuclear Information System (INIS)

Scheblanov, V Y; Bobrov, A F; Sneve, M K

2012-01-01

This paper describes research aimed at improving regulatory supervision of radiation safety during work associated with the management of spent nuclear fuel and radioactive waste at legacy sites in northwest Russia through timely identification of employees presenting unfavourable human factor risk characteristics. The legacy sites of interest include sites of temporary storage now operated by SevRAO on behalf of Rosatom. The sites were previously operational bases for servicing nuclear powered submarines and are now subject to major remediation activities. These activities include hazardous operations for recovery of spent nuclear fuel and radioactive waste from sub-optimal storage conditions. The paper describes the results of analysis of methods, procedures, techniques and informational issues leading to the development of an expert-diagnostic information system for monitoring of workers involved in carrying out the most hazardous operations. The system serves as a tool for human factor and professional reliability risk monitoring and has been tested in practical working environments and implemented as part of regulatory supervision. The work has been carried out by the Burnasyan Federal Medical Biophysical Center, within the framework of the regulatory cooperation programme between the Federal Medical–Biological Agency of Russia and the Norwegian Radiation Protection Authority. (paper)

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

Aviation Trends Related to Atmospheric Environment Safety Technologies Project Technical Challenges

Science.gov (United States)

Reveley, Mary S.; Withrow, Colleen A.; Barr, Lawrence C.; Evans, Joni K.; Leone, Karen M.; Jones, Sharon M.

2014-01-01

Current and future aviation safety trends related to the National Aeronautics and Space Administration's Atmospheric Environment Safety Technologies Project's three technical challenges (engine icing characterization and simulation capability; airframe icing simulation and engineering tool capability; and atmospheric hazard sensing and mitigation technology capability) were assessed by examining the National Transportation Safety Board (NTSB) accident database (1989 to 2008), incidents from the Federal Aviation Administration (FAA) accident/incident database (1989 to 2006), and literature from various industry and government sources. The accident and incident data were examined for events involving fixed-wing airplanes operating under Federal Aviation Regulation (FAR) Parts 121, 135, and 91 for atmospheric conditions related to airframe icing, ice-crystal engine icing, turbulence, clear air turbulence, wake vortex, lightning, and low visibility (fog, low ceiling, clouds, precipitation, and low lighting). Five future aviation safety risk areas associated with the three AEST technical challenges were identified after an exhaustive survey of a variety of sources and include: approach and landing accident reduction, icing/ice detection, loss of control in flight, super density operations, and runway safety.

Industrial hazard and safety handbook

CERN Document Server

King, Ralph W

1979-01-01

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

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