Evaluation of periodic safety status analyses

International Nuclear Information System (INIS)

Faber, C.; Staub, G.

1997-01-01

In order to carry out the evaluation of safety status analyses by the safety assessor within the periodical safety reviews of nuclear power plants safety goal oriented requirements have been formulated together with complementary evaluation criteria. Their application in an inter-disciplinary coopertion covering the subject areas involved facilitates a complete safety goal oriented assessment of the plant status. The procedure is outlined briefly by an example for the safety goal 'reactivity control' for BWRs. (orig.) [de

Bases of updating of nuclear safety regulations for NPP in Romania

International Nuclear Information System (INIS)

Biro, Lucian; Serbanescu, Dan

1999-01-01

The paper presents the basic principles of reviewing and updating process of the regulatory environment pyramid. The main part of this review process refers to Cernavoda NPP Unit 2. However, there is an important impact on Cernavoda NPP Unit 1. The basic principles were defined in 1993/1994 when the licensing process for Unit 1 was resumed in order to be in accordance with the latest developments of Candu 600 worldwide and with the IAEA and NEA latest recommended documents and practices. After the licensing process for the Unit 1 was completed up to operation stage, CNCAN developed new updated regulations on nuclear safety and the regulatory pyramid in the framework of the RAMG PHARE project. CNCAN issued in 1996 the regulatory Policy for Unit 2, self-sustained and independent of future possible revisions of the regulations. The use of the concept of hierarchical systems, systematic review of safety criteria and objectives and margins along with the feedback from international and national experience on this topic ensured issuance of a reference document for future approach of nuclear safety in Romania. (authors)

Periodic safety review of the HTR-10 safety analysis

International Nuclear Information System (INIS)

Chen Fubing; Zheng Yanhua; Shi Lei; Li Fu

2015-01-01

Designed by the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University, the 10 MW High Temperature Gas-cooled Reactor-Test Module (HTR-10) is the first modular High Temperature Gas-cooled Reactor (HTGR) in China. According to the nuclear safety regulations of China, the periodic safety review (PSR) of the HTR-10 was initiated by INET after approved by the National Nuclear Safety Administration (NNSA) of China. Safety analysis of the HTR-10 is one of the key safety factors of the PSR. In this paper, the main contents in the review of safety analysis are summarized; meanwhile, the internal evaluation on the review results is presented by INET. (authors)

2016 Updated American Society of Clinical Oncology/Oncology Nursing Society Chemotherapy Administration Safety Standards, Including Standards for Pediatric Oncology.

Science.gov (United States)

Neuss, Michael N; Gilmore, Terry R; Belderson, Kristin M; Billett, Amy L; Conti-Kalchik, Tara; Harvey, Brittany E; Hendricks, Carolyn; LeFebvre, Kristine B; Mangu, Pamela B; McNiff, Kristen; Olsen, MiKaela; Schulmeister, Lisa; Von Gehr, Ann; Polovich, Martha

2016-12-01

Purpose To update the ASCO/Oncology Nursing Society (ONS) Chemotherapy Administration Safety Standards and to highlight standards for pediatric oncology. Methods The ASCO/ONS Chemotherapy Administration Safety Standards were first published in 2009 and updated in 2011 to include inpatient settings. A subsequent 2013 revision expanded the standards to include the safe administration and management of oral chemotherapy. A joint ASCO/ONS workshop with stakeholder participation, including that of the Association of Pediatric Hematology Oncology Nurses and American Society of Pediatric Hematology/Oncology, was held on May 12, 2015, to review the 2013 standards. An extensive literature search was subsequently conducted, and public comments on the revised draft standards were solicited. Results The updated 2016 standards presented here include clarification and expansion of existing standards to include pediatric oncology and to introduce new standards: most notably, two-person verification of chemotherapy preparation processes, administration of vinca alkaloids via minibags in facilities in which intrathecal medications are administered, and labeling of medications dispensed from the health care setting to be taken by the patient at home. The standards were reordered and renumbered to align with the sequential processes of chemotherapy prescription, preparation, and administration. Several standards were separated into their respective components for clarity and to facilitate measurement of adherence to a standard. Conclusion As oncology practice has changed, so have chemotherapy administration safety standards. Advances in technology, cancer treatment, and education and training have prompted the need for periodic review and revision of the standards. Additional information is available at http://www.asco.org/chemo-standards .

75 FR 51525 - Railroad Safety Advisory Committee (RSAC); Working Group Activity Update

Science.gov (United States)

2010-08-20

.... The Working Group continues to work on after arrival orders, and at the September 25-26, 2008, meeting... protecting persons who work on, under, or between rolling equipment and persons applying, removing or.... 63] Railroad Safety Advisory Committee (RSAC); Working Group Activity Update AGENCY: Federal Railroad...

Krsko periodic safety review project prioritization process

International Nuclear Information System (INIS)

Basic, I.; Vrbanic, I.; Spiler, J.; Lambright, J.

2004-01-01

Definition of a Krsko Periodic Safety Review (PSR) project is a comprehensive safety review of a plant after last ten years of operation. The objective is a verification by means of a comprehensive review using current methods that Krsko NPP remains safety when judged against current safety objectives and practices and that adequate arrangements are in place to maintain plant safety. This objective encompasses the three main criteria or goals: confirmation that the plant is as safe as originally intended, determination if there are any structures, systems or components that could limit the life of the plant in the foreseeable future, and comparison the plant against modern safety standards and to identify where improvements would be beneficial at justifiable cost. Krsko PSR project is structured in the three phases: Phase 1: Preparation of Detailed 10-years PSR Program, Phase 2: Performing of 10-years PSR Program and preparing of associated documents (2001-2003), and Phase 3: Implementation of the prioritized compensatory measures and modifications (development of associated EEAR, DMP, etc.) after agreement with the SNSA on the design, procedures and time-scales (2004-2008). This paper presents the NEK PSR results of work performed under Phase 2 focused on the ranking of safety issues and prioritization of corrective measures needed for establishing an efficient action plan. Safety issues were identified in Phase 2 during the following review processes: Periodic Safety Review (PSR) task; Krsko NPP Regulatory Compliance Program (RCP) review; Westinghouse Owner Group (WOG) catalog items screening/review; SNSA recommendations (including IAEA RAMP mission suggestions/recommendations).(author)

NPP Krsko periodic safety review. Safety assessment and analyses

International Nuclear Information System (INIS)

Basic, I.; Spiler, J.; Thaulez, F.

2002-01-01

Definition of a PSR (Periodic Safety Review) project is a comprehensive safety review of a plant after ten years of operation. The objective is a verification by means of a comprehensive review using current methods that the plant remains safe when judged against current safety objectives and practices and that adequate arrangements are in place to maintain plant safety. The overall goals of the NEK PSR Program are defined in compliance with the basic role of a PSR and the current practice typical for most of the countries in EU. This practice is described in the related guides and good practice documents issued by international organizations. The overall goals of the NEK PSR are formulated as follows: to demonstrate that the plant is as safe as originally intended; to evaluate the actual plant status with respect to aging and wear-out identifying any structures, systems or components that could limit the life of the plant in the foreseeable future, and to identify appropriate corrective actions, where needed; to compare current level of safety in the light of modern standards and knowledge, and to identify where improvements would be beneficial for minimizing deviations at justifiable costs. The Krsko PSR will address the following safety factors: Operational Experience, Safety Assessment, EQ and Aging Management, Safety Culture, Emergency Planning, Environmental Impact and Radioactive Waste.(author)

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

Science.gov (United States)

2009-10-01

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

Long-Term Safety Analysis of Baldone Radioactive Waste Repository and Updating of Waste Acceptance Criteria

International Nuclear Information System (INIS)

2001-12-01

The main objective of the project was to provide advice to the Latvian authorities on the safety enhancements and waste acceptance criteria for near surface radioactive waste disposal facilities of the Baldone repository. The project included the following main activities: Analysis of the current status of the management of radioactive waste in Latvia in general and, at the Baldone repository in particular Development of the short and long-term safety analysis of the Baldone repository, including: the planned increasing of capacity for disposal and long term storage, the radiological analysis for the post-closure period Development of the Environment Impact Statement, for the new foreseen installations, considering the non radiological components Proposal of recommendations for future updating of radioactive waste acceptance criteria Proposal of recommendations for safety upgrades to the facility. The work programme has been developed in phases and main tasks as follows. Phase 0: Project inception, Phase 1: Establishment of current status, plans and practices (Legislation, regulation and standards, Radioactive waste management, Waste acceptance criteria), Phase 2: Development of future strategies for long-term safety management and recommendations for safety enhancements. The project team found the general approach use at the installation, the basic design and the operating practices appropriate to international standards. Nevertheless, a number of items subject to potential improvements were also identified. These upgrading recommendations deal with general aspects of the management (mainly storage versus disposal of long-lived sources), site and environmental surveillance, packaging (qualification of containers, waste characterization requirements), the design of an engineered cap and strategies for capping. (author)

Optimization of maintenance periodicity of complex of NPP safety systems

International Nuclear Information System (INIS)

Kolykhanov, V.; Skalozubov, V.; Kovrigkin, Y.

2006-01-01

The analysis of the positive and negative aspects connected to maintenance of the safety systems equipment which basically is in a standby state is executed. Tests of systems provide elimination of the latent failures and raise their reliability. Poor quality of carrying out the tests can be a source of the subsequent failures. Therefore excess frequency of tests can result in reducing reliability of safety systems. The method of optimization of maintenance periodicity of the equipment taking into account factors of its reliability and restoration procedures quality is submitted. The unavailability factor is used as a criterion of optimization of maintenance periodicity. It is offered to use parameters of reliability of the equipment and each of safety systems of NPPs received at developing PSA. And it is offered to carry out the concordance of maintenance periodicity of systems within the NPP maintenance program taking into account a significance factor of the system received on the basis of the contribution of system in CDF. Basing on the submitted method the small computer code is developed. This code allows to calculate reliability factors of a separate safety system and to determine optimum maintenance periodicity of its equipment. Optimization of maintenance periodicity of a complex of safety systems is stipulated also. As an example results of optimization of maintenance periodicity at Zaporizhzhya NPP are presented. (author)

Los Alamos Climatology 2016 Update

Energy Technology Data Exchange (ETDEWEB)

Bruggeman, David Alan [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-02-10

The Los Alamos National Laboratory (LANL or the Laboratory) operates a meteorology monitoring network to support LANL emergency response, engineering designs, environmental compliance, environmental assessments, safety evaluations, weather forecasting, environmental monitoring, research programs, and environmental restoration. Weather data has been collected in Los Alamos since 1910. Bowen (1990) provided climate statistics (temperature and precipitation) for the 1961– 1990 averaging period, and included other analyses (e.g., wind and relative humidity) based on the available station locations and time periods. This report provides an update to the 1990 publication Los Alamos Climatology (Bowen 1990).

Preparation of NPP Dukovany periodic safety review

International Nuclear Information System (INIS)

Dubsky, L.; Vymazal, P.

2004-01-01

Dukovany NPP in Czech Republic performs a periodic safety review for the second time after approximately 20 years of operation. The history of the Safety Report and its transformation into an internationally accepted form complying with IAEA standards is described. The deterministic and probabilistic assessment of the plant's safety-related design and state is applied to determine whether and to what extend the relevant protective goals are fulfilled by the existing plant design. A description of the step-by-step process is presented together with the creation of methods and criteria for PSR evaluation prepared by Nuclear Research Institute Rez

An updated status of Department of Energy safety reviews of packages for transporting radioactive material

International Nuclear Information System (INIS)

Kapoor, A.

1995-01-01

The Department of Energy conducts conformance reviews and issues Certificates of Compliance for Type B packaging for radioactive materials. Several offices within DOE perform these reviews which are required by the Department of Transportation to be to the regulations promulgated by the Nuclear Regulatory Commission or their safety equivalent. This paper focuses on one of these offices, the Office of Facility Safety Analysis, EH-32, which is responsible for reviewing and certifying packages other than those used for weapons and weapons component, for Naval Reactors, and for Civilian Radioactive Waste Management. This paper gives the background and organizational history of EH-32, discusses the version of regulations to which the packaging is reviewed, updates the status of these reviews, describes the effectiveness of the reviews, updates the training courses sponsored by EH-32, and mentions the new Quality Assurance Evaluations being started by EH-32

Periodic safety re-evaluations in NPPs in EC member states, Finland and Sweden

International Nuclear Information System (INIS)

1990-01-01

The work on periodic safety re-evaluations summarized in this report was performed by a Task Force of the CEC Working Group on the Safety of Thermal Reactors. The periodic safety re-evaluations under review in this study were those that are carried out in addition to other reviews which represent the primary means of safety assurance. The periodic safety re-evaluation is broader and more comprehensive in nature. The cumulative effects of experience (national and international), advances in knowledge and analysis techniques, improvements in safety standards and operating practices, overall effects of plant ageing, and the totality of all modifications over the period in question need to be taken into account. All countries have recognized the value of such periodic reviews, and licensees, either as a regulatory requirement or as a voluntary action, are carrying them out. The scope and contents of each country's review showed many similarities of approach, any differences being explained by the age and type of reactor in operation. Many similarities emerged in the topics selected for re-evaluation and in the approach to re-evaluation itself. The overall conclusion was that while approaches may differ in some respects, for practical purposes comparable levels of safety are achieved in the periodic safety re-evaluation of nuclear power plants

Myopic control of stochastic inventories with intermittent updates: continuous versus periodic replenishment

OpenAIRE

M Shnaiderman

2012-01-01

A manufacturer who is responsible for supplying a retailer with a single product is considered. The retailer sells the product in response to stochastic demand and provides the manufacturer with periodic updates about his inventories. Replenishing the retailer's inventory under two myopic base-stock policies is addressed. These policies, referred to as vendor managed inventory, represent a relatively new approach to allocating responsibility in the replenishment process. Specifically, the man...

Evaluation of Hazardous Material Management Safety in the Chemical Laboratory in BATAN

International Nuclear Information System (INIS)

Nur-Rahmah-Hidayati

2005-01-01

The management safety of the hazardous material (B3) in the chemical laboratory of BATAN was evaluated. The evaluation is necessary to be done because B3 is often used together with radioactive materials in the laboratory, but the attention to the safety aspect of B3 is not paid sufficiently in spite of its big potential hazard. The potential hazard generated from the nature of B3 could be flammable, explosive, oxidative, corrosive and poisonous. The handling of B3 could be conducted by enforcing the labelling and classification in the usage and disposal processes. Some observations of the chemical laboratory of BATAN show that the management safety of hazardous material in compliance with the government regulation no. 74 year 2001 has not been dully conducted. The management safety of B3 could be improved by, designating one who has adequate skill in hazardous material safety specially as the B3 safety officer, providing the Material Safety Data Sheet that is updated periodically to use in the laboratory and storage room, updating periodically the inventory of B3, performing training in work safety periodically, and monitoring the ventilation system intensively in laboratory and storage room. (author)

Updated procedure for the safety evaluation of natural flavor complexes used as ingredients in food

NARCIS (Netherlands)

Cohen, Samuel M.; Eisenbrand, Gerhard; Fukushima, Shoji; Gooderham, Nigel J.; Guengerich, F.P.; Hecht, Stephen S.; Rietjens, Ivonne M.C.M.; Davidsen, Jeanne M.; Harman, Christie L.; Taylor, Sean V.

2018-01-01

An effective and thorough approach for the safety evaluation of natural flavor complexes (NFCs) was published in 2005 by the Expert Panel of the Flavor and Extract Manufacturers Association (FEMA). An updated procedure is provided here, which maintains the essential concepts of the use of the

Major update of Safety Analysis Report for Thai Research Reactor-1/Modification 1

Energy Technology Data Exchange (ETDEWEB)

Tippayakul, Chanatip [Thailand Institute of Nuclear Technology, Bangkok (Thailand)

2013-07-01

Thai Research Reactor-1/Modification 1 (TRR-1/M1) was converted from a Material Testing Reactor in 1975 and it had been operated by Office of Atom for Peace (OAP) since 1977 until 2007. During the period, Office of Atom for Peace had two duties for the reactor, that is, to operate and to regulate the reactor. However, in 2007, there was governmental office reformation which resulted in the separation of the reactor operating organization from the regulatory body in order to comply with international standard. The new organization is called Thailand Institute of Nuclear Technology (TINT) which has the mission to promote peaceful utilization of nuclear technology while OAP remains essentially the regulatory body. After the separation, a new ministerial regulation was enforced reflecting a new licensing scheme in which TINT has to apply for a license to operate the reactor. The safety analysis report (SAR) shall be submitted as part of the license application. The ministerial regulation stipulates the outlines of the SAR almost equivalent to IAEA standard 35-G1. Comparing to the IAEA 35-G1 standard, there were several incomplete and missing chapters in the original SAR of TRR1/M1. The major update of the SAR was therefore conducted and took approximately one year. The update work included detail safety evaluation of core configuration which used two fuel element types, the classification of systems, structures and components (SSC), the compilation of detail descriptions of all SSCs and the review and evaluation of radiation protection program, emergency plan and emergency procedure. Additionally, the code of conduct and operating limits and conditions were revised and finalized in this work. A lot of new information was added to the SAR as well, for example, the description of commissioning program, information on environmental impact assessment, decommissioning program, quality assurance program and etc. Due to the complexity of this work, extensive knowledge was

77 FR 41258 - FOIA Fee Schedule Update

Science.gov (United States)

2012-07-13

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD 10 CFR Part 1703 FOIA Fee Schedule Update AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Establishment of FOIA Fee Schedule. SUMMARY: The Defense Nuclear Facilities Safety Board is publishing its Freedom of Information Act (FOIA) Fee Schedule Update pursuant to...

76 FR 43819 - FOIA Fee Schedule Update

Science.gov (United States)

2011-07-22

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD 10 CFR Part 1703 FOIA Fee Schedule Update AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Establishment of FOIA Fee Schedule. SUMMARY: The Defense Nuclear Facilities Safety Board is publishing its Freedom of Information Act (FOIA) Fee Schedule Update pursuant to...

Update on radiation safety and dose reduction in pediatric neuroradiology

International Nuclear Information System (INIS)

Mahesh, Mahadevappa

2015-01-01

The number of medical X-ray imaging procedures is growing exponentially across the globe. Even though the overall benefit from medical X-ray imaging procedures far outweighs any associated risks, it is crucial to take all necessary steps to minimize radiation risks to children without jeopardizing image quality. Among the X-ray imaging studies, except for interventional fluoroscopy procedures, CT studies constitute higher dose and therefore draw considerable scrutiny. A number of technological advances have provided ways for better and safer CT imaging. This article provides an update on the radiation safety of patients and staff and discusses dose optimization in medical X-ray imaging within pediatric neuroradiology. (orig.)

Update on radiation safety and dose reduction in pediatric neuroradiology

Energy Technology Data Exchange (ETDEWEB)

Mahesh, Mahadevappa [Johns Hopkins University School of Medicine, The Russell H. Morgan Department of Radiology and Radiological Science, Baltimore, MD (United States)

2015-09-15

The number of medical X-ray imaging procedures is growing exponentially across the globe. Even though the overall benefit from medical X-ray imaging procedures far outweighs any associated risks, it is crucial to take all necessary steps to minimize radiation risks to children without jeopardizing image quality. Among the X-ray imaging studies, except for interventional fluoroscopy procedures, CT studies constitute higher dose and therefore draw considerable scrutiny. A number of technological advances have provided ways for better and safer CT imaging. This article provides an update on the radiation safety of patients and staff and discusses dose optimization in medical X-ray imaging within pediatric neuroradiology. (orig.)

Periodic safety reviews of nuclear power plants

International Nuclear Information System (INIS)

Toth, Csilla

2009-01-01

Operational nuclear power plants (NPPs) are generally subject to routine reviews of plant operation and special safety reviews following operational events. In addition, many Member States of the International Atomic Energy Agency (IAEA) have initiated systematic safety reassessment, termed periodic safety review (PSR), to assess the cumulative effects of plant ageing and plant modifications, operating experience, technical developments, site specific, organizational and human aspects. These reviews include assessments of plant design and operation against current safety standards and practices. PSRs are considered an effective way of obtaining an overall view of actual plant safety, to determine reasonable and practical modifications that should be made in order to maintain a high level of safety throughout the plant's operating lifetime. PSRs can be used as a means to identify time limiting features of the plant. The trend is to use PSR as a condition for deciding whether to continue operation of the plant beyond the originally established design lifetime and for assessing the status of the plant for long term operation. To assist Member States in the implementation of PSR, the IAEA develops safety standards, technical documents and provides different services: training courses, workshops, technical meetings and safety review missions for the independent assessment of the PSR at NPPs, including the requirements for PSR, the review process and the PSR final reports. This paper describes the PSR's objectives, scopes, methods and the relationship of PSR with other plant safety related activities and recent experiences of Member States in implementation of PSRs at NPPs. (author)

Safety of Transcranial Direct Current Stimulation: Evidence Based Update 2016.

Science.gov (United States)

Bikson, Marom; Grossman, Pnina; Thomas, Chris; Zannou, Adantchede Louis; Jiang, Jimmy; Adnan, Tatheer; Mourdoukoutas, Antonios P; Kronberg, Greg; Truong, Dennis; Boggio, Paulo; Brunoni, André R; Charvet, Leigh; Fregni, Felipe; Fritsch, Brita; Gillick, Bernadette; Hamilton, Roy H; Hampstead, Benjamin M; Jankord, Ryan; Kirton, Adam; Knotkova, Helena; Liebetanz, David; Liu, Anli; Loo, Colleen; Nitsche, Michael A; Reis, Janine; Richardson, Jessica D; Rotenberg, Alexander; Turkeltaub, Peter E; Woods, Adam J

2016-01-01

This review updates and consolidates evidence on the safety of transcranial Direct Current Stimulation (tDCS). Safety is here operationally defined by, and limited to, the absence of evidence for a Serious Adverse Effect, the criteria for which are rigorously defined. This review adopts an evidence-based approach, based on an aggregation of experience from human trials, taking care not to confuse speculation on potential hazards or lack of data to refute such speculation with evidence for risk. Safety data from animal tests for tissue damage are reviewed with systematic consideration of translation to humans. Arbitrary safety considerations are avoided. Computational models are used to relate dose to brain exposure in humans and animals. We review relevant dose-response curves and dose metrics (e.g. current, duration, current density, charge, charge density) for meaningful safety standards. Special consideration is given to theoretically vulnerable populations including children and the elderly, subjects with mood disorders, epilepsy, stroke, implants, and home users. Evidence from relevant animal models indicates that brain injury by Direct Current Stimulation (DCS) occurs at predicted brain current densities (6.3-13 A/m(2)) that are over an order of magnitude above those produced by conventional tDCS. To date, the use of conventional tDCS protocols in human trials (≤40 min, ≤4 milliamperes, ≤7.2 Coulombs) has not produced any reports of a Serious Adverse Effect or irreversible injury across over 33,200 sessions and 1000 subjects with repeated sessions. This includes a wide variety of subjects, including persons from potentially vulnerable populations. Copyright © 2016 Elsevier Inc. All rights reserved.

Development of a Safety Assessment Information System for the Management of Periodic Safety Assessment Activities

International Nuclear Information System (INIS)

Song, Tae Young

2007-01-01

At present, the 10-year Periodic Safety Review(PSR) has been performing to confirm all the aspects of safety issues for all the operating plants in compliance with domestic nuclear law of article 23, subarticle 3. For each plant, in addition, Probabilistic Safety Assessment(PSA) and Severe Accident Management Guideline(SAMG) are being implemented and revised periodically to reflect the latest safety level according to principle fulfillment of severe accident policy statement. The assessment reports, as one of outcomes from these activities, are submitted into and reviewed by domestic regulatory body. During reviewing (in-office duty) and licensing (regulatory duty) process, a large number of outcomes of which most are the formal technical reports and licensing materials, are inevitably produced. Moreover, repeated review process over the plants can make them accumulated and produce a variety of documents additionally. This circumstance motivates to develop effective tool or system for the management of these reports and related technical documents for the future use in licensing process and for subsequent plant assessments. This paper presents the development status of Safety Assessment Information System(SAIS) which manages safety-related documents of PSR, PSA and SAMG for practical use for experienced engineers in charge of these areas

Development of a Safety Assessment Information System for the Management of Periodic Safety Assessment Activities

Energy Technology Data Exchange (ETDEWEB)

Song, Tae Young [Nuclear Engineering and Technology Institute, Daejeon (Korea, Republic of)

2007-07-01

At present, the 10-year Periodic Safety Review(PSR) has been performing to confirm all the aspects of safety issues for all the operating plants in compliance with domestic nuclear law of article 23, subarticle 3. For each plant, in addition, Probabilistic Safety Assessment(PSA) and Severe Accident Management Guideline(SAMG) are being implemented and revised periodically to reflect the latest safety level according to principle fulfillment of severe accident policy statement. The assessment reports, as one of outcomes from these activities, are submitted into and reviewed by domestic regulatory body. During reviewing (in-office duty) and licensing (regulatory duty) process, a large number of outcomes of which most are the formal technical reports and licensing materials, are inevitably produced. Moreover, repeated review process over the plants can make them accumulated and produce a variety of documents additionally. This circumstance motivates to develop effective tool or system for the management of these reports and related technical documents for the future use in licensing process and for subsequent plant assessments. This paper presents the development status of Safety Assessment Information System(SAIS) which manages safety-related documents of PSR, PSA and SAMG for practical use for experienced engineers in charge of these areas.

Using resources for scientific-driven pharmacovigilance: from many product safety documents to one product safety master file.

Science.gov (United States)

Furlan, Giovanni

2012-08-01

Current regulations require a description of the overall safety profile or the specific risks of a drug in multiple documents such as the Periodic and Development Safety Update Reports, Risk Management Plans (RMPs) and Signal Detection Reports. In a resource-constrained world, the need for preparing multiple documents reporting the same information results in shifting the focus from a thorough scientific and medical evaluation of the available data to maintaining compliance with regulatory timelines. Since the aim of drug safety is to understand and characterize product issues to take adequate risk minimization measures rather than to comply with bureaucratic requirements, there is the need to avoid redundancy. In order to identify core drug safety activities that need to be undertaken to protect patient safety and reduce the number of documents reporting the results of these activities, the author has reviewed the main topics included in the drug safety guidelines and templates. The topics and sources that need to be taken into account in the main regulatory documents have been found to greatly overlap and, in the future, as a result of the new Periodic Safety Update Report structure and requirements, in the author's opinion this overlap is likely to further increase. Many of the identified inter-document differences seemed to be substantially formal. The Development Safety Update Report, for example, requires separate presentation of the safety issues emerging from different sources followed by an overall evaluation of each safety issue. The RMP, instead, requires a detailed description of the safety issues without separate presentation of the evidence derived from each source. To some extent, however, the individual documents require an in-depth analysis of different aspects; the RMP, for example, requires an epidemiological description of the indication for which the drug is used and its risks. At the time of writing this article, this is not specifically

Second periodic safety review of Angra Nuclear Power Station, unit 1

Energy Technology Data Exchange (ETDEWEB)

Martins, Carlos F.O.; Crepaldi, Roberto; Freire, Enio M., E-mail: ottoncf@tecnatom.com.br, E-mail: emfreire46@gmail.com, E-mail: robcrepaldi@hotmail.com [Tecnatom do Brasil Engenharia e Servicos Ltda, Rio de Janeiro, RJ (Brazil); Campello, Sergio A., E-mail: sacampe@eletronuclear.gov.br [Eletrobras Termonuclear S.A. (ELETRONUCLEAR), Rio de Janeiro, RJ (Brazil)

2015-07-01

This paper describes the second Periodic Safety Review (PSR2-A1) of Angra Nuclear Power Station, Unit 1, prepared by Eletrobras Eletronuclear S.A. and Tecnatom do Brasil Engenharia e Servicos Ltda., during Jul.2013-Aug.2014, covering the period of 2004-2013. The site, in Angra dos Reis-RJ, Brazil, comprises: Unit 1, (640 MWe, Westinghouse PWR, operating), Unit 2 (1300 MWe, KWU/Areva, operating) and Unit 3 (1405 MWe, KWU/Areva, construction). The PSR2-A1 attends the Standards 1.26-Safety in Operation of Nuclear Power Plants, Brazilian Nuclear Regulatory Commission (CNEN), and IAEA.SSG.25-Periodic Safety Review of Nuclear Power Plants. Within 18 months after each 10 years operation, the operating organization shall perform a plant safety review, to investigate the evolution consequences of safety code and standards, regarding: Plant design; structure, systems and components behavior; equipment qualification; plant ageing management; deterministic and probabilistic safety analysis; risk analysis; safety performance; operating experience; organization and administration; procedures; human factors; emergency planning; radiation protection and environmental radiological impacts. The Review included 6 Areas and 14 Safety Parameters, covered by 33 Evaluations.After document evaluations and discussions with plant staff, it was generated one General and 33 Specific Guide Procedures, 33 Specific and one Final Report, including: Description, Strengths, Deficiencies, Areas for Improvement and Conclusions. An Action Plan was prepared by Electronuclear for the recommendations. It was concluded that the Unit was operated within safety standards and will attend its designed operational lifetime, including possible life extensions. The Final Report was submitted to CNEN, as one requisite for renewal of the Unit Permanent Operation License. (author)

Second periodic safety review of Angra Nuclear Power Station, unit 1

International Nuclear Information System (INIS)

Martins, Carlos F.O.; Crepaldi, Roberto; Freire, Enio M.; Campello, Sergio A.

2015-01-01

This paper describes the second Periodic Safety Review (PSR2-A1) of Angra Nuclear Power Station, Unit 1, prepared by Eletrobras Eletronuclear S.A. and Tecnatom do Brasil Engenharia e Servicos Ltda., during Jul.2013-Aug.2014, covering the period of 2004-2013. The site, in Angra dos Reis-RJ, Brazil, comprises: Unit 1, (640 MWe, Westinghouse PWR, operating), Unit 2 (1300 MWe, KWU/Areva, operating) and Unit 3 (1405 MWe, KWU/Areva, construction). The PSR2-A1 attends the Standards 1.26-Safety in Operation of Nuclear Power Plants, Brazilian Nuclear Regulatory Commission (CNEN), and IAEA.SSG.25-Periodic Safety Review of Nuclear Power Plants. Within 18 months after each 10 years operation, the operating organization shall perform a plant safety review, to investigate the evolution consequences of safety code and standards, regarding: Plant design; structure, systems and components behavior; equipment qualification; plant ageing management; deterministic and probabilistic safety analysis; risk analysis; safety performance; operating experience; organization and administration; procedures; human factors; emergency planning; radiation protection and environmental radiological impacts. The Review included 6 Areas and 14 Safety Parameters, covered by 33 Evaluations.After document evaluations and discussions with plant staff, it was generated one General and 33 Specific Guide Procedures, 33 Specific and one Final Report, including: Description, Strengths, Deficiencies, Areas for Improvement and Conclusions. An Action Plan was prepared by Electronuclear for the recommendations. It was concluded that the Unit was operated within safety standards and will attend its designed operational lifetime, including possible life extensions. The Final Report was submitted to CNEN, as one requisite for renewal of the Unit Permanent Operation License. (author)

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

International Nuclear Information System (INIS)

1976-01-01

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

Safety and efficacy of vernakalant for acute cardioversion of atrial fibrillation: an update

Science.gov (United States)

Tsuji, Yukiomi; Dobrev, Dobromir

2013-01-01

Intravenous vernakalant has recently been approved in Europe as an atrial-selective antiarrhythmic drug for the conversion of recent-onset atrial fibrillation (AF). It inhibits atrial-selective K+ currents (IK,ACh and IKur) and causes rate-dependent atrial-predominant Na+ channel block, with only a small inhibitory effect on the rapid delayed rectifier K+ current (IKr) in the ventricle. Due to its atrial-selective properties, vernakalant prolongs the effective refractory period of the atria with minimal effects on the ventricles, being associated with a low proarrhythmic risk for torsades de pointes arrhythmias. Five pivotal clinical trials consistently demonstrated that vernakalant rapidly terminates AF with stable maintenance of sinus rhythm for up to 24 hours. A head-to-head comparative trial showed that the 90-minute conversion rate of vernakalant was substantially higher than that of amiodarone. Initially, a longer-acting oral formulation of vernakalant was shown to be effective and safe in preventing AF recurrence after cardioversion in a Phase IIb study. However, the clinical studies testing oral vernakalant for maintenance of sinus rhythm after AF cardioversion were prematurely halted for undisclosed reasons. This review article provides an update on the safety and efficacy of intravenous vernakalant for the rapid cardioversion of AF. PMID:23637539

Regulatory Aspect of Periodic Safety Review Performed in Nuclear Power Plants in the Slovak Republic

International Nuclear Information System (INIS)

Baszo, Z.

2010-01-01

The paper deals with the regulatory aspect of Nuclear Power Plant (NPP) Periodic Safety Review (PSR) as a part of license renewal process in the Slovak Republic. It summarizes the history of activities similar to PSR performed in the past for NPPs operated in the Slovak Republic. Furthermore, it describes both the requirements involved in the current Slovak legislation to be met by licensee in the Slovak Republic in this field and the procedures concerning the PSR as well. The objective and rules of PSR to be performed for NPPs in the Slovak Republic were derived from the internationally accepted International Atomic Energy Agency (IAEA) document and have been implemented into national legislation. PSR of two twin units located in Bohunice NPP and Mochovce NPP, respectively, has been initiated in the Slovak Republic based on evaluation of each area to be reviewed (safety factors) using recent methodology and practice. Other significant factors, such as ageing, modifications of NPP and the safe operation for a specified future period, have to be assessed in the frame of PSR. Report on performed PSR outlines the results of review for each area, the corrective plan, which considering mutual relations between assessed areas specifies the issues to be solved with the aim to eliminate shortcomings identified in the frame of PSR and to adopt safety improvements. The findings from PSR in the evaluated areas also serve as a source of information for updating of all documents to be attached to the written application of licensee for renewal of a nuclear power plant operating license. The presented procedure describes how the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) has reviewed the documents submitted during PSR. Based on results of submitted documents evaluation and licensee application for license renewal the license for next 10 years operation has been issued for Bohunice NPP. At present, similar procedure for Mochovce NPP unit 1 and 2 is underway.(author).

Safety update on the use of recombinant activated factor VII in approved indications.

Science.gov (United States)

Neufeld, Ellis J; Négrier, Claude; Arkhammar, Per; Benchikh el Fegoun, Soraya; Simonsen, Mette Duelund; Rosholm, Anders; Seremetis, Stephanie

2015-06-01

This updated safety review summarises the large body of safety data available on the use of recombinant activated factor VII (rFVIIa) in approved indications: haemophilia with inhibitors, congenital factor VII (FVII) deficiency, acquired haemophilia and Glanzmann's thrombasthenia. Accumulated data up to 31 December 2013 from clinical trials as well as post-marketing data (registries, literature reports and spontaneous reports) were included. Overall, rFVIIa has shown a consistently favourable safety profile, with no unexpected safety concerns, in all approved indications. No confirmed cases of neutralising antibodies against rFVIIa have been reported in patients with congenital haemophilia, acquired haemophilia or Glanzmann's thrombasthenia. The favourable safety profile of rFVIIa can be attributed to the recombinant nature of rFVIIa and its localised mechanism of action at the site of vascular injury. Recombinant FVIIa activates factor X directly on the surface of activated platelets, which are present only at the site of injury, meaning that systemic activation of coagulation is avoided and the risk of thrombotic events (TEs) thus reduced. Nonetheless, close monitoring for signs and symptoms of TE is warranted in all patients treated with any pro-haemostatic agent, including rFVIIa, especially the elderly and any other patients with concomitant conditions and/or predisposing risk factors to thrombosis. Copyright © 2015 Elsevier Ltd. All rights reserved.

Sixth national report of Brazil for the nuclear safety convention

International Nuclear Information System (INIS)

2013-01-01

Brazil has presented periodically its National Report prepared by a group composed of representatives of the various Brazilian organizations with responsibilities related to nuclear safety. Due to the implications of the Fukushima nuclear accident in 2011, an Extraordinary National Report was presented in 2012. This Sixth National Report is an update of the Fifth National Report in relation to the Convention on Nuclear Safety articles and also an update of the Extraordinary Report with respect to the action taken related to lesson learned from the Fukushima accident. It includes relevant information for the period of 2010/2012. This document represents the national report prepared as a fulfillment of the brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations

Sixth national report of Brazil for the nuclear safety convention

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-07-01

Brazil has presented periodically its National Report prepared by a group composed of representatives of the various Brazilian organizations with responsibilities related to nuclear safety. Due to the implications of the Fukushima nuclear accident in 2011, an Extraordinary National Report was presented in 2012. This Sixth National Report is an update of the Fifth National Report in relation to the Convention on Nuclear Safety articles and also an update of the Extraordinary Report with respect to the action taken related to lesson learned from the Fukushima accident. It includes relevant information for the period of 2010/2012. This document represents the national report prepared as a fulfillment of the brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations.

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

Science.gov (United States)

2010-06-28

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

Periodic safety review of the experimental fast reactor JOYO. Review of the activity for safety

International Nuclear Information System (INIS)

Maeda, Yukimoto; Kashimura, Youichi; Suzuki, Toshiaki; Isozaki, Kazunori; Hoshiba, Hideaki; Kitamura, Ryoichi; Nakano, Tomoyuki; Takamatsu, Misao; Sekine, Takashi

2005-02-01

Periodic safety review (Review of the activity for safety) which consisted of 'Comprehensive evaluation of operation experience' and Incorporation of the latest technical knowledge' was carried out up to January 2005. 1. Comprehensive evaluation of operation experience. It was confirmed that the effectual activities for safety through the operation of JOYO were carried out in terms of (1) Operation management, (2) Maintenance management, (3) Fuel management, (4) Radiation management, (5) Radioactive waste management, (6) Emergency planning and (7) Feedback of incidents and failures. 2. Reflection of the latest technical knowledge. It was confirmed that the latest technical knowledge including regulation and guide line established by Nuclear Safety Commission of Japan until March 31st. 2003 were properly reflected in impressing the safety of the reactor. As a result, it was evaluated that the activity for safety was carried out effectually, and no additional measure was identified continual safe operation of the reactor. (author)

Safety assessment of Olkiluoto NPP units 1 and 2. Decision of the Radiation and Nuclear Safety Authority regarding the periodic safety review of the Olkiluoto NPP

International Nuclear Information System (INIS)

2010-02-01

In this safety assessment the Radiation and Nuclear Safety Authority (STUK) has evaluated the safety of the Olkiluoto Nuclear Power Plant units 1 and 2 in connection with the periodic safety review. This safety assessment provides a summary of the reviews, inspections and continuous oversight carried out by STUK. The issues addressed in the assessment and the related evaluation criteria are set forth in the nuclear energy and radiation safety legislation and the regulations issued thereunder. The provisions of the Nuclear Energy Act concerning the safe use of nuclear energy, security and emergency preparedness arrangements, and waste management are specified in more detail in the Government Decrees and Regulatory Guides issued by STUK. Based on the assessment, STUK consideres that the Olkiluoto Nuclear Power Plant units 1 and 2 meet the set safety requirements for operational nuclear power plants, the emergency preparedness arrangements are sufficient and the necessary control to prevent the proliferation of nuclear weapons has been appropriately arranged. The physical protection of the Olkiluoto nuclear power plant is not yet completely in compliance with the requirements of Government Decree 734/2008, which came into force in December 2008. Further requirements concerning this issue based also on the principle of continuous improvement were included in the decision relating to the periodic safety review. The safety of the Olkiluoto nuclear power plant was assessed in compliance with the Government Decree on the Safety of Nuclear Power Plants (733/2008), which came into force in 2008. The decree notes that existing nuclear power plants need not meet all the requirements set out for new plants. Most of the design bases pertaining to the Olkiluoto 1 and 2 nuclear power plant units were set in the 1970s. Substantial modernisations have been carried out at the Olkiluoto 1 and 2 nuclear power plant units since their commissioning to improve safety. This is in line with

Playground Safety

Science.gov (United States)

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

The periodic safety review of nuclear power plants. Practices in OECD countries

International Nuclear Information System (INIS)

1992-01-01

This report gives an overview of the regulatory concepts and practices for the periodic safety review of nuclear power plants in OECD countries with nuclear power programmes. The statutory bases for such reviews, their objectives and the processes adopted are summarised against the background of each country's regulatory practices. Although periodic safety reviews are now, or will soon be, part of the regulatory process in the majority of countries, the national approaches to these reviews still differ considerably. This report includes numerous examples of the different concepts and practices in OECD countries, thereby illustrating the variety of ways adopted to reach the common goal of maintaining and improving nuclear safety

Aging evaluation methodology of periodic safety review in Korea

International Nuclear Information System (INIS)

Park, Heung-Bae; Jung, Sung-Gyu; Jin, Tae-Eun; Jeong, Ill-Seok

2002-01-01

In Korea plant lifetime management (PLIM) study for Kori Unit 1 has been performed since 1993. Meanwhile, periodic safety review (PSR) for all operating nuclear power plants (NPPs) has been started with Kori Unit 1 since 2000 per IAEA recommendation. The evaluation period is 10 years, and safety (evaluation) factors are 11 per IAEA guidelines as represented in table 1. The relationship between PSR factors and PLIM is also represented. Among these factors evaluation of 'management of aging' is one of the most important and difficult factor. This factor is related to 'actual condition of the NPP', 'use of experience from other nuclear NPPs and of research findings', and 'management of aging'. The object of 'management of aging' is to obtain plant safety through identifying actual condition of system, structure and components (SSCs) and evaluating aging phenomena and residual life of SSCs using operating experience and research findings. The paper describes the scope and procedure of valuation of 'management of aging', such as, screening criteria of SSCs, Code and Standards, evaluation of SSCs and safety issues as represented. Evaluating SSCs are determined using final safety analysis report (FSAR) and power unit maintenance system for Nuclear Ver. III (PUMAS/N-III). The screening criteria of SSCs are safety-related items (quality class Q), safety-impact items (quality class T), backfitting rule items (fire protection (10CFR50.48), environmental qualification (10CFR50.49), pressurized thermal shock (10CFR50.61), anticipated transient without scram (10CFR50.62), and station blackout (10CFR50.63)) and regulating authority requiring items[1∼3]. The purpose of review of Code and Standards is identifying actual condition of the NPP and evaluating aging management using effective Code and Standards corresponding to reactor facilities. Code and Standards is composed of regulating laws, FSAR items, administrative actions, regulating actions, agreement items, and other

75 FR 28814 - FHA Lender Approval, Annual Renewal, Periodic Updates and Required Reports From FHA Approved Lenders

Science.gov (United States)

2010-05-24

... proposal. This information is required for: (1) FHA lender approval, (2) Annual renewal of each FHA lender... following information: Title of Proposal: FHA Lender Approval, Annual Renewal, Periodic Updates and Required... and HUD-92001-C. Description of the Need for the Information and Its Proposed Use: This information is...

Guidance on health effects of toxic chemicals. Safety Analysis Report Update Program

Energy Technology Data Exchange (ETDEWEB)

Foust, C.B.; Griffin, G.D.; Munro, N.B.; Socolof, M.L.

1994-02-01

Martin Marietta Energy Systems, Inc. (MMES), and Martin Marietta Utility Services, Inc. (MMUS), are engaged in phased programs to update the safety documentation for the existing US Department of Energy (DOE)-owned facilities. The safety analysis of potential toxic hazards requires a methodology for evaluating human health effects of predicted toxic exposures. This report provides a consistent set of health effects and documents toxicity estimates corresponding to these health effects for some of the more important chemicals found within MMES and MMUS. The estimates are based on published toxicity information and apply to acute exposures for an ``average`` individual. The health effects (toxicological endpoints) used in this report are (1) the detection threshold; (2) the no-observed adverse effect level; (3) the onset of irritation/reversible effects; (4) the onset of irreversible effects; and (5) a lethal exposure, defined to be the 50% lethal level. An irreversible effect is defined as a significant effect on a person`s quality of life, e.g., serious injury. Predicted consequences are evaluated on the basis of concentration and exposure time.

State updating and calibration period selection to improve dynamic monthly streamflow forecasts for an environmental flow management application

Science.gov (United States)

Gibbs, Matthew S.; McInerney, David; Humphrey, Greer; Thyer, Mark A.; Maier, Holger R.; Dandy, Graeme C.; Kavetski, Dmitri

2018-02-01

Monthly to seasonal streamflow forecasts provide useful information for a range of water resource management and planning applications. This work focuses on improving such forecasts by considering the following two aspects: (1) state updating to force the models to match observations from the start of the forecast period, and (2) selection of a shorter calibration period that is more representative of the forecast period, compared to a longer calibration period traditionally used. The analysis is undertaken in the context of using streamflow forecasts for environmental flow water management of an open channel drainage network in southern Australia. Forecasts of monthly streamflow are obtained using a conceptual rainfall-runoff model combined with a post-processor error model for uncertainty analysis. This model set-up is applied to two catchments, one with stronger evidence of non-stationarity than the other. A range of metrics are used to assess different aspects of predictive performance, including reliability, sharpness, bias and accuracy. The results indicate that, for most scenarios and metrics, state updating improves predictive performance for both observed rainfall and forecast rainfall sources. Using the shorter calibration period also improves predictive performance, particularly for the catchment with stronger evidence of non-stationarity. The results highlight that a traditional approach of using a long calibration period can degrade predictive performance when there is evidence of non-stationarity. The techniques presented can form the basis for operational monthly streamflow forecasting systems and provide support for environmental decision-making.

Child Safety: MedlinePlus Health Topic

Science.gov (United States)

... injuries in children (Medical Encyclopedia) Also in Spanish Topic Image MedlinePlus Email Updates Get Child Safety updates ... safety Preventing head injuries in children Related Health Topics Infant and Newborn Care Internet Safety Motor Vehicle ...

USAR managing and updating process

International Nuclear Information System (INIS)

Prah, M.; Spiler, J.

1996-01-01

In this paper basis and background of the FSAR (Final Safety Analysis Report) document and its conversion process to the USAR (Updated Safety Analysis Report) document are described. In addition, there are internal and external reviews as approval process presented. The following is included in our new approach to manage USAR changes: initiating the USAR change, technical reviewing, preparing a safety evaluation, KSC (Krsko Safety Committee) and KOC (Krsko Operating Committee) review, ESD Director approval, and the Regulatory Body review or approval. The intensive technological modification activities started in the year 1992 when the NEK Engineering Services Division was established. These activities are one of the most important reason for a very intensive USAR items change. The other reason for its conversation to an electronic format is a possibility for easier and faster searching, updating and changing process and introducing a new systematic USAR managing approach as mentioned above. (author)

AAP Updates Recommendations on Car Seats

Science.gov (United States)

... Size Email Print Share AAP Updates Recommendations on Car Seats Page Content Article Body Children should ride ... of approved car safety seats. Healthy Children Radio: Car Seat Safety Dennis Durbin, MD, FAAP, lead author ...

Safety technical considerations on the 2012 periodic safety verification of the Beznau nuclear power plant

International Nuclear Information System (INIS)

2016-12-01

According to nuclear legislation, the owner of an operational license for a nuclear power plant has to provide a periodic safety verification (PSU) every 10 years. The 'North Eastern Power Plants' company (NOK), today AXPO Power AG already performed such a PSU for the Beznau-2 nuclear reactor block (KKB2) in 2002. The Beznau-1 nuclear reactor block (KKB1) received its definitive operational license in October 1970, after test operation during 7 months. After the license for test operation received on July 16 th , 1971, the operational license of KKB2 was renewed several times, each time for a certain period of validity. In 1991, NOK requested a definitive operational license for KKB2, but in 1994 the Swiss Federal Council lengthened the license for only 10 years. Moreover, it laid down that NOK has to periodically report on the safety of the facility. With its letter of August 23 rd , 1998, the Federal Office of Energy defined the documents to be produced for the PSU. The extent of the PSU was defined in such a way that many documents concern the whole power plant, i.e. both nuclear reactor blocks. On December 3 rd , 2004, the Swiss Federal Council granted KKB2 an operational license of limited validity. The present report reviews the 2012 PSU, which covers the time interval from January 1 st , 2002, to December 31 st , 2011, from the point of view of safety. It contains documents for the evaluation of both reactor blocks at KKB. The Beznau interim storage pool was also taken into consideration; it is situated on the KKB site, but, according to a decision of the Swiss Federal Council of May 23 rd , 1991, it has an independent operational license. The evaluation of ageing surveillance takes the whole operational period of the facility into account, i.e. the ageing mechanisms acting as from the beginning of the operation. Moreover, important developments that occurred after the surveillance time interval have been taken into account, especially the status

Assessment and management of ageing of major nuclear power plant components important to safety: PWR vessel internals: 2007 update

International Nuclear Information System (INIS)

2007-06-01

At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that effective control of the ageing degradation of the major NPP components (e.g. caused by unanticipated phenomena and by operating, maintenance or manufacturing errors) is one of the most important issues for plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling within acceptable limits the ageing degradation and wearout of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. IAEA-TECDOC-1119 documents ageing assessment and management practices for PWR Reactor Vessel Internals (RVIs) that were current at the time of its finalization in 1997-1998. Safety significant operating events have occurred since the finalization of the TECDOC, e.g. irradiation assisted stress corrosion cracking (IASCC) of baffle-former bolts, which threatened the integrity of the vessel internals. In addition, concern of fretting wear of control rod guide tubes has been raised in Japan. These events led to new ageing management actions by both NPP operators and regulators. Therefore it was recognized that IAEA-TECDOC-1119 should be updated by incorporating those new events and their countermeasures. The objective of this report is to update relevant sections of the existing IAEA-TECDOC- 1119 in order to provide current ageing management guidance for PWR RVIs to all involved in the operation and regulation of PWRs and thus to help ensure PWR safety in IAEA Member States throughout their entire service life

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

International Nuclear Information System (INIS)

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

2017-01-01

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

Development of Safety Review Guide for the Periodic Safety Review of Reactor Vessel Internals

International Nuclear Information System (INIS)

Park, Jeongsoon; Ko, Hanok; Kim, Seonjae; Jhung, Myungjo

2013-01-01

Aging management of the reactor vessel internals (RVIs) is one of the important issues for long-term operation of nuclear power plants (NPPs). Safety review on the assessment and management of the RVI aging is conducted through the process of a periodic safety review (PSR). The regulatory body should check that reactor facilities sustain safety functions in light of degradation due to aging and that the operator of a nuclear power reactor establishes and implements management program to deal with degradation due to aging in order to guarantee the safety functions and the safety margin as a result of PSR. KINS(Korea Institute of Nuclear Safety) has utilized safety review guides (SRG) which provide guidance to KINS staffs in performing safety reviews in order to assure the quality and uniformity of staff safety reviews. The KINS SRGs for the continued operation of pressurized water reactors (PWRs) published in 2006 contain areas of review regarding aging management of RVIs in chapter 2 (III.2.15, Appendix 2.0.1). However unlike the SRGs for the continued operation, KINS has not officially published the SRGs for the PSR of PWRs, but published them as a form of the research report. In addition to that, the report provides almost same review procedures for aging assessment and management of RVIs with the ones provided in the SRGs for the continued operation, it cannot provide review guidance specific to PSRs. Therefore, a PSR safety review guide should be developed for RVIs in PWRs. In this study, a draft PSR safety review guide for reactor vessel internals in PWRs is developed and provided. In this paper, a draft PSR safety review guide for reactor vessel internals (PSR SRG-RVIs) in PWRs is introduced and main contents of the draft are provided. However, since the PSR safety review guides for areas other than RVIs in the pressurized water reactors (PWRs) are expected to be developed in the near future, the draft PSR SRG-RVIs should be revisited to be compatible with

Nurses' Perceived Skills and Attitudes About Updated Safety Concepts: Impact on Medication Administration Errors and Practices.

Science.gov (United States)

Armstrong, Gail E; Dietrich, Mary; Norman, Linda; Barnsteiner, Jane; Mion, Lorraine

Approximately a quarter of medication errors in the hospital occur at the administration phase, which is solely under the purview of the bedside nurse. The purpose of this study was to assess bedside nurses' perceived skills and attitudes about updated safety concepts and examine their impact on medication administration errors and adherence to safe medication administration practices. Findings support the premise that medication administration errors result from an interplay among system-, unit-, and nurse-level factors.

Assessment and management of ageing of major nuclear power plant components important to safety: PWR pressure vessels. 2007 update

International Nuclear Information System (INIS)

2007-06-01

At present, there are over four hundred operational nuclear power plants (NPPs) in IAEA Member States. Operating experience has shown that effective control of the ageing degradation of the major NPP components (e.g. caused by unanticipated phenomena and by operating, maintenance or manufacturing errors) is one of the most important issues for plant safety and also plant life. Ageing in these NPPs must be therefore effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling within acceptable limits the ageing degradation and wear-out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. IAEA-TECDOC-1120 documented ageing assessment and management practices for pressurized water reactor (PWR) reactor pressure vessels (RPVs) that were current at the time of its finalization in 1997-1998. Safety significant operating events have occurred since the finalization of the TECDOC, e.g. primary water stress corrosion cracking (PWSCC) of Alloy 600 control rod drive mechanism (CRDM) penetrations and boric acid corrosion/wastage of RPV heads, which threatened the integrity of the RPV heads. These events led to new ageing management actions by both NPP operators and regulators. Therefore it was recognized that IAEA-TECDOC-1120 should be updated by incorporating those new events and their countermeasures. The objective of this report is to update IAEA-TECDOC-1120 in order to provide current ageing management guidance for PWR RPVs to all involved in the operation and regulation of PWRs and thus to help ensure PWR RPV integrity in IAEA Member States throughout their entire service life

Periodic safety review of the experimental fast reactor JOYO. Review of aging management

International Nuclear Information System (INIS)

Isozaki, Kazunori; Ogawa, To-ru; Nishino, Kazunari

2005-05-01

Periodic safety review (Review of the aging management) which consisted of ''Technical review on aging for the safety related structures, systems and components'' and ''Establishment a long term maintenance program'' was carried out up to April 2005. 1. Technical review on aging for the safety related structures, systems and components. It was technically confirmed to prevent the loss of function of the safety related structures, systems and components due to aging phenomena, which (1) irradiation damage, (2) corrosion, (3) abrasion and erosion, (4) thermal aging, (5) creep and fatigue, (6) Stress Corrosion Cracking, (7) insulation deterioration and (8) general deterioration, under the periodic monitoring or renewal of them. 2. Establishment of long term maintenance program. The long term maintenance during JFY2005 to 2014 were established based on the technical review on aging for the safety related structures, systems and components. It was evaluated that the inspection and renewal based on the long term maintenance program, in addition to the spontaneous inspection of the long term voluntary long-term inspection plan, could prevent the loss of function of the safety related structures, systems and components. (author)

Efficacy and safety of biological and targeted-synthetic DMARDs: a systematic literature review informing the 2016 update of the ASAS/EULAR recommendations for the management of axial spondyloarthritis

NARCIS (Netherlands)

Sepriano, Alexandre; Regel, Andrea; van der Heijde, Désirée; Braun, Jürgen; Baraliakos, Xenofon; Landewé, Robert; van den Bosch, Filip; Falzon, Louise; Ramiro, Sofia

2017-01-01

To update the evidence for the efficacy and safety of (b)biological and (ts)targeted-synthetic disease-modifying anti-rheumatic drugs (DMARDs) in patients with axial spondyloarthritis (axSpA) to inform the 2016 update of the Assessment of SpondyloArthritis international Society/European League

Overview of the periodic safety review of nuclear power plants as practised in India

International Nuclear Information System (INIS)

Jhamb, N.K.; Chande, S.K.

1997-01-01

In India, routine and periodic safety reviews of nuclear facilities are carried out through a multitiered hierarchy of committees at the plant level, the operating organization level and the regulatory body level. In 1993, it was decided by the Atomic Energy Regulatory Board (AERB, the regulatory body) that, as a policy, authorization for operation of nuclear power plants (NPPs) shall have a validity period of 5 years, after which this authorization will have to be renewed. NPPs have to carry out a self-assessment according to an established procedure, prepare a Safety Assessment Report for Renewal of Authorization (SARRA) and submit it to the AERB for review. The procedure defines the objectives of the report and gives guidelines on the required review of the self-assessment of the operational plant safety. The paper discusses the objectives, the elements of the SARRA review, the review process, the SARRA review carried out in 1993-1994, the basis for acceptability of continued plant operation, and the lessons learned for future periodic safety reviews in India and for exchange of operating experience feedback. (author)

DOE interpretations Guide to OSH standards. Update to the Guide

Energy Technology Data Exchange (ETDEWEB)

1994-03-31

Reflecting Secretary O`Leary`s focus on occupational safety and health, the Office of Occupational Safety is pleased to provide you with the latest update to the DOE Interpretations Guide to OSH Standards. This Guide was developed in cooperation with the Occupational Safety and Health Administration, which continued it`s support during this last revision by facilitating access to the interpretations found on the OSHA Computerized Information System (OCIS). This March 31, 1994 update contains 123 formal in letter written by OSHA. As a result of the unique requests received by the 1-800 Response Line, this update also contains 38 interpretations developed by DOE. This new occupational safety and health information adds still more important guidance to the four volume reference set that you presently have in your possession.

DOE interpretations Guide to OSH standards. Update to the Guide

Energy Technology Data Exchange (ETDEWEB)

1994-03-31

Reflecting Secretary O`Leary`s focus on occupational safety and health, the Office of Occupational Safety is pleased to provide you with the latest update to the DOE Interpretations Guide to OSH Standards. This Guide was developed in cooperation with the Occupational Safety and Health Administration, which continued its support during this last revision by facilitating access to the interpretations found on the OSHA Computerized Information System (OCIS). This March 31, 1994 update contains 123 formal interpretation letters written by OSHA. As a result of the unique requests received by the 1-800 Response Line, this update also contains 38 interpretations developed by DOE. This new occupational safety and health information adds still more important guidance to the four volume reference set that you presently have in your possession.

DOE interpretations Guide to OSH standards. Update to the Guide

Energy Technology Data Exchange (ETDEWEB)

1994-03-31

Reflecting Secretary O`Leary`s focus on occupational safety and health, the Office of Occupational Safety is pleased to provide you with the latest update to the DOE Interpretations Guide to OSH Standards. This Guide was developed in cooperation with the Occupational Safety and Health Administration, which continued its support during this last revision by facilitating access to the interpretations found on the OSHA Computerized Information System (OCIS). This March 31, 1994 update contains 123 formal interpretation letters written OSHA. As a result of the unique requests received by the 1-800 Response Line, this update also contains 38 interpretations developed by DOE. This new occupational safety and health information adds still more important guidance to the four volume reference set that you presently have in your possession.

49 CFR 385.333 - What happens at the end of the 18-month safety monitoring period?

Science.gov (United States)

2010-10-01

... SAFETY REGULATIONS SAFETY FITNESS PROCEDURES New Entrant Safety Assurance Program § 385.333 What happens at the end of the 18-month safety monitoring period? (a) If a safety audit has been performed within... the same basis as any other carrier. (d) If a safety audit or compliance review has not been performed...

Research on review technology for three key safety factors of periodic safety review (PSR) and its application to Qinshan Nuclear Power Plant

International Nuclear Information System (INIS)

Xu Shoulv; Yao Weida; Dou Yikang; Lin Shaoxuan; Cao Yenan; Zhou Quanfu; Zheng Jiong; Zhang Ming

2009-04-01

In 2001, after 10 years' operation, Qinshan Nuclear Power Plant (Q1) started to carry out periodic safety review (PSR) based on a nuclear safety guideline, Periodic Safety Review for Operational Nuclear Power Plants (HAF0312), issued by National Nuclear Safety Administration of China (NNSA). Entrusted by the owner of Q1, Shanghai Nuclear Engineering Research and Design Institute (SNERDI) implemented reviews of three key safety factors including safety analysis, equipment qualification and ageing. PSR was a challenging work in China at that time and through three years' research and practice, SNERDI summarized a systematic achievement for the review including review methodology, scoping, review contents and implementation steps, etc.. During the process of review for the three safety factors, totally 148 review reports and 341 recommendations for corrections were submitted to Q1. These reports and recommendations have provided guidance for correction actions as follow-up of PSR. This paper focuses on technical aspects to carry out PSR for the above-mentioned three safety factors, including review scoping, contents, methodology and main steps. The review technology and relevant experience can be taken for reference for other NPPs to carry out PSR. (authors)

Notification: FY 2017 Update of Proposed Key Management Challenges and Internal Control Weaknesses Confronting the U.S. Chemical Safety and Hazard Investigation Board

Science.gov (United States)

Jan 5, 2017. The EPA OIG is beginning work to update for fiscal year 2017 its list of proposed key management challenges and internal control weaknesses confronting the U.S. Chemical Safety and Hazard Investigation Board (CSB).

Periodic inspection for safety of CANDU heat transport piping systems

International Nuclear Information System (INIS)

Ellyin, F.

1979-10-01

Periodic inspection of heat transport and emergency core cooling piping systems is intended to maintain an adequate level of safety throughout the life of the plant, and to protect plant personnel and the public from the consequences of a failure and release of fission products. This report outlines a rational approach to the periodic inspection based on a fully probabilistic model. It demonstrates the methodology based on theoretical treatment and experimental data whereby the strength of a pressurized pipe or vessel containing a defect could be evaluated. It also shows how the extension of the defect at various lifetimes could be predicted. These relationships are prerequisite for the probabilistic formulation and analysis for the periodic inspection of piping systems

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.

Safety as experienced by patients themselves: a Finnish survey of the most recent period of care.

Science.gov (United States)

Sahlström, Merja; Partanen, Pirjo; Turunen, Hannele

2014-06-01

We examined patients' experiences of patient safety and participation in promoting safe care during their most recent care period. A survey of patients (N = 175) revealed that treatment, medication, and device safety were mostly experienced as very good or excellent, but responses varied by age and experience. Patients ages 66-75 were most critical of treatment and medication safety. Device safety was rated the worst aspect of safety. Twenty percent of respondents had experienced errors at some time during their care. Patients who had experienced errors and those who were treated at inpatient wards versus a day surgery unit were most critical towards patient participation. Open and transparent error management involving patients is needed to promote treatment, medication, and especially device safety. © 2014 Wiley Periodicals, Inc.

Project SAFE. Update of the SFR-1 safety assessment. Phase 1. Appendix A4: Far-field

International Nuclear Information System (INIS)

Follin, S.; Andersson, Johan; Holmen, J.; Axelsson, C.L.

1998-01-01

This appendix has identified potential needs for updated hydrogeological modelling of the SFR in connection to the planned update of the performance assessment of the SFR within the framework of the SAFE-project. The objectives of such updated modelling should be to present a credible representation of the hydrogeological system, to explore effects of seals and repository extensions and to provide input to the release and transport calculations of the assessment. The last objective has led to the conclusion that an important focus of the modelling should be to determine the flow through the vaults under different conditions as this flow appear to be a very important quantity in the radionuclide release calculations. The suggested modelling should use relevant data and apply modern modelling tools and techniques, but should be geared towards the objectives. For this reasons it is suggested to apply a set of complementary and sometimes nested approaches, where each model approach is set up in order to address a specific set of questions. Answering these questions would motivate simplifications made in subsequent steps of the modelling. To the extent possible the models should be compared with existing data on flow and Baltic water breakthrough. However, in making such comparisons the accuracy of the measurements and the precision of the models need to be considered. A one-to-one match cannot be expected. It appears that careful geochemical evaluation of the site would only be necessary if more credit is placed on migration in the geosphere. If such an evaluation is considered it should be co-ordinated with the regional groundwater modelling. The issue of gas production should be reconsidered in a scenario and process analysis of SFR. However, given the strong conclusions already made it appears that gas migration in the rock will still remain as a minor issue. The major assumptions going into the analysis of the near-field in the final safety report and the deepened

Integrated safety assessment report, Haddam Neck Plant (Docket No. 50-213): Integrated Safety Assessment Program: Draft report

International Nuclear Information System (INIS)

1987-07-01

The integrated assessment is conducted on a plant-specific basis to evaluate all licensing actions, licensee initiated plant improvements and selected unresolved generic/safety issues to establish implementation schedules for each item. Procedures allow for a periodic updating of the schedules to account for licensing issues that arise in the future. The Haddam Neck Plant is one of two plants being reviewed under the pilot program. This report indicates how 82 topics selected for review were addressed, and presents the staff's recommendations regarding the corrective actions to resolve the 82 topics and other actions to enhance plant safety. 135 refs., 4 figs., 5 tabs

RADWASS update. Radioactive Waste Safety Standards Programme

International Nuclear Information System (INIS)

Delattre, D.

2000-01-01

By the late 1980s, the issue of radioactive wastes and their management was becoming increasingly politically important. The IAEA responded by establishing a high profile family of safety standards, the Radioactive Waste Safety Standards (RADWASS). By this means, the IAEA intended to draw attention to the fact that well-established procedures for the safe management of radioactive wastes already were in place. The programme was intended to establish an ordered structure for safety documents on waste management and to ensure comprehensive coverage of all relevant subject areas. RADWASS documents are categorized under four subject areas - discharges, predisposal, disposal, and environmental restoration. The programme is overseen through a formalized review and approval mechanism that was established in 1996 for all safety standards activities. The Waste Safety Standards Committee (WASSC) is a standing body of senior regulatory officials with technical expertise in radioactive waste safety. To date, three Safety Requirements and seven Safety Guides have been issued

Reliability data update using condition monitoring and prognostics in probabilistic safety assessment

Directory of Open Access Journals (Sweden)

Hyeonmin Kim

2015-03-01

Full Text Available Probabilistic safety assessment (PSA has had a significant role in quantitative decision-making by finding design and operational vulnerabilities and evaluating cost-benefit in improving such weak points. In particular, it has been widely used as the core methodology for risk-informed applications (RIAs. Even though the nature of PSA seeks realistic results, there are still “conservative” aspects. One of the sources for the conservatism is the assumptions of safety analysis and the estimation of failure frequency. Surveillance, diagnosis, and prognosis (SDP, utilizing massive databases and information technology, is worth highlighting in terms of its capability for alleviating the conservatism in conventional PSA. This article provides enabling techniques to solidify a method to provide time- and condition-dependent risks by integrating a conventional PSA model with condition monitoring and prognostics techniques. We will discuss how to integrate the results with frequency of initiating events (IEs and probability of basic events (BEs. Two illustrative examples will be introduced: (1 how the failure probability of a passive system can be evaluated under different plant conditions and (2 how the IE frequency for a steam generator tube rupture (SGTR can be updated in terms of operating time. We expect that the proposed model can take a role of annunciator to show the variation of core damage frequency (CDF depending on operational conditions.

Reliability data update using condition monitoring and prognostics in probabilistic safety assessment

Energy Technology Data Exchange (ETDEWEB)

Kim, Hyeon Min; Lee, Sang Hwan; Park, Jun Seok; Kim, Hyung Dae; Chang, Yoon Suk; Heo, Gyun Young [Dept. of Nuclear Engineering, Kyung Hee University, Yongin (Korea, Republic of)

2015-03-15

Probabilistic safety assessment (PSA) has had a significant role in quantitative decision making by finding design and operational vulnerabilities and evaluating cost-benefit in improving such weak points. In particular, it has been widely used as the core methodology for risk-informed applications (RIAs). Even though the nature of PSA seeks realistic results, there are still 'conservative' aspects. One of the sources for the conservatism is the assumptions of safety analysis and the estimation of failure frequency. Surveillance, diagnosis, and prognosis (SDP), utilizing massive databases and information technology, is worth highlighting in terms of its capability for alleviating the conservatism in conventional PSA. This article provides enabling techniques to solidify a method to provide time and condition-dependent risks by integrating a conventional PSA model with condition monitoring and prognostics techniques. We will discuss how to integrate the results with frequency of initiating events (IEs) and probability of basic events (BEs). Two illustrative examples will be introduced: (1) how the failure probability of a passive system can be evaluated under different plant conditions and (2) how the IE frequency for a steam generator tube rupture (SGTR) can be updated in terms of operating time. We expect that the proposed model can take a role of annunciator to show the variation of core damage frequency (CDF) depending on operational conditions.

Practice Hospital Bed Safety

Science.gov (United States)

... Home For Consumers Consumer Updates Practice Hospital Bed Safety Share Tweet Linkedin Pin it More sharing options ... It depends on the complexity of the bed." Safety Tips CDRH offers the following safety tips for ...

Circular Updates

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — Circular Updates are periodic sequentially numbered instructions to debriefing staff and observers informing them of changes or additions to scientific and specimen...

Efficacy and safety of fentanyl buccal for cancer pain management by administration through a soluble film: an update

International Nuclear Information System (INIS)

Delgado-Guay, Marvin Omar

2010-01-01

More than half of patients receiving prescription medicine for cancer pain have been reported to experience inadequate pain relief or breakthrough pain. Buccal administration can deliver lipophilic opioids rapidly to the systemic circulation through the buccal mucosa, limiting gastrointestinal motility and first-pass metabolism. This review updates the safety and efficacy of fentanyl buccal soluble film (FBSF) in patients with cancer pain. Literature was identified through searches of Medline (PubMed). Search terms included combinations of the following: cancer pain, fentanyl, fentanyl buccal soluble film, pharmacology, kinetics, safety, efficacy and toxicity. FBSF is an oral transmucosal form of fentanyl citrate developed as a treatment of breakthrough pain in opioid-tolerant patients with cancer. Studies have shown that it is well tolerated in the oral cavity, with adequate bioavailability and safety in cancer patients. Further studies are warranted to evaluate, in comparison with other short-acting opioids, its efficacy in the management of breakthrough cancer pain, its addictive potential and its economic impact in cancer patients

76 FR 28194 - Proposed FOIA Fee Schedule Update

Science.gov (United States)

2011-05-16

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD 10 CFR Part 1703 Proposed FOIA Fee Schedule Update AGENCY... publishing its proposed Freedom of Information Act (FOIA) Fee Schedule Update and solicits comments from... on the proposed fee schedule should be mailed or delivered to the Office of the General Counsel...

75 FR 27228 - Proposed FOIA Fee Schedule Update

Science.gov (United States)

2010-05-14

... DEFENSE NUCLEAR FACILITIES SAFETY BOARD 10 CFR Part 1703 Proposed FOIA Fee Schedule Update AGENCY... publishing its proposed Freedom of Information Act (FOIA) Fee Schedule Update and solicits comments from... on the proposed fee schedule should be mailed or delivered to the Office of the General Counsel...

Periodic safety review of operational nuclear power plants. A publication within the NUSS programme

International Nuclear Information System (INIS)

1994-01-01

This Safety Guide which supplements the IAEA Safety Fundamentals: The Safety of Nuclear Installations and the Code on the Safety of Nuclear Power Plants: Operation, forms part of the Agency's programme, referred to as the NUSS programme, for establishing Codes and Guides relating to nuclear power plants. A list of NUSS publications is given at the end of this book. This Guide was drafted on the basis of a systematic review approach that was endorsed by the IAEA Conference on the Safety of Nuclear Power: Strategy for the Future. The purpose of this Safety Guide is to provide guidance on the conduct of Periodic Safety Reviews (PSRs) for an operational nuclear power plant. The Guide is directed at both owners/operators and regulators. This Safety Guide deals with the PSR of an operational nuclear power plant. A PSR is a comprehensive safety review addressing all important aspects of safety, carried out at regular intervals. 22 refs, 4 figs

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

International Nuclear Information System (INIS)

Hirano, Masashi; Narumiya, Yoshiyuki

2010-01-01

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

76 FR 40648 - Safety Enhancements Part 139, Certification of Airports; Reopening of Comment Period

Science.gov (United States)

2011-07-11

... that was published on February 1, 2011. In that document, the FAA proposed several safety enhancements...-0247; Notice No. 11-01] RIN 2120-AJ70 Safety Enhancements Part 139, Certification of Airports... comment period for the NPRM published on February 1, 2011 (76 FR 5510) and reopened (76 FR 20570) April 13...

Safety and efficacy of vernakalant for acute cardioversion of atrial fibrillation: an update

Directory of Open Access Journals (Sweden)

Dobrev D

2013-04-01

Full Text Available Yukiomi Tsuji,1 Dobromir Dobrev1–3 1Institute of Pharmacology, Faculty of Medicine, University Duisburg-Essen, Essen, 2Division of Experimental Cardiology, Medical Faculty Mannheim, Heidelberg University, Mannheim, 3Deutsches Zentrum für Herz-Kreislauf-Forshcung [German Center for Cardiovascular Research], partner site Heidelberg/Mannheim, Mannheim, Germany Abstract: Intravenous vernakalant has recently been approved in Europe as an atrial-selective antiarrhythmic drug for the conversion of recent-onset atrial fibrillation (AF. It inhibits atrial-selective K+ currents (IK,ACh and IKur and causes rate-dependent atrial-predominant Na+ channel block, with only a small inhibitory effect on the rapid delayed rectifier K+ current (IKr in the ventricle. Due to its atrial-selective properties, vernakalant prolongs the effective refractory period of the atria with minimal effects on the ventricles, being associated with a low proarrhythmic risk for torsades de pointes arrhythmias. Five pivotal clinical trials consistently demonstrated that vernakalant rapidly terminates AF with stable maintenance of sinus rhythm for up to 24 hours. A head-to-head comparative trial showed that the 90-minute conversion rate of vernakalant was substantially higher than that of amiodarone. Initially, a longer-acting oral formulation of vernakalant was shown to be effective and safe in preventing AF recurrence after cardioversion in a Phase IIb study. However, the clinical studies testing oral vernakalant for maintenance of sinus rhythm after AF cardioversion were prematurely halted for undisclosed reasons. This review article provides an update on the safety and efficacy of intravenous vernakalant for the rapid cardioversion of AF. Keywords: atrial fibrillation, antiarrhythmic drug, atrial-selective K+ currents, Na+ channel block, ventricles

77 FR 33980 - Proposed FOIA Fee Schedule Update

Science.gov (United States)

2012-06-08

... 1703 Proposed FOIA Fee Schedule Update AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Notice... the Board's proposed FOIA Fee Schedule Update published in the Federal Register of June 1, 2012. The...: The FOIA requires each Federal agency covered by the Act to specify a schedule of fees applicable to...

About the necessity to update the Radiological safety and protection regulations of the National Institute of Nuclear Research (ININ)

International Nuclear Information System (INIS)

Alvarez R, J.T.

1997-01-01

It is argued the necessity to update the Radiological safety and Protection regulations (Review 3) of ININ, with the purpose that it implements the ICRU operative magnitudes system. Such a system used with radiological protection purposes. The objective of this system is to do an estimation of the effective equivalent dose H E and/or the Effective dose E, proposed in the ICRP 26 and ICRU 60 dose limits systems respectively. (Author)

Biological effects of electromagnetic fields and recently updated safety guidelines for strong static magnetic fields

International Nuclear Information System (INIS)

Yamaguchi-Sekino, Sachiko; Sekino, Masaki; Ueno, Shoogo

2011-01-01

Humans are exposed daily to artificial and naturally occurring magnetic fields that originate from many different sources. We review recent studies that examine the biological effects of and medical applications involving electromagnetic fields, review the properties of static and pulsed electromagnetic fields that affect biological systems, describe the use of a pulsed electromagnetic field in combination with an anticancer agent as an example of a medical application that incorporates an electromagnetic field, and discuss the recently updated safety guidelines for static electromagnetic fields. The most notable modifications to the 2009 International Commission on Non-Ionizing Radiation Protection guidelines are the increased exposure limits, especially for those who work with or near electromagnetic fields (occupational exposure limits). The recommended increases in exposure were determined using recent scientific evidence obtained from animal and human studies. Several studies since the 1994 publication of the guidelines have examined the effects on humans after exposure to high static electromagnetic fields (up to 9.4 tesla), but additional research is needed to ascertain further the safety of strong electromagnetic fields. (author)

Environmental Regulatory Update Table, January/February 1995

Energy Technology Data Exchange (ETDEWEB)

Houlberg, L.M.; Hawkins, G.T.; Bock, R.E.; Mayer, S.J.; Salk, M.S.

1995-03-01

The Environmental Regulatory Update Table provides information on regulatory initiatives impacting environmental, health, and safety management responsibilities. the table is updated bi-monthly with information from the Federal Register and other sources, including direct contact with regulatory agencies. Each table entry provides a chronological record of the rulemaking process for that initiative with an abstract and a projection of further action.

Environmental Regulatory Update Table, January/February 1995

International Nuclear Information System (INIS)

Houlberg, L.M.; Hawkins, G.T.; Bock, R.E.; Mayer, S.J.; Salk, M.S.

1995-03-01

The Environmental Regulatory Update Table provides information on regulatory initiatives impacting environmental, health, and safety management responsibilities. the table is updated bi-monthly with information from the Federal Register and other sources, including direct contact with regulatory agencies. Each table entry provides a chronological record of the rulemaking process for that initiative with an abstract and a projection of further action

An approach for Periodic Safety Review (PSR) of units 5 and 6 of Kozloduy NPP

International Nuclear Information System (INIS)

Kichev, Emil

2014-01-01

Periodic Safety Reviews (PSR) is complementary to the routine and special safety reviews and does not replaced them. It determines the level of compliance with current safety requirements and covers all safety aspects of NPP operation and all equipment (SSCs) on site. Three levels of importance are defined for the documents in PSR (towards higher conservatism): Bulgarian documents; IAEA documents; Documents of manufactures and suppliers of the equipment (SSCs). The scope and activities consists of four stages and includes 14 safety factors (SF). Cooperation with external companies and organizations in areas with proved experience is used.

Updating Rhode Island's strategic highway safety plan (SHSP).

Science.gov (United States)

2012-05-01

This report summarizes the peer exchange sponsored by the Rhode Island : Department of Transportation (RIDOT) that focused on Rhode Islands SHSP : update. : Rhode Islands goals for the peer exchange included learning from other States : expe...

Fifth national report of Brazil for the nuclear safety convention

International Nuclear Information System (INIS)

2010-01-01

This Fifth National Report is a new update to include relevant information for the period of 2007/2009. This document represents the national report prepared as a fulfillment of the Brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations

Twenty-fifth water reactor safety information meeting: Proceedings. Volume 1: Plenary sessions; Pressure vessel research; BWR strainer blockage and other generic safety issues; Environmentally assisted degradation of LWR components; Update on severe accident code improvements and applications

Energy Technology Data Exchange (ETDEWEB)

Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

1998-03-01

This three-volume report contains papers presented at the conference. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Japan, Norway, and Russia. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume contains the following information: (1) plenary sessions; (2) pressure vessel research; (3) BWR strainer blockage and other generic safety issues; (4) environmentally assisted degradation of LWR components; and (5) update on severe accident code improvements and applications. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database.

Twenty-fifth water reactor safety information meeting: Proceedings. Volume 1: Plenary sessions; Pressure vessel research; BWR strainer blockage and other generic safety issues; Environmentally assisted degradation of LWR components; Update on severe accident code improvements and applications

International Nuclear Information System (INIS)

Monteleone, S.

1998-03-01

This three-volume report contains papers presented at the conference. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Japan, Norway, and Russia. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume contains the following information: (1) plenary sessions; (2) pressure vessel research; (3) BWR strainer blockage and other generic safety issues; (4) environmentally assisted degradation of LWR components; and (5) update on severe accident code improvements and applications. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database

Phase 9 update (1987) report for the Energy Economic Data Base Program EEDB-IX

International Nuclear Information System (INIS)

1988-07-01

This document is a review of the 1987 update of detailed reference powerplant cost estimates. This distribution is the latest in a series published since 1978. The overall program purpose is to provide periodically updated, detailed base construction cost estimates for large nuclear electric operating plants. These data, which are representative of current US powerplant construction cost experience, are a useful contribution to program planning by the Office of the Assistant Secretary for Nuclear Energy. The ninth update includes three new models as a basis for projecting future costs of both small and large nuclear power plants and examining the potential for cost reduction by incorporation of improved and advanced design features. The models designated as improved include the advantages of modular construction and standardized approach to design and construction. The advanced model includes many of the features of the improved data models as well as application of passive or near-passive safety systems and design simplification

Technologies and mechanisms for safety control of ready-to-eat muscle foods: an updated review.

Science.gov (United States)

Jiang, Jiang; Xiong, Youling L

2015-01-01

Ready-to-eat (RTE) muscle foods refer to a general category of meat and poultry products that are fully cooked and consumable without reheating. These products, including whole and sliced pork, beef, turkey, chicken, and variety of meats, in the forms of ham, roast, rolls, sausage, and frankfurter, are widely available in the delicatessen section of retail stores or various food service outlets. However, difficulties in avoidance of contamination by foodborne pathogens, notably Listeria monocytogenes, during product postlethality repackaging render RTE meats labile to outbreaks. Accordingly, the USDA-FSIS has established processing guidelines and regulations, which are constantly updated, to minimize foodborne pathogens in RTE products. Technologies that complement good manufacturing practice have been developed to control RTE meat safety. Among them, various antimicrobial product formulations, postpackaging pasteurization (thermal and nonthermal), and antimicrobial packaging are being used. Through these efforts, outbreaks linked to RTE meat consumption have substantially reduced in recent years. However, the pervasive and virulent nature of L. monocytogenes and the possible presence of other cold-tolerant pathogens entail continuing developments of new intervention technologies. This review updates existing and emerging physical and chemical methods and their mode of action to inactivate or inhibit threatening microorganisms in RTE muscle foods.

Second-generation speed limit map updating applications

DEFF Research Database (Denmark)

Tradisauskas, Nerius; Agerholm, Niels; Juhl, Jens

2011-01-01

Intelligent Speed Adaptation is an Intelligent Transport System developed to significantly improve road safety in helping car drivers maintain appropriate driving behaviour. The system works in connection with the speed limits on the road network. It is thus essential to keep the speed limit map...... used in the Intelligent Speed Adaptation scheme updated. The traditional method of updating speed limit maps on the basis of long time interval observations needed to be replaced by a more efficient speed limit updating tool. In a Danish Intelligent Speed Adaptation trial a web-based tool was therefore...... for map updating should preferably be made on the basis of a commercial map provider, 2 such as Google Maps and that the real challenge is to oblige road authorities to carry out updates....

The second periodic safety review report of Tokai Reprocessing Plant [JAEA-Technology--2016-007-PT1

International Nuclear Information System (INIS)

Shirai, Nobutoshi; Miura, Yasushi; Tachibana, Ikuya; Omori, Satoru; Wake, Junichi; Fukuda, Kazuhito; Nakano, Takafumi; Nagasato, Yoshihiko

2016-07-01

The periodic safety review of Tokai Reprocessing Plant (TRP) is an activity to confirm the application of the safety activity implementation and to give effective additional measures for the facility safety and the improvement of its reliability. We implemented 4 items as follows; (1) evaluation of safety activity implementation, (2) evaluation of status of safety activities reflecting the latest technical knowledges, (3) technical evaluation about aging degradation, and (4) planning measures about a 10-years-plan that the operator shall implement in order to keep the facility condition. We summarized this report as the result of research and evaluation of above 4 items as the second periodic safety review at TRP. About (1), we researched about the 8 items that are QA activities, operation management, maintenance management, etc. We confirmed the result that we are adequately expanding its safety activities by preparing the necessary documents and schemes, and so on. About (2), we researched them in view point of safety research results and technology development results and confirmed that we reflect latest knowledges into our facility and make efforts for improvement of safety and reliability. About (3), we can keep the safety of the facilities important to safety and the sea discharge line, under assumption of the present maintenance till the next aging evaluation, because no 'focuses for aging degradation' exist which we cannot deny the gap between the initial prediction and actual condition, by measurements and technical view. About (4), by the technical results of aging degradation evaluation, we found no additional safety plans into maintenance strategies. (author)

National Nuclear Safety Report 2001. Convention on Nuclear Safety

International Nuclear Information System (INIS)

2001-01-01

The First National Nuclear Safety Report was presented at the first review meeting of the Nuclear Safety Convention. At that time it was concluded that Argentina met the obligations of the Convention. This second National Nuclear Safety Report is an updated report which includes all safety aspects of the Argentinian nuclear power plants and the measures taken to enhance the safety of the plants. The present report also takes into account the observations and discussions maintained during the first review meeting. The conclusion made in the first review meeting about the compliance by Argentina of the obligations of the Convention are included as Annex 1. In general, the information contained in this Report has been updated since March 31, 1998 to March 31, 2001. Those aspects that remain unchanged were not addressed in this second report with the objective of avoiding repetitions and in order to carry out a detailed analysis considering article by article. As a result of the above mentioned detailed analysis of all the Articles, it can be stated that the country fulfils all the obligations imposed by the Nuclear Safety Convention

National nuclear safety report 2004. Convention on nuclear safety

International Nuclear Information System (INIS)

2004-01-01

The second National Nuclear Safety Report was presented at the second review meeting of the Nuclear Safety Convention. At that time it was concluded that Argentina met the obligations of the Convention. This third National Nuclear Safety Report is an updated report which includes all safety aspects of the Argentinian nuclear power plants and the measures taken to enhance the safety of the plants. The present report also takes into account the observations and discussions maintained during the second review meeting. The conclusion made in the first review meeting about the compliance by Argentina of the obligations of the Convention are included as Annex I and those belonging to the second review meeting are included as Annex II. In general, the information contained in this Report has been updated since March 31, 2001 to April 30, 2004. Those aspects that remain unchanged were not addressed in this third report. As a result of the detailed analysis of all the Articles, it can be stated that the country fulfils all the obligations imposed by the Nuclear Safety Convention. The questions and answers originated at the Second Review Meeting are included as Annex III

77 FR 32433 - Proposed FOIA Fee Schedule Update

Science.gov (United States)

2012-06-01

... 1703 Proposed FOIA Fee Schedule Update AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Notice... Defense Nuclear Facilities Safety Board is publishing its proposed Freedom of Information Act (FOIA) Fee.... on or before July 2, 2012. ADDRESSES: Comments on the proposed fee schedule should be mailed or...

Status of safety analysis reports

Energy Technology Data Exchange (ETDEWEB)

Cserhati, A

1999-06-01

The safety regulation connected to both of the Atomic Acts from 1980 and 1996 requires preparation of the Preliminary Safety Analysis Report (PSAR) as well as Final SAR (FSAR). In this respect the licensing procedure for the construction and commissioning of Paks NPP did not formally deviate from the standards applied in developed countries; this is particularly true if comparison is made with the standards applied for commissioning NPPs in the second half of the seventies. By the time the overall development of internationally accepted safety standards and some existing deficiencies of earlier SAR made necessary a general reassessment of the plant safety (AGNES project). The carried out PSR for Paks-1 and 2 also added a valuable contribution to the SAR content, however a formal update of SAR is not made yet. A Hungarian nuclear authority decree from 1997 obligates the licensee to prepare and submit a major upgrade of FSAR until the mid of 2000, after finishing the PSR for Paks-3 and 4. From this date a periodic update of FSAR is required every year. The operational license renewal affects only the PSR but not the FSAR updating. The new Nuclear Safety Code outlines the contents of PSAR and FSAR, based on US NRC Reg. Guide 1. 70. Rev. 3. Hungary by now can fulfill the upgrading of SAR without major external technical or financial help. The AGNES project covered the safety analysis chapters of SAR. It was financed mainly by the country. In the project there have been involved in limited cases as performers the VTT (Finland), Belgatom (Belgium), GRS (Germany), etc., the IVO (Finland) fulfilled tasks of an independent reviewer for safety analysis. The AGNES had certain interconnection with the similar IAEA RER safety reassessment project for WWER-440/213. The PSR for Paks-1 and 2 have been carried out by the Paks staff from the resources of the plant. During the evaluation of several parts of Paks-3 and 4 PSR documentation the authority intends to use certain

Status of safety analysis reports

International Nuclear Information System (INIS)

Cserhati, A.

1999-01-01

The safety regulation connected to both of the Atomic Acts from 1980 and 1996 requires preparation of the Preliminary Safety Analysis Report (PSAR) as well as Final SAR (FSAR). In this respect the licensing procedure for the construction and commissioning of Paks NPP did not formally deviate from the standards applied in developed countries; this is particularly true if comparison is made with the standards applied for commissioning NPPs in the second half of the seventies. By the time the overall development of internationally accepted safety standards and some existing deficiencies of earlier SAR made necessary a general reassessment of the plant safety (AGNES project). The carried out PSR for Paks-1 and 2 also added a valuable contribution to the SAR content, however a formal update of SAR is not made yet. A Hungarian nuclear authority decree from 1997 obligates the licensee to prepare and submit a major upgrade of FSAR until the mid of 2000, after finishing the PSR for Paks-3 and 4. From this date a periodic update of FSAR is required every year. The operational license renewal affects only the PSR but not the FSAR updating. The new Nuclear Safety Code outlines the contents of PSAR and FSAR, based on US NRC Reg. Guide 1. 70. Rev. 3. Hungary by now can fulfill the upgrading of SAR without major external technical or financial help. The AGNES project covered the safety analysis chapters of SAR. It was financed mainly by the country. In the project there have been involved in limited cases as performers the VTT (Finland), Belgatom (Belgium), GRS (Germany), etc., the IVO (Finland) fulfilled tasks of an independent reviewer for safety analysis. The AGNES had certain interconnection with the similar IAEA RER safety reassessment project for WWER-440/213. The PSR for Paks-1 and 2 have been carried out by the Paks staff from the resources of the plant. During the evaluation of several parts of Paks-3 and 4 PSR documentation the authority intends to use certain

Selection of detailed items for periodic safety review on PWR radwaste management system

Energy Technology Data Exchange (ETDEWEB)

Sung, K. B.; Ahn, Y. S.; Park, Y. S.; Kim, S. H.; Kim, J. T. [Korea Hydric and Nuclear Power Company, Taejon (Korea, Republic of)

2003-10-01

Selection of detailed-items for Periodic Safety Review on PWR radwaste management system, the main component could be faithfully clarified according to the purpose of establishment on each system and basic purpose. It is proper to select detailed-items those of radioactivities in the reactor coolant activity levels and the released volume of liquid and gaseous radioactive material on safety performance. It's also proper to select solid radwaste production quantities as detailed-item that it would be predict the next ten years trends after PSR.

Cassini Spacecraft Uncertainty Analysis Data and Methodology Review and Update/Volume 1: Updated Parameter Uncertainty Models for the Consequence Analysis

Energy Technology Data Exchange (ETDEWEB)

WHEELER, TIMOTHY A.; WYSS, GREGORY D.; HARPER, FREDERICK T.

2000-11-01

Uncertainty distributions for specific parameters of the Cassini General Purpose Heat Source Radioisotope Thermoelectric Generator (GPHS-RTG) Final Safety Analysis Report consequence risk analysis were revised and updated. The revisions and updates were done for all consequence parameters for which relevant information exists from the joint project on Probabilistic Accident Consequence Uncertainty Analysis by the United States Nuclear Regulatory Commission and the Commission of European Communities.

Re-assessment of seismic loads in conjunction with periodic safety review

International Nuclear Information System (INIS)

Jonczyk, Josef

2002-01-01

The objective of this paper is the fundamental consideration of a safeguard-aim-oriented approach for use in the re-assessment of seismic events with regard to the periodic safety review (PSR) of nuclear power plants (NPP). The re-assessment aspects of site-specific design earthquakes (DEQ), specially the procedure for seismic hazard analysis, will not, however, be considered in detail here. The proposed assessment concept clearly presents a general approach for safety assessments. The approach is based on a successive screening review of components that are considered sufficiently earthquake-resistant. In this respect, the principle of maximum practical application of the design documentation has been considered in the re-assessment process. On the other hand, the safeguard-aim-oriented evaluation will also be applied with regard to whether the requirements of the safety regulations are fulfilled with respect to the safety goals. The review in conjunction with PSR does not, however, attempt to perform this under all technical aspects. Moreover, it is possible to make extensive use of experimental knowledge and engineering judgement with regard to the structural capacity behaviour in case of a seismic event. Compared with design procedures, however, this proposed approach differs from the one applied in licensing procedures, in which such assessment freedom will not usually be exhausted. (author)

How update schemes influence crowd simulations

International Nuclear Information System (INIS)

Seitz, Michael J; Köster, Gerta

2014-01-01

Time discretization is a key modeling aspect of dynamic computer simulations. In current pedestrian motion models based on discrete events, e.g. cellular automata and the Optimal Steps Model, fixed-order sequential updates and shuffle updates are prevalent. We propose to use event-driven updates that process events in the order they occur, and thus better match natural movement. In addition, we present a parallel update with collision detection and resolution for situations where computational speed is crucial. Two simulation studies serve to demonstrate the practical impact of the choice of update scheme. Not only do density-speed relations differ, but there is a statistically significant effect on evacuation times. Fixed-order sequential and random shuffle updates with a short update period come close to event-driven updates. The parallel update scheme overestimates evacuation times. All schemes can be employed for arbitrary simulation models with discrete events, such as car traffic or animal behavior. (paper)

Fourth national report of Brazil for the nuclear safety convention. Sep. 2007

International Nuclear Information System (INIS)

2007-09-01

This Fourth National Report of Brazil is a new update to include relevant information of the period of 2004-2007. This document represents the national report prepared as a fulfillment of the brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations

Fourth national report of Brazil for the nuclear safety convention. Sep. 2007

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-09-15

This Fourth National Report of Brazil is a new update to include relevant information of the period of 2004-2007. This document represents the national report prepared as a fulfillment of the brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations

Efficacy and safety of fentanyl buccal for cancer pain management by administration through a soluble film: an update

Directory of Open Access Journals (Sweden)

Marvin Omar Delgado-Guay

2010-11-01

Full Text Available Marvin Omar Delgado-GuayDivision of Geriatrics and Palliative Medicine, The University of Texas, Medical School at Houston, Houston, TX, USAAbstract: More than half of patients receiving prescription medicine for cancer pain have been reported to experience inadequate pain relief or breakthrough pain. Buccal administration can deliver lipophilic opioids rapidly to the systemic circulation through the buccal mucosa, limiting gastrointestinal motility and first-pass metabolism. This review updates the safety and efficacy of fentanyl buccal soluble film (FBSF in patients with cancer pain. Literature was identified through searches of Medline (PubMed. Search terms included combinations of the following: cancer pain, fentanyl, fentanyl buccal soluble film, pharmacology, kinetics, safety, efficacy and toxicity. FBSF is an oral transmucosal form of fentanyl citrate developed as a treatment of breakthrough pain in opioid-tolerant patients with cancer. Studies have shown that it is well tolerated in the oral cavity, with adequate bioavailability and safety in cancer patients. Further studies are warranted to evaluate, in comparison with other short-acting opioids, its efficacy in the management of breakthrough cancer pain, its addictive potential and its economic impact in cancer patients.Keywords: fentanyl buccal soluble film, cancer pain

National nuclear safety report 2005. Convention on nuclear safety

International Nuclear Information System (INIS)

2006-01-01

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

Development and Psychometric Analysis of a Nurses' Attitudes and Skills Safety Scale: Initial Results.

Science.gov (United States)

Armstrong, Gail E; Dietrich, Mary; Norman, Linda; Barnsteiner, Jane; Mion, Lorraine

Health care organizations have incorporated updated safety principles in the analysis of errors and in norms and standards. Yet no research exists that assesses bedside nurses' perceived skills or attitudes toward updated safety concepts. The aims of this study were to develop a scale assessing nurses' perceived skills and attitudes toward updated safety concepts, determine content validity, and examine internal consistency of the scale and subscales. Understanding nurses' perceived skills and attitudes about safety concepts can be used in targeting strategies to enhance their safety practices.

[Safety monitoring of cell-based medicinal products (CBMPs)].

Science.gov (United States)

Funk, Markus B; Frech, Marion; Spranger, Robert; Keller-Stanislawski, Brigitte

2015-11-01

Cell-based medicinal products (CBMPs), a category of advanced-therapy medicinal products (ATMPs), are authorised for the European market by the European Commission by means of the centralized marketing authorisation. By conforming to the German Medicinal Products Act (Sec. 4b AMG), national authorisation can be granted by the Paul-Ehrlich-Institut in Germany exclusively for ATMPs not based on a routine manufacturing procedure. In both procedures, quality, efficacy, and safety are evaluated and the risk-benefit balance is assessed. For the centralised procedure, mainly controlled clinical trial data must be submitted, whereas the requirements for national procedures could be modified corresponding to the stage of development of the ATMP. After marketing authorization, the marketing authorization/license holder is obligated to report all serious adverse reactions to the competent authority and to provide periodic safety update reports. If necessary, post-authorization safety studies could be imposed. On the basis of these regulatory measures, the safety of advanced therapies can be monitored and improved.

a Bottom-Up Geosptial Data Update Mechanism for Spatial Data Infrastructure Updating

Science.gov (United States)

Tian, W.; Zhu, X.; Liu, Y.

2012-08-01

Currently, the top-down spatial data update mechanism has made a big progress and it is wildly applied in many SDI (spatial data infrastructure). However, this mechanism still has some issues. For example, the update schedule is limited by the professional department's project, usually which is too long for the end-user; the data form collection to public cost too much time and energy for professional department; the details of geospatial information does not provide sufficient attribute, etc. Thus, how to deal with the problems has become the effective shortcut. Emerging Internet technology, 3S technique and geographic information knowledge which is popular in the public promote the booming development of geoscience in volunteered geospatial information. Volunteered geospatial information is the current "hotspot", which attracts many researchers to study its data quality and credibility, accuracy, sustainability, social benefit, application and so on. In addition to this, a few scholars also pay attention to the value of VGI to support the SDI updating. And on that basis, this paper presents a bottom-up update mechanism form VGI to SDI, which includes the processes of match homonymous elements between VGI and SDI vector data , change data detection, SDI spatial database update and new data product publication to end-users. Then, the proposed updating cycle is deeply discussed about the feasibility of which can detect the changed elements in time and shorten the update period, provide more accurate geometry and attribute data for spatial data infrastructure and support update propagation.

Efforts to update firefighter safety zone guidelines

Science.gov (United States)

Bret Butler

2009-01-01

One of the most critical decisions made on wildland fires is the identification of suitable safety zones for firefighters during daily fire management operations. To be effective (timely, repeatable, and accurate), these decisions rely on good training and judgment, but also on clear, concise guidelines. This article is a summary of safety zone guidelines and the...

Development and Psychometric Analysis of a Nurses’ Attitudes and Skills Safety Scale: Initial Results

Science.gov (United States)

Armstrong, Gail E.; Dietrich, Mary; Norman, Linda; Barnsteiner, Jane; Mion, Lorraine

2016-01-01

Health care organizations have incorporated updated safety principles in the analysis of errors and in norms and standards. Yet no research exists that assesses bedside nurses’ perceived skills or attitudes toward updated safety concepts. The aims of this study were to develop a scale assessing nurses’ perceived skills and attitudes toward updated safety concepts, determine content validity, and examine internal consistency of the scale and subscales. Understanding nurses’ perceived skills and attitudes about safety concepts can be used in targeting strategies to enhance their safety practices. PMID:27479518

Periodical safety review of units 1 and 2 of PAKS NPP. Examples from summary report

International Nuclear Information System (INIS)

Hammar, K.

1998-01-01

On the basis of American practice of qualification and relevant IAEA recommendations detailed guidelines of the qualification procedure were developed and executed on the Units 1 and 2 of the Paks NPP. Periodic safety supervision will be performed by evaluation of the following reports to be submitted by NPP: real technical conditions of the facility; existing practice and proposals for equipment qualification; evaluation of the existing safety reports estimating their validity up to the plant lifetime; ageing and ageing management; procedures of operation, maintenance, supervision; organisation and administration; safety impact of human factor, training, education, qualification of personnel

Optimal inspection and replacement periods of the safety system in Wolsung Nuclear Power Plant Unit 1 with an optimized cost perspective

International Nuclear Information System (INIS)

Jinil Mok; Poong Hyun Seong

1996-01-01

In this work, a model for determining the optimal inspection and replacement periods of the safety system in Wolsung Nuclear Power Plant Unit 1 is developed, which is to minimize economic loss caused by inadvertent trip and the system failure. This model uses cost benefit analysis method and the part for optimal inspection period considers the human error. The model is based on three factors as follows: (i) The cumulative failure distribution function of the safety system, (ii) The probability that the safety system does not operate due to failure of the system or human error when the safety system is needed at an emergency condition and (iii) The average probability that the reactor is tripped due to the failure of system components or human error. The model then is applied to evaluate the safety system in Wolsung Nuclear Power Plant Unit 1. The optimal replacement periods which are calculated with proposed model differ from those used in Wolsung NPP Unit 1 by about a few days or months, whereas the optimal inspection periods are in about the same range. (author)

Second quarterly report of the Nuclear Safety Bureau for the period 19 January 1988 to 18 April 1988

International Nuclear Information System (INIS)

1988-04-01

The Nuclear Safety Bureau is responsible for monitoring and reviewing the safety of any nuclear plant operated by the Australian Nuclear Science and Technology Organisation (ANSTO). The report covers operation of the HIFAR and MOATA reactors at Lucas Heights, including unusual operating events, maintenance, periodic testing, inspection, HIFAR safety documentation, shift staffing, audit of HIFAR staff training and the emergency control room, HIFAR modifications, nuclear safety aspects of reactor fuel storage and the subcritical assembly

Updated on effluents releases of the CEA nuclear fuel cycle facilities - 1995 to 2010 period

Energy Technology Data Exchange (ETDEWEB)

Ferreira, Nelson Luiz Dias [Centro Tecnologico da Marinha em Sao Paulo (CTMSP) Sao Paulo, SP (Brazil)

2011-07-01

The environmental impact assessment of the Centro Experimental Aramar (CEA) facilities has been presented in a former work, based on the measured effluent releases data, for the period from 1995 to 2007. This work shows the update up to 2010. The effluents releases to the environment result from the routine operation of CEA nuclear fuel cycle facilities (LEI - Isotopic Enrichment Laboratory, USIDE - Pilot Plant for Industrial Verification of Uranium Enrichment and LABMAT - Nuclear Materials Laboratory). Basically, this work presents the radioactive release source terms, as described at the CEA Effluent Report sent to the National Commission for Nuclear Energy (CNEN) each semester, and a historical assessment of the critical group annual doses from 1995 up to 2010. The assessed doses are compared to the maximum dose constraint as well as to the exemption level specified by CNEN. (author)

Updated on effluents releases of the CEA nuclear fuel cycle facilities - 1995 to 2010 period

International Nuclear Information System (INIS)

Ferreira, Nelson Luiz Dias

2011-01-01

The environmental impact assessment of the Centro Experimental Aramar (CEA) facilities has been presented in a former work, based on the measured effluent releases data, for the period from 1995 to 2007. This work shows the update up to 2010. The effluents releases to the environment result from the routine operation of CEA nuclear fuel cycle facilities (LEI - Isotopic Enrichment Laboratory, USIDE - Pilot Plant for Industrial Verification of Uranium Enrichment and LABMAT - Nuclear Materials Laboratory). Basically, this work presents the radioactive release source terms, as described at the CEA Effluent Report sent to the National Commission for Nuclear Energy (CNEN) each semester, and a historical assessment of the critical group annual doses from 1995 up to 2010. The assessed doses are compared to the maximum dose constraint as well as to the exemption level specified by CNEN. (author)

SSI and SKI's Review of SKB's Updated Final Safety Report for SFR 1. Review Report

International Nuclear Information System (INIS)

2003-10-01

The Repository for Radioactive Operational Waste (SFR 1) is now the object of a new review by the Swedish Radiation Protection Authority (SSI) and the Swedish Nuclear Power Inspectorate (SKI). One of the stipulations for operating SFR 1 was that a new assessment of the long-term performance and environmental consequences of the repository should be conducted once every 10 years by the licensee, the Swedish Nuclear Fuel and Waste Management Co (SKB). During the time that SFR 1 has been in operation, experience has been gained of operating the facility and new knowledge of long-term performance of SFR 1 has been obtained. New regulations for nuclear facilities have been promulgated since SFR 1 was taken into operation (1988). A review committee comprising employees from SKI and SSI has conducted the review of SSR 2001. This review report has resulted in the committee's evaluation of the safety of SFR 1 and is the basis of the regulatory authorities' decision concerning any amendments to the stipulations for the operation of SFR 1. However, the review has found deficiencies in the follow up of the development of design basis norms since the facility was constructed as well as deficiencies in learning from operating experience. However, the overall evaluation is that the facility is being operated in an acceptable manner from the standpoint of safety. With respect to the long-term performance of the repository, it is a deficiency that SSR 2001 does not describe how compliance with the stipulated radiation protection requirements on optimisation and use of the best available technology (BAT) is achieved during operation. In the opinion of the review committee, issues relating to occupational radiation protection are being handled satisfactorily and the operational releases of radioactive substances are very small. Safety and Radiation Protection after Closure SKB's long-term repository performance assessment contains essential updates and improvements compared with the

NASA's Software Safety Standard

Science.gov (United States)

Ramsay, Christopher M.

2007-01-01

NASA relies more and more on software to control, monitor, and verify its safety critical systems, facilities and operations. Since the 1960's there has hardly been a spacecraft launched that does not have a computer on board that will provide command and control services. There have been recent incidents where software has played a role in high-profile mission failures and hazardous incidents. For example, the Mars Orbiter, Mars Polar Lander, the DART (Demonstration of Autonomous Rendezvous Technology), and MER (Mars Exploration Rover) Spirit anomalies were all caused or contributed to by software. The Mission Control Centers for the Shuttle, ISS, and unmanned programs are highly dependant on software for data displays, analysis, and mission planning. Despite this growing dependence on software control and monitoring, there has been little to no consistent application of software safety practices and methodology to NASA's projects with safety critical software. Meanwhile, academia and private industry have been stepping forward with procedures and standards for safety critical systems and software, for example Dr. Nancy Leveson's book Safeware: System Safety and Computers. The NASA Software Safety Standard, originally published in 1997, was widely ignored due to its complexity and poor organization. It also focused on concepts rather than definite procedural requirements organized around a software project lifecycle. Led by NASA Headquarters Office of Safety and Mission Assurance, the NASA Software Safety Standard has recently undergone a significant update. This new standard provides the procedures and guidelines for evaluating a project for safety criticality and then lays out the minimum project lifecycle requirements to assure the software is created, operated, and maintained in the safest possible manner. This update of the standard clearly delineates the minimum set of software safety requirements for a project without detailing the implementation for those

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

International Nuclear Information System (INIS)

1993-12-01

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

Time to rethink: an evidence-based response from pelvic surgeons to the FDA Safety Communication: "UPDATE on Serious Complications Associated with Transvaginal Placement of Surgical Mesh for Pelvic Organ Prolapse".

Science.gov (United States)

Murphy, Miles; Holzberg, Adam; van Raalte, Heather; Kohli, Neeraj; Goldman, Howard B; Lucente, Vincent

2012-01-01

In July of 2011 the U.S. Food and Drug Administration (FDA) released a safety communication entitled "UPDATE on Serious Complications Associated with Transvaginal Placement of Surgical Mesh for Pelvic Organ Prolapse." The stated purpose of this communication is to inform health care providers and patients that serious complications with placement of this mesh are not rare and that it is not clear that these repairs are more effective than nonmesh repair. The comments regarding efficacy are based on a systematic review of the scientific literature from 1996-2011 conducted by the FDA. Our review of the literature during this time yields some different conclusions regarding the safety and efficacy of mesh use in prolapse repair. It may be useful to consider this information prior to making recommendations regarding mesh use in prolapse surgery according to the recent UPDATE.

Operational safety performance indicator system at the Dukovany Nuclear Power Plant - Experience with indicator aggregation

International Nuclear Information System (INIS)

Mandula, J.

2001-01-01

The operational safety performance indicators serve as an important tool of performance monitoring and management at the Dukovany NPP. A software-supported system has been developed, which has included: data collection, central data storage, graphic output production and periodical report generation. Analyses of performance indicator trends together with evaluation in respect of annually updated target values and acceptance criteria are used for operational safety reviews forming an integral part of continual self-assessment process. This contribution has been focused on experience obtained during development of the operational safety assessment model using indicator aggregation. It summarises problems that had to be paid specific attention in the development process. Thanks to their solution, the model has become a synoptic monitor and a useful tool for operational safety assessment. (author)

Safety assessment of GM plants: An updated review of the scientific literature.

Science.gov (United States)

Domingo, José L

2016-09-01

In a wide revision of the literature conducted in 2000, I noted that the information in scientific journals on the safety of genetically modified (GM) foods in general, and GM plants in particular, was scarce. Of course, it was not sufficient to guarantee that the consumption of these products should not mean risks for the health of the consumers. Because of the scientific interest in GM organisms (GMOs), as well as the great concern that the consumption of GM foods/plants has raised in a number of countries, I conducted two subsequent revisions (2007 and 2011) on the adverse/toxic effects of GM plants. In the present review, I have updated the information on the potential adverse health effects of GM plants consumed as food and/or feed. With only a few exceptions, the reported studies in the last six years show rather similar conclusions; that is to say, the assessed GM soybeans, rice, corn/maize and wheat would be as safe as the parental species of these plants. However, in spite of the notable increase in the available information, studies on the long-term health effects of GM plants, including tests of mutagenicity, teratogenicity and carcinogenicity seem to be still clearly necessary. Copyright © 2016 Elsevier Ltd. All rights reserved.

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

International Nuclear Information System (INIS)

2007-01-01

legislation, should be aware that the terms included have been chosen and the definitions and explanations given have been drafted for the purpose mentioned above. Terminology and usage may differ in other contexts, such as in binding international legal instruments and in the publications of other organizations. It is recognized that the Safety Glossary will be of wider interest, and it is therefore now issued as an IAEA publication. It is intended to issue a CD-ROM that will include this Safety Glossary (2007 Edition) and versions of the publication in the other five official languages of the IAEA: Arabic, Chinese, French, Russian and Spanish. These other five versions will also be made available for downloading from the Safety Glossary web site. It is intended to revise and update the Safety Glossary periodically in the light of changes in terminology and usage in the safety standards due to developments in technology and changes in regulatory approaches in Member States. The IAEA Secretariat invites the submission of feedback concerning the definitions of technical terms and the explanations of their usage given in the Safety Glossary from users of the IAEA safety standards (in English and in translation) and other safety related publications. A change form is provided on the Safety Glossary web site - http://www-ns.iaea.org/standards/safetyglossary.htm - for the submission of information or suggestions for consideration in a revision of the Safety Glossary. The first version of the Safety Glossary was compiled and issued in 2000. The Safety Glossary, 2007 Edition, is a revised and updated version. In revising the Safety Glossary, account has been taken of safety standards issued since 2000 and of the comments and suggestions submitted in the revision process and in the course of its translation

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

International Nuclear Information System (INIS)

2007-06-01

legislation, should be aware that the terms included have been chosen and the definitions and explanations given have been drafted for the purpose mentioned above. Terminology and usage may differ in other contexts, such as in binding international legal instruments and in the publications of other organizations. It is recognized that the Safety Glossary will be of wider interest, and it is therefore now issued as an IAEA publication. It is intended to issue a CD-ROM that will include this Safety Glossary (2007 Edition) and versions of the publication in the other five official languages of the IAEA: Arabic, Chinese, French, Russian and Spanish. These other five versions will also be made available for downloading from the Safety Glossary web site. It is intended to revise and update the Safety Glossary periodically in the light of changes in terminology and usage in the safety standards due to developments in technology and changes in regulatory approaches in Member States. The IAEA Secretariat invites the submission of feedback concerning the definitions of technical terms and the explanations of their usage given in the Safety Glossary from users of the IAEA safety standards (in English and in translation) and other safety related publications. A change form is provided on the Safety Glossary web site - http://www-ns.iaea.org/standards/safetyglossary.htm - for the submission of information or suggestions for consideration in a revision of the Safety Glossary. The first version of the Safety Glossary was compiled and issued in 2000. The Safety Glossary, 2007 Edition, is a revised and updated version. In revising the Safety Glossary, account has been taken of safety standards issued since 2000 and of the comments and suggestions submitted in the revision process and in the course of its translation

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

International Nuclear Information System (INIS)

2007-01-01

legislation, should be aware that the terms included have been chosen and the definitions and explanations given have been drafted for the purpose mentioned above. Terminology and usage may differ in other contexts, such as in binding international legal instruments and in the publications of other organizations. It is recognized that the Safety Glossary will be of wider interest, and it is therefore now issued as an IAEA publication. It is intended to issue a CD-ROM that will include this Safety Glossary (2007 Edition) and versions of the publication in the other five official languages of the IAEA: Arabic, Chinese, French, Russian and Spanish. These other five versions will also be made available for downloading from the Safety Glossary web site. It is intended to revise and update the Safety Glossary periodically in the light of changes in terminology and usage in the safety standards due to developments in technology and changes in regulatory approaches in Member States. The IAEA Secretariat invites the submission of feedback concerning the definitions of technical terms and the explanations of their usage given in the Safety Glossary from users of the IAEA safety standards (in English and in translation) and other safety related publications. A change form is provided on the Safety Glossary web site - http://www-ns.iaea.org/standards/safetyglossary.htm - for the submission of information or suggestions for consideration in a revision of the Safety Glossary. The first version of the Safety Glossary was compiled and issued in 2000. The Safety Glossary, 2007 Edition, is a revised and updated version. In revising the Safety Glossary, account has been taken of safety standards issued since 2000 and of the comments and suggestions submitted in the revision process and in the course of its translation

Safety of vaccinations in patients with cryopyrin-associated periodic syndromes: a prospective registry based study

NARCIS (Netherlands)

Jaeger, Veronika K.; Hoffman, Hal M.; van der Poll, Tom; Tilson, Hugh; Seibert, Julia; Speziale, Antonio; Junge, Guido; Franke, Kristina; Vritzali, Eleni; Hawkins, Philip N.; Kuemmerle-Deschner, Jasmin; Walker, Ulrich A.

2017-01-01

Pneumococcal, tetanus and influenza vaccinations are recommended for patients with cryopyrin-associated periodic syndromes (CAPS) when treated with immunosuppressive medication. The aim of this publication is to report the safety of pneumococcal and other vaccinations in CAPS patients. All CAPS

Periodic Safety Review in Interim Storage Facilities - Current Regulation and Experiences in Germany

International Nuclear Information System (INIS)

Neles, Julia Mareike; Schmidt, Gerhard

2014-01-01

Periodic safety reviews in nuclear power plants in Germany have been performed since the end of the 1980's as an indirect follow-up of the accident in Chernobyl and, in the meantime, are formally required by law. During this process the guidelines governing this review were developed in stages and reached their final form in 1996. Interim storage facilities and other nuclear facilities at that time were not included, so the guidelines were solely focused on the specific safety issues of nuclear power plants. Following IAEA's recommendations, the Western European Nuclear Regulator Association (WENRA) introduced PSRs in its safety reference levels for storage facilities (current version in WGWD report 2.1 as of Feb 2011: SRLs 59 - 61). Based on these formulations, Germany improved its regulation in 2010 with a recommendation of the Nuclear Waste Management Commission (Entsorgungskommission, ESK), an expert advisory commission for the federal regulatory body BMU. The ESK formulated these detailed requirements in the 'ESK recommendation for guides to the performance of periodic safety reviews for interim storage facilities for irradiated fuel elements and heat-generating radioactive waste'. Before finalization of the guideline a test phase was introduced, aimed to test the new regulation in practice and to later include the lessons learned in the final formulation of the guideline. The two-year test phase started in October 2011 in which the performance of a PSR will be tested at two selected interim storage facilities. Currently these recommendations are discussed with interested/concerned institutions. The results of the test phase shall be considered for improvements of the draft and during the final preparation of guidelines. Currently the PSR for the first ISF is in an advanced stage, the second facility just started the process. Preliminary conclusions from the test phase show that the implementation of the draft guideline requires interpretation. The aim of a

New Safety rules

CERN Multimedia

Safety Commission

2008-01-01

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

The impact of safety standards updating for design purposes in nuclear power plants licensing

International Nuclear Information System (INIS)

Alvarenga, Marco Antonio Bayout; Rabello, Sidney Luiz

2009-01-01

The Brazilian experience of nuclear power plants licensing was consolidated by the use of the Brazilian, American, German and IAEA standards. Independently of the set of norms, standards or guides to be used, this set should be in consonance with the state-of-art or the current state of knowledge in science and technology. In the general design criteria of US NRC or German BMI, or in the Brazilian norms (CNEN) or even, in the IAEA standards, this aspect is always emphasized. On the other hand, the international operational experience of nuclear reactors (for example, TMI accident) also contributes to the updating of norms and standards. The use of new technologies (for example, digital technology) impels the norms and standards to adopt new design criteria related to the new technological context. Moreover, we must add the particular vision that each country can have concerning to specific topics in nuclear safety. This work discusses how the norms, standards and guides used in the nuclear licensing are being reviewed to cope with the requirement of the state-of-art. In order to accomplish this aim we took some general design criteria to exemplify how they are fulfilled, mainly those related directly with the protection of the defense-in-depth barriers: primary coolant system, containment vessel and containment systems, including external events and severe accidents. In complement to the deterministic analysis, it is also discussed the design criteria related to the human factors engineering and probabilistic safety analysis, including severe accidents aspects. (author)

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

International Nuclear Information System (INIS)

1994-12-01

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

2011 NASA Range Safety Annual Report

Science.gov (United States)

Dumont, Alan G.

2012-01-01

Welcome to the 2011 edition of the NASA Range Safety Annual Report. Funded by NASA Headquarters, this report provides a NASA Range Safety overview for current and potential range users. As is typical with odd year editions, this is an abbreviated Range Safety Annual Report providing updates and links to full articles from the previous year's report. It also provides more complete articles covering new subject areas, summaries of various NASA Range Safety Program activities conducted during the past year, and information on several projects that may have a profound impact on the way business will be done in the future. Specific topics discussed and updated in the 2011 NASA Range Safety Annual Report include a program overview and 2011 highlights; Range Safety Training; Range Safety Policy revision; Independent Assessments; Support to Program Operations at all ranges conducting NASA launch/flight operations; a continuing overview of emerging range safety-related technologies; and status reports from all of the NASA Centers that have Range Safety responsibilities. Every effort has been made to include the most current information available. We recommend this report be used only for guidance and that the validity and accuracy of all articles be verified for updates. Once again the web-based format was used to present the annual report. We continually receive positive feedback on the web-based edition and hope you enjoy this year's product as well. As is the case each year, contributors to this report are too numerous to mention, but we thank individuals from the NASA Centers, the Department of Defense, and civilian organizations for their contributions. In conclusion, it has been a busy and productive year. I'd like to extend a personal Thank You to everyone who contributed to make this year a successful one, and I look forward to working with all of you in the upcoming year.

Periodic tests: a human factors analysis of documentary aspects

International Nuclear Information System (INIS)

Perinet, Romuald; Rousseau, Jean-Marie

2007-01-01

Periodic tests are technical inspections aimed at verifying the availability of the safety-related systems during operation. The French licensee, Electricite de France (EDF), manages periodic tests according to procedures, methods of examination and a frequency, which were defined when the systems were designed. These requirements are defined by national authorities of EDF in a reference document composed of rules of testing and tables containing the reference values to be respected. This reference document is analyzed and transformed by each 'Centre Nucleaire de Production d'Electricite' (CNPE) into station-specific operating ranges of periodic tests. In 2003, the IRSN noted that significant events for safety (ESS) involving periodic tests represented more than 20% of ESS between 2000 and 2002. Thus, 340 ESS were related to non-compliance with the conditions of the test and errors in the implementation of the procedures. A first analysis showed that almost 26% of all ESSs from 2000 to 2002 were related to periodic tests. For many of them, the national reference document and the operating ranges of tests were involved. In this context, the 'Direction Generale de la Surete Nucleaire' (DGSNR), requested the 'Institut de Radioprotection et de Surete Nucleaire' (IRSN) to examine the process of definition and implementation of the periodic tests. The IRSN analyzed about thirty French Licensee event reports occurring during the considered period (2000-2002). The IRSN also interviewed the main persons responsible for the processes and observed the performance of 3 periodic tests. The results of this analysis were presented to a group of experts ('Groupe Permanent') charged with delivering advice to the DGSNR about the origin of the problems identified and the improvements to be implemented. The main conclusions of the IRSN addressed the quality of the prescriptive documents. In this context, EDF decided to carry out a thorough analysis of the whole process. The first

Interaction of national and foreign safety guidelines

International Nuclear Information System (INIS)

Domaratzki, Z.

1991-01-01

A commercial contract for a nuclear power plant includes an agreement on the appropriate safety requirements with which the plant must conform. This may involve adopting the safety requirements of the exporting country, the importing country or a combination of the two sets of safety requirements. To ensure that a high level of safety is achieved it is appropriate that the regulatory authorities in the two countries should establish a co-operative arrangement which will extend for the life of the plant. The regulatory authority in the importing country will need to develop a good understanding of the design, safety analysis and operating history of the reactor type which is being purchased. The regulator in the exporting country can be of great assistance in this regard. The co-operative arrangement should extend into the commissioning and operating stage at which point there will be a two way flow of information. During the operating stage information exchange should include significant operating events, operating problems, new safety related research information, necessary design changes and the results of periodic updating of the safety analysis. In some cases the co-operation should extend to training of regulatory staff. The choice of national versus foreign safety requirements may be important. However, if the two regulatory authorities are to discharge their legal and moral safety responsibilities it is at least equally important to maintain a co-operative arrangement for the life of the plant. (author)

Review and updates of the risk assessment for advanced test reactor operations for operating events and experience

International Nuclear Information System (INIS)

Atkinson, S.A.

1996-01-01

Annual or biannual reviews of the operating history of the Advanced Test Reactor (ATR) at the Idaho National Engineering Laboratory (INEL) have been conducted for the purpose of reviewing and updating the ATR probabilistic safety assessment (PSA) for operating events and operating experience since the first compilation of plant- specific experience data for the ATR PSA which included data for operation from initial power operation in 1969 through 1988. This technical paper briefly discusses the means and some results of these periodic reviews of operating experience and their influence on the ATR PSA

Safety training: places available in September 2014

CERN Multimedia

HSE Unit

2014-01-01

There are places available in the forthcoming Safety courses. For updates and registrations, please refer to the Safety Training Catalogue (see here).   Please note that there are 7 places left on the “Territorial Safety Officer (TSO) – Initial” course on September 23-25, 2014 (in French).

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.)

Evaluation of repository safety

Energy Technology Data Exchange (ETDEWEB)

Sagar, B.; Patrick, W.; Dasgupta, B.; Mohanty, S. [Center for Nuclear Waste Regulatory Analyses, San Antonio (United States)

2002-07-01

The United States high-level waste program requires evaluation of radiological safety during two distinct time intervals. The first interval, commonly referred to as the preclosure period, deals with receipt of waste at the site, transfer into disposal containers, if needed, emplacement in the underground openings, monitoring and maintenance activities, backfill and closure of the underground openings, and decontamination and decommissioning of the surface facilities of the geologic repository. The preclosure period may extend from a few tens of years to as long as a few hundred of years, depending on repository design and societal norms regarding a final decision to permanently seal the repository. During the preclosure or operational period, performance confirmation studies are conducted to provide a basis for updating and reevaluating estimates of postclosure performance and, finally, to provide a basis for a closure decision. The postclosure period during which expected repository performance must meet certain standards may range from ten thousands years, as it does in the United States, to millions of years, as it does in some European nations. Waste handling operations in the preclosure period are to be evaluated in relation to their potential effect on workers, members of general public, and the general environment. During this period, releases of radioactivity are to be monitored and appropriate actions taken whenever established limits are approached or exceeded. Preclosure safety is highly dependent on facility design, operational hardware and automated systems, operational sequences, and reliability of humans involved in operations. Preclosure safety analyses conducted before operations begin play a major role in the design process, selection of equipment, and development of operational procedures. Because of the complexity, duration, and spatial scales of the operations, analyses are conducted using mathematical models implemented in computer codes

Evaluation of repository safety

International Nuclear Information System (INIS)

Sagar, B.; Patrick, W.; Dasgupta, B.; Mohanty, S.

2002-01-01

The United States high-level waste program requires evaluation of radiological safety during two distinct time intervals. The first interval, commonly referred to as the preclosure period, deals with receipt of waste at the site, transfer into disposal containers, if needed, emplacement in the underground openings, monitoring and maintenance activities, backfill and closure of the underground openings, and decontamination and decommissioning of the surface facilities of the geologic repository. The preclosure period may extend from a few tens of years to as long as a few hundred of years, depending on repository design and societal norms regarding a final decision to permanently seal the repository. During the preclosure or operational period, performance confirmation studies are conducted to provide a basis for updating and reevaluating estimates of postclosure performance and, finally, to provide a basis for a closure decision. The postclosure period during which expected repository performance must meet certain standards may range from ten thousands years, as it does in the United States, to millions of years, as it does in some European nations. Waste handling operations in the preclosure period are to be evaluated in relation to their potential effect on workers, members of general public, and the general environment. During this period, releases of radioactivity are to be monitored and appropriate actions taken whenever established limits are approached or exceeded. Preclosure safety is highly dependent on facility design, operational hardware and automated systems, operational sequences, and reliability of humans involved in operations. Preclosure safety analyses conducted before operations begin play a major role in the design process, selection of equipment, and development of operational procedures. Because of the complexity, duration, and spatial scales of the operations, analyses are conducted using mathematical models implemented in computer codes

Current Status of Periodic Safety Review of HANARO Research Reactor

Energy Technology Data Exchange (ETDEWEB)

Kim, Minjin; Ahn, Guk-Hoon; Lee, Choong Sung [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

A PSR for a research reactor became a legal requirement as the Nuclear Safety Act was amended and came into effect in 2014. This paper describes the current status and methodology of the first Periodic Safety Review (PSR) of HANARO that is being performed. The legal requirements, work plan, and process of implementing a PSR are described. Because this is the first PSR for a research reactor, it is our understating that the operating organization and regulatory body should communicate well with each other to complete the PSR in a timely manner. The first PSR of HANARO is under way. In order to achieve a successful result, activities of the operation organization such as scheduling, maintaining consistency in input data for review, and reviewing the PSR reports that will require intensive resources should be well planned. This means the operating organization needs to incorporate appropriate measures to ensure the transfer of knowledge and expertise arising from the PSR via a contractor to the operation organization. It is desirable for the Regulatory Body to be involved in all stage of the PSR to prevent any waste of resources and minimize the potential for a reworking of the PSR and the need for an additional assessment and review as recommended by foreign experts.

Optimal replacement and inspection periods of safety and control boards in Wolsung nuclear power plant unit 1

International Nuclear Information System (INIS)

Mok, Jin Il

1993-02-01

In nuclear power plants, the safety and control systems are important for operating and maintaining safety of nuclear power plants. Due to the failure of the instrument and control devices of nuclear power plants caused by aging, nuclear power plants occasionally trip. Since the start of first commercial operation of Kori nuclear power plant (NPP) unit 1, the trips caused by instrument and control systems account for 28% of total trips of NPPs in Korea. Even a single trip of a nuclear power plant causes an extravagant economical loss and deteriorates public acceptance of nuclear power plants. Therefore, the replacement of the instrument and control devices with proper consideration of the aging effect is necessary in order to prevent the inadvertent trip. In this work we investigated the optimal replacement periods of the digital control computer's (DCC) and the programmable digital comparator's (PDC) electronic circuit boards of Wolsung nuclear power plant Unit 1. We first derived mathematical models which calculate optimal replacement periods for electronic circuit boards of digital control computer (DCC) and for those of the programmable digital comparator (PDC) in Wolsung NPP unit 1. And we analytically obtained the optimal replacement periods of electronic circuit boards by using these models. We compared these periods with the replacement periods currently used at Wolsung NPP Unit. The periods used at Wolsung is not based on mathematical analysis, but on empirical knowledge. As a consequence, the optimal replacement periods analytically obtained for the electronic circuit boards of DCC and those used in the field shown small difference : the optimal replacement periods analytically obtained for the electronic circuit boards of PDC are shorter than those used in the field in general. The engineered safeguards of Wolsung nuclear power plant unit 1 contains redundant systems of 2-out-of-3 logic which are not operating under normal conditions but they are called

ILK statement on determining operation periods for nuclear power plants in Germany

International Nuclear Information System (INIS)

2005-09-01

The question of how long nuclear power plants (NPPs) can be safely operated while maintaining a high safety standard played an important role in the worldwide expert discussion in recent years. Far-reaching agreement exists on which reviews and measures to undertake in order to safely operate such plants over longer time periods. In most countries operating licenses for NPPs are not limited in time; this is also the case for Germany. However, the authorization for power operation expires if the plant has used up its approved electricity generation quota. This quota corresponds to a value established in the Atomic Energy Act (AtG) for the individual unit that is based on an operating time of 32 years. On the basis of operating experiences gathered with plants currently in operation and also due to available research findings, the ILK believes that there are no safetyrelated reasons for limiting the operating time of nuclear power plants a priori. The ILK notes that the German NPPs have a high safety standard that is constantly monitored by the regulatory authority. Periodic safety reviews (PSRs), which are performed every ten years, are part of this process. The ILK also takes the view, however, that in the case of very long operating periods, it makes sense to make the continued operation depend on a renewed evaluation (of the plant). This requires demonstrating that the plant displays a level of safety that corresponds to the requirements for the future operating period. The ILK recommends the following approach: - The limitation of production quotas currently laid down in the German Atomic Energy Act should be lifted; - In addition to maintaining the current safety standard, licensees should examine improvement measures for the further reduction of the residual risk and, where appropriate, apply these. The effectiveness of the PSR in its current form should be assessed and the guidelines for their application should be updated, if necessary; - After an operating

An Online Risk Monitor System (ORMS) to Increase Safety and Security Levels in Industry

International Nuclear Information System (INIS)

Zubair, M; Ur Rahman, Khalil; Ul Hassan, Mehmood

2013-01-01

The main idea of this research is to develop an Online Risk Monitor System (ORMS) based on Living Probabilistic Safety Assessment (LPSA). The article highlights the essential features and functions of ORMS. The basic models and modules such as, Reliability Data Update Model (RDUM), running time update, redundant system unavailability update, Engineered Safety Features (ESF) unavailability update and general system update have been described in this study. ORMS not only provides quantitative analysis but also highlights qualitative aspects of risk measures. ORMS is capable of automatically updating the online risk models and reliability parameters of equipment. ORMS can support in the decision making process of operators and managers in Nuclear Power Plants

An Online Risk Monitor System (ORMS) to Increase Safety and Security Levels in Industry

Science.gov (United States)

Zubair, M.; Rahman, Khalil Ur; Hassan, Mehmood Ul

2013-12-01

The main idea of this research is to develop an Online Risk Monitor System (ORMS) based on Living Probabilistic Safety Assessment (LPSA). The article highlights the essential features and functions of ORMS. The basic models and modules such as, Reliability Data Update Model (RDUM), running time update, redundant system unavailability update, Engineered Safety Features (ESF) unavailability update and general system update have been described in this study. ORMS not only provides quantitative analysis but also highlights qualitative aspects of risk measures. ORMS is capable of automatically updating the online risk models and reliability parameters of equipment. ORMS can support in the decision making process of operators and managers in Nuclear Power Plants.

ENSI's technical view on the periodic safety review 2008 of the nuclear power plant Goesgen

International Nuclear Information System (INIS)

2012-08-01

The owner of a license for a nuclear power plant operation in Switzerland has to undergo every 10 years a comprehensive safety check called 'periodic safety review' (PSR). The regulatory authority, the Swiss Federal Nuclear Safety Inspectorate (ENSI), reviews the documents supplied by the licensee. The Goesgen power plant (KKG) obtained its operation license and started operation in 1978. A first PSR was performed in the years 1996 to 1998 (PSR 1998) and reported. KKG delivered an analysis of the safety status, an evaluation of subsystems as well as test reports. The new PSR covers the period 1998 to 2007. The basis of the evaluation by ENSI is the new nuclear energy law in force since 1 February 2005. In comparison to PSR 1998, new aspects have to be considered like the description of the safety concept, including the technical safety classification of buildings, systems and components, or consideration of the protection objective 'limitation of the radiation exposure'. The PSR 2008 is focussed on the estimate of the nuclear safety of KKG. Basically, for the operation of a nuclear power plant, a sufficient protection has to be guaranteed against the release of radioactive materials to the environment as well as the irradiation of persons, during normal operation as well as in the case of accidents. The licensee of a nuclear power plant in operation must retrofit his plant according to the experience already gained and the state-of-the-art. The purpose of the PSR is to check the quality of the plant in the domain of safety. A probabilistic safety assessment (PSA) study must prove that the probability of damages to the reactor core is smaller than 10 -5 /year. In Switzerland the life time of a nuclear power plant is not limited by a fixed maximum time of operation. On the contrary, the limitation proceeds from safety criteria. Insufficiencies in the plant design are often recognized only through the evolution of the technique or some unexpected events. Ageing

Pivotal ERIVANCE basal cell carcinoma (BCC) study: 12-month update of efficacy and safety of vismodegib in advanced BCC.

Science.gov (United States)

Sekulic, Aleksandar; Migden, Michael R; Lewis, Karl; Hainsworth, John D; Solomon, James A; Yoo, Simon; Arron, Sarah T; Friedlander, Philip A; Marmur, Ellen; Rudin, Charles M; Chang, Anne Lynn S; Dirix, Luc; Hou, Jeannie; Yue, Huibin; Hauschild, Axel

2015-06-01

Primary analysis from the pivotal ERIVANCE BCC study resulted in approval of vismodegib, a Hedgehog pathway inhibitor indicated for treatment of adults with metastatic or locally advanced basal cell carcinoma (BCC) that has recurred after surgery or for patients who are not candidates for surgery or radiation. An efficacy and safety analysis was conducted 12 months after primary analysis. This was a multinational, multicenter, nonrandomized, 2-cohort study in patients with measurable and histologically confirmed locally advanced or metastatic BCC taking oral vismodegib (150 mg/d). Primary outcome measure was objective response rate (complete and partial responses) assessed by independent review facility. After 12 months of additional follow-up, median duration of exposure to vismodegib was 12.9 months. Objective response rate increased from 30.3% to 33.3% in patients with metastatic disease, and from 42.9% to 47.6% in patients with the locally advanced form. Median duration of response in patients with locally advanced BCC increased from 7.6 to 9.5 months. No new safety signals emerged with extended treatment duration. Limitations include low prevalence of advanced BCC and challenges of designing a study with heterogenous manifestations. The 12-month update of the study confirms the efficacy and safety of vismodegib in management of advanced BCC. Copyright © 2015 American Academy of Dermatology, Inc. Published by Elsevier Inc. All rights reserved.

[The experience of involvement of volunteers into maintenance of infection safety during period of implementation of mass activities].

Science.gov (United States)

Imamov, A A; Balabanova, L A; Zamalieva, M A

2016-01-01

The article presents experience of Rospotrebnadzor in the Republic of Tatarstan in the field of preventive medicine concerning training of volunteers on issues of infection safety with purpose of prevention of ictuses of infection diseases during mass activities with international participation in the period of XXVII World Summer Students Games. The model of hygienic training for volunteers provides two directions: training for volunteers ’ leaders on issues of infection safety and remote course for involved volunteers. During period of preparation for the Students Games-2013 hygienic training was organized for volunteers-leaders in the field of infection safety with following attestation. The modern training technologies were applied. The volunteers-leaders familiarized with groups of infection diseases including the most dangerous ones, investigated with expert algorithm of actions to be applied in case of suspicion on infection disease in gest or participant of the Games-2013 to secure one's health and health of immediate population. The active volunteers-leaders became trainers and coaches in the field of infection safety. The second stage of infection safety training organized by youth trainers' pool in number of 30 individuals the training technology "Equal trains equal" was applied for hygienic training of volunteers involved at epidemiologically significant objects (food objects, hotels, accompaniment of guests and sportsmen). The volunteers-leaders trained to infection safety 1400 volunteers. The format of electronic personal cabinet and remote course were selected as tools of post-training monitoring.

Compatibility of safety and security

International Nuclear Information System (INIS)

Jalouneix, J.

2013-01-01

Nuclear safety means the achievement of proper operating conditions, prevention of accidents or mitigation of accident consequences, resulting in protection of workers, the public and the environment from undue radiation hazards while nuclear security means the prevention and detection of, and response to, theft, sabotage, unauthorized access, illegal transfer or other malicious acts involving nuclear material. Nuclear safety and nuclear security present large similarities in their aim as in their methods and are mutually complementary in the field of protection with regard to the risk of sabotage. However they show specific attributes in certain areas which leads to differences in their implementation. For instance security culture must integrate deterrence and confidentiality while safety culture implies transparency and open dialogue. Two important design principles apply identically for safety and security: the graded approach and the defense in depth. There are also strong similarities in operating provisions: -) a same need to check the availability of the equipment, -) a same need to treat the experience feedback, or -) a same need to update the basic rules. There are also strong similarities in emergency management, for instance the elaboration of emergency plans and the performance of periodic exercises. Activities related to safety of security of an installation must be managed by a quality management system. For all types of nuclear activities and facilities, a well shared safety culture and security culture is the guarantee of a safe and secure operation. The slides of the presentation have been added at the end of the paper

Blood safety in the world updated

Institute of Scientific and Technical Information of China (English)

Silvano Wandel

2010-01-01

@@ Blood safety is of paramount importance in any medical context, given that it represents one of the most impor-tant supportive procedures in medicine. Nearly all medical fields that lead with very critical patients will depend on blood products as part of supporting medical strategies (both clinical and surgical). Thus, it is im-portant that every country in the world relies on a well established national blood program.

Results of evaluation of periodic safety review for No. 1 plant in Mihama Power Station, Kansai Electric Power Co., Inc

International Nuclear Information System (INIS)

1994-01-01

No. 1 plant in Mihama Power Station started the commercial power generation in November, 1970, and has continued the operation for more than 23 years. During this period, the counter measures to troubles, periodic inspections and the maintenance by the electric power company have been carried out. These states of No. 1 plant in Mihama Power Station for more than 23 years are to be recollected from the view-points of the comprehensive evaluation of operation experiences and the reflection of latest technological knowledge, and the safety and reliability are to be further improved in the periodic safety review. Agency of Natural Resources and Energy evaluated the report of the periodic safety review for No. 1 plant in Mihama Power Station made by Kansai Electric Power Co., and summarized the results. The course of the evaluation of the report is shown. The facility utilization factor is 43.3% on the average of about 23 years, but in the last 10 years, it was improved to 69.4%. In the last five years, the rate of occurrence of unexpected shutoff was 0.6 times/year. These are the results of preventive maintenance and the improvement of the facilities and operation management. Operation management, maintenance management, fuel management, radiation control, and radioactive waste management have been carried out properly. The work plan for preventing disasters was established, and the experience of troubles and the latest technological knowledge were well reflected to improve the safety. (K.I.)

The nuclear safety case for the replacement research reactor

International Nuclear Information System (INIS)

Willers, A.; Garea, V.

2003-01-01

This paper presents a broad overview of the safety case being used in the licensing of Australia's Replacement Research Reactor. The reactor is a 20 MW pool-type research reactor and is being constructed at the Lucas Heights Science and Technology Centre in Sydney's south. It will be owned and operated by the Australian Nuclear Science and Technology Organisation (ANSTO) and will take over the duties currently performed by HIFAR, a DIDO-type reactor currently operating at the site. The safety case for the RRR considers all aspects of normal operation and anticipated occurrences and will be subject to periodic review and updated in line with evolving methodologies and modifications to plant and procedures. Its scope and degree of detail ensure that the risk posed to members of the public, operators and environment are all adequately low and well in the regulatory limits

IAEA safety requirements for safety assessment of fuel cycle facilities and activities

International Nuclear Information System (INIS)

Jones, G.

2013-01-01

The IAEA's Statute authorises the Agency to establish standards of safety for protection of health and minimisation of danger to life and property. In that respect, the IAEA has established a Safety Fundamentals publication which contains ten safety principles for ensuring the protection of workers, the public and the environment from the harmful effects of ionising radiation. A number of these principles require safety assessments to be carried out as a means of evaluating compliance with safety requirements for all nuclear facilities and activities and to determine the measures that need to be taken to ensure safety. The safety assessments are required to be carried out and documented by the organisation responsible for operating the facility or conducting the activity, are to be independently verified and are to be submitted to the regulatory body as part of the licensing or authorisation process. In addition to the principles of the Safety Fundamentals, the IAEA establishes requirements that must be met to ensure the protection of people and the environment and which are governed by the principles in the Safety Fundamentals. The IAEA's Safety Requirements publication 'Safety Assessment for Facilities and Activities', establishes the safety requirements that need to be fulfilled in conducting and maintaining safety assessments for the lifetime of facilities and activities, with specific attention to defence in depth and the requirement for a graded approach to the application of these safety requirements across the wide range of fuel cycle facilities and activities. Requirements for independent verification of the safety assessment that needs to be carried out by the operating organisation, including the requirement for the safety assessment to be periodically reviewed and updated are also covered. For many fuel cycle facilities and activities, environmental impact assessments and non-radiological risk assessments will be required. The

Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety: Steam Generators. 2011 Update

International Nuclear Information System (INIS)

2011-11-01

At present there are over four hundred forty operational nuclear power plants (NPPs) in IAEA Member States. Ageing degradation of the systems, structures of components during their operational life must be effectively managed to ensure the availability of design functions throughout the plant service life. From the safety perspective, this means controlling, within acceptable limits, the ageing degradation and wear-out of plant components important to safety so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This IAEA-TECDOC is one in a series of reports on the assessment and management of ageing of the major NPP components important to safety. The reports are based on experience and practices of NPP operators, regulators, designers, manufacturers, and technical support organizations. The current practices for the assessment of safety margins (fitness for service) and the inspection, monitoring and mitigation of ageing degradation of selected components of Canada deuteriumuranium (CANDU) reactor, boiling water reactor (BWR), pressurized water reactor (PWR), and water moderated, water cooled energy reactor (WWER) plants are documented in the reports. These practices are intended to help all involved directly and indirectly in ensuring the safe operation of NPPs, and also to provide a common technical basis for dialogue between plant operators and regulators when dealing with age related licensing issues. Since the reports are written from a safety perspective, they do not address life or life cycle management of the plant components, which involves the integration of ageing management and economic planning. The target audience of the reports consists of technical experts from NPPs and from regulatory, plant design, manufacturing and technical support organizations dealing with specific plant components addressed in the reports. The component addressed in the present publication is the steam

MO-AB-201-00: Radiation Safety Officer Update

Energy Technology Data Exchange (ETDEWEB)

NONE

2015-06-15

The role of the Radiation Safety Officer at a medical facility can be complicated. The complexity of the position is based on the breadth of services provided at the institution and the nature of the radioactive materials license. Medical practices are constantly changing and the use of ionizing radiation continues to rise in this area. Some of the newer medical applications involving radiation have unique regulatory and safety issues that must be addressed. Oversight of the uses of radiation start at the local level (radiation safety officer, radiation safety committee) and are heavily impacted by outside agencies (i.e. Nuclear Regulatory Commission, State Radiologic Health, The Joint Commission (TJC), etc). This session will provide both an overview of regulatory oversight and essential compliance practices as well as practical ways to assess and introduce some of the new applications utilizing radioactive materials into your medical facility. Learning Objectives: Regulatory Compliance and Safety with New Radiotherapies: Spheres and Ra-223 (Lance Phillips) Understand the radioactive materials license amendment process to add new radiotherapies (i.e., SIR-Spheres, Therasphere, Xofigo). Understand the AU approval process for microspheres and Xofigo. Examine the training and handling requirements for new procedures. Understand the process involved with protocol development, SOP in order to define roles and responsibilities. The RSO and The RSC: Challenges and Opportunities (Colin Dimock) Understand how to form an effective Committee. Examine what the Committee does for the Program and the RSO. Understand the importance of Committee engagement. Discuss the balance of the complimentary roles of the RSO and the Committee. The Alphabet Soup of Regulatory Compliance: Being Prepared for Inspections (Linda Kroger) Recognize the various regulatory bodies and organizations with oversight or impact in Nuclear Medicine, Radiology and Radiation Oncology. Examine 10CFR35

MO-AB-201-00: Radiation Safety Officer Update

International Nuclear Information System (INIS)

2015-01-01

The role of the Radiation Safety Officer at a medical facility can be complicated. The complexity of the position is based on the breadth of services provided at the institution and the nature of the radioactive materials license. Medical practices are constantly changing and the use of ionizing radiation continues to rise in this area. Some of the newer medical applications involving radiation have unique regulatory and safety issues that must be addressed. Oversight of the uses of radiation start at the local level (radiation safety officer, radiation safety committee) and are heavily impacted by outside agencies (i.e. Nuclear Regulatory Commission, State Radiologic Health, The Joint Commission (TJC), etc). This session will provide both an overview of regulatory oversight and essential compliance practices as well as practical ways to assess and introduce some of the new applications utilizing radioactive materials into your medical facility. Learning Objectives: Regulatory Compliance and Safety with New Radiotherapies: Spheres and Ra-223 (Lance Phillips) Understand the radioactive materials license amendment process to add new radiotherapies (i.e., SIR-Spheres, Therasphere, Xofigo). Understand the AU approval process for microspheres and Xofigo. Examine the training and handling requirements for new procedures. Understand the process involved with protocol development, SOP in order to define roles and responsibilities. The RSO and The RSC: Challenges and Opportunities (Colin Dimock) Understand how to form an effective Committee. Examine what the Committee does for the Program and the RSO. Understand the importance of Committee engagement. Discuss the balance of the complimentary roles of the RSO and the Committee. The Alphabet Soup of Regulatory Compliance: Being Prepared for Inspections (Linda Kroger) Recognize the various regulatory bodies and organizations with oversight or impact in Nuclear Medicine, Radiology and Radiation Oncology. Examine 10CFR35

76 FR 10246 - Updating Fire Safety Standards

Science.gov (United States)

2011-02-24

... public noted the importance of requiring facilities to meet up-to-date safety standards. The third... Affairs (VA) regulations concerning community residential care facilities, contract facilities for certain outpatient and residential services, and State home facilities. The final rule will clarify current...

75 FR 13807 - Pipeline Safety: Information Collection Activities

Science.gov (United States)

2010-03-23

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... of Transportation, Pipeline and Hazardous Materials Safety Administration, 1200 New Jersey Avenue, SE...: Updates to Pipeline and Liquefied Natural Gas Reporting Requirements (One Rule). The Notice of Proposed...

Plan for safety case of spent fuel repository at Olkiluoto

International Nuclear Information System (INIS)

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

2005-02-01

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

Performance of dynamic safety barriers-Structuring, modelling and visualization

OpenAIRE

Wikdahl, Olga

2014-01-01

The main objective of this master thesis is to discuss performance of dynamic safety barriers. A comprehensive literature review is performed in order to get understanding what dynamic safety barrier is. Three different concepts of dynamic safety barriers based on various meanings of dynamic were derived from the literature review: - dynamic safety barriers related to motion or physical force - dynamic safety barriers as updated barriers from dynamic risk analysis - dynamic safety ...

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

International Nuclear Information System (INIS)

2008-10-01

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

Human Factors Evaluation of Procedures for Periodic Safety Review of Yonggwang Unit no. 1, 2

Energy Technology Data Exchange (ETDEWEB)

Lee, Yong Hee; Lee, Jung Woon; Park, Jae Chang (and others)

2006-01-15

This report describes the results of human factors assessment on the plant operating procedures as part of Periodic Safety Review(PSR) of Yonggwang Nuclear Power Plant Unit no. 1, 2. The suitability of item and appropriateness of format and structure in the key operating procedures of nuclear power plants were investigated by the review of plant operating experiences and procedure documents, field survey, and experimental assessment on some part of procedures. A checklist was used to perform this assessment and record the review results. The reviewed procedures include EOP(Emergency Operating Procedures), GOP(General Operating Procedures), AOP(Abnormal Operating Procedures), and management procedures of some technical departments. As results of the assessments, any significant problem challenging the safety was not found on the human factors in the operating procedures. However, several small items to be changed and improved were discovered. An action plan is recommended to accommodate the suggestions and review comments. It will enhance the plant safety on the operating procedure.

An update to inplace testing of safety/relief valves utilizing lift assist technology

International Nuclear Information System (INIS)

Heorman, K.R.

1992-01-01

Inplace testing of safety and relief valves with lift-assist devices has received mixed reviews from nuclear power plant testing personnel. While many plants use the technology, most limit its use to testing main steam safety valves (even though both OM-1-1981 and PTC 25.3-1976 allow its use for several different service applications). Test coordinator concerns regarding the technology range from lift set point accuracy and repeatability to the quality of the test result output. In addition, OM-1-1981 and PTC 25.3-1976 differ in their approach to the technology. The reasons for the differences between PTC 25.3-1976 and OM-1-1981 are discussed along with additional considerations applicable to the use of the technology in testing liquid service valves. This paper shows that lift assist technology is capable of determining lift set points within the accuracy requirements of OM-1 and PTC 25.3. It also demonstrates that the technology should not be limited to compressible service systems. Also, improvements in test repeatability and output quality are discussed as a function of the assist device design used and valve characteristics. Lift assist testing is often preferred over inplace testing that uses direct system pressure. It is often more cost efficient than bench testing because it does not require removal of critical systems from service and transportation of components. Also, duplicating system temperatures and other environmental factors is not an issue during inplace testing. Valve testing that once required an outage and maintenance period can now be conducted prior to such periods. This approach minimizes the possibility of failures becoming critical path limiting items

76 FR 70885 - Updating Fire Safety Standards

Science.gov (United States)

2011-11-16

... effect on the economy of $100 million or more or adversely affect in a material way the economy, a sector of the economy, productivity, competition, jobs, the environment, public health or safety, or State...; 64.018, Sharing Specialized Medical Resources; 64.019, Veterans Rehabilitation Alcohol and Drug...

Safety balance: Analysis of safety systems

International Nuclear Information System (INIS)

Delage, M.; Giroux, C.

1990-12-01

Safety analysis, and particularly analysis of exploitation of NPPs is constantly affected by EDF and by the safety authorities and their methodologies. Periodic safety reports ensure that important issues are not missed on daily basis, that incidents are identified and that relevant actions are undertaken. French safety analysis method consists of three principal steps. First type of safety balance is analyzed at the normal start-up phase for each unit including the final safety report. This enables analysis of behaviour of units ten years after their licensing. Second type is periodic operational safety analysis performed during a few years. Finally, the third step consists of safety analysis of the oldest units with the aim to improve the safety standards. The three steps of safety analysis are described in this presentation in detail with the aim to present the objectives and principles. Examples of most recent exercises are included in order to illustrate the importance of such analyses

Dam safety at Seven Sisters Generating Station

International Nuclear Information System (INIS)

Carson, R. W.; Gupta, R. C.

1996-01-01

A safety surveillance program for all hydraulic structures in Manitoba was first implemented in 1979, and updated in 1988. This contribution describes the current status of the program, and the nature of the issues that the program was designed to address. The Seven Sisters Station's dam on the Winnipeg River, about 90 km northeast of the City of Winnipeg, was used as an example. Extensive reviews of flood risks and downstream inundation potential at Seven Sisters' revealed a number of deficiencies; these findings will be incorporated into a corporate plan of overall remediation. Updating the program will also include efforts to ensure adherence to national dam safety guidelines. 5 figs

Animal Cloning and Food Safety

Science.gov (United States)

... Products For Consumers Home For Consumers Consumer Updates Animal Cloning and Food Safety Share Tweet Linkedin Pin ... safe to eat as food from conventionally bred animals. This conclusion stems from an extensive study of ...

Safety stock placement in supply chains with demand forecast updates

Directory of Open Access Journals (Sweden)

Youssef Boulaksil

2016-01-01

Full Text Available Supply chains are exposed to many types of risks and it may not be obvious where to keep safety stocks in the supply chain to hedge against those risks, while maintaining a high customer service level. In this paper, we develop an approach to determine the safety stock levels in supply chain systems that face demand uncertainty. We model customer demand following the Martingale Model of Forecast Evolution (MMFE. An extensive body of literature discusses the safety stock placement problem in supply chains, but most studies assume independent and identically distributed demand. Our approach is based on a simulation study in which mathematical models are solved in a rolling horizon setting. It allows determining the safety stock levels at each stage of the supply chain. Based on a numerical study, we find that a big portion of the safety stocks should be placed downstream in the supply chain to achieve a high customer service level.

An approach to handling timescales in post-closure safety assessment

International Nuclear Information System (INIS)

Bailey, L.; Littleboy, A.

2002-01-01

Previous Nirex post-closure assessments of deep geological disposal have been based on the use of probabilistic safety analysis covering many millions of years. However, Nirex has also published an assessment methodology in which the assessment timescale is divided into a number of discrete periods of time (time frames). Nirex is currently at the stage of planning the next update to its generic post-closure performance assessment and is considering the merits of using an assessment methodology based on time frames, in order to improve links with operational assessments and the provision of advice on the packaging of wastes, and to encourage stakeholder dialogue. This paper has been prepared as part of Nirex's aim, wherever possible, to 'preview', or seek input from others on, its ideas for new work to generate discussion and feedback. It describes an evolution of Nirex's published assessment methodology and outlines how it could be applied in an updated post-closure performance assessment of the Nirex generic phased disposal concept. (authors)

Ongoing enhancements in the German nuclear regulatory framework with respect to fire safety

Energy Technology Data Exchange (ETDEWEB)

Elsche, Bjoern [e.on Kernkraft, Hannover (Germany); Roewekamp, Marina [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Koeln (Germany); Neugebauer, Wilfried [AREVA NP, Erlangen (Germany); Gersinska, Rainer [Bundesamt fuer Strahlenschutz (BfS), Salzgitter (Germany). KTA-Geschaeftsstelle

2015-12-15

In the recent past, the regulatory framework for nuclear power plants (NPP) in Germany has been updated and enhanced comprising on the one hand comprehensive high level regulatory documents such as the 'Safety Requirements for Nuclear Power Plants' and, on the other hand, revised state-of-the-art nuclear safety standards and rules being incorporated in a corresponding legal structure. A major enhancement concerns the nuclear fire and explosion protection standards being already available as so-called green print for final comments which are expected to be officially published end of 2015. The update became necessary after approx. ten years for better addressing some lessons learnt form the operating experience, the consideration of post- Fukushima insights, such as more systematically addressing event combinations with fires and taking into account deviations from non-nuclear standards for escape and rescue routes. Moreover, fire protections remains an important issue for nuclear power plants in Germany during the longer term post-commercial safe shutdown period before decommissioning during which the spent fuel elements remain either in the containment or in the spent fuel pool for further years requiring suitable fire protection means being in place.

Integrated safety assessment report: Integrated Safety Assessment Program: Millstone Nuclear Power Station, Unit 1 (Docket No. 50-245): Draft report

International Nuclear Information System (INIS)

1987-04-01

The Integrated Safety Assessment Program (ISAP) was initiated in November 1984, by the US Nuclear Regulatory Commission to conduct integrated assessments for operating nuclear power reactors. The integrated assessment is conducted in a plant-specific basis to evaluate all licensing actions, licensee initiated plant improvements and selected unresolved generic/safety issues to establish implementation schedules for each item. In addition, procedures will be established to allow for a periodic updating of the schedules to account for licensing issues that arise in the future. This report documents the review of Millstone Nuclear Power Station, Unit No. 1, operated by Northeast Nuclear Energy Company (located in Waterford, Connecticut). Millstone Nuclear Power Station, Unit No. 1, is one of two plants being reviewed under the pilot program for ISAP. This report indicates how 85 topics selected for review were addressed. This report presents the staff's recommendations regarding the corrective actions to resolve the 85 topics and other actions to enhance plant safety. The report is being issued in draft form to obtain comments from the licensee, nuclear safety experts, and the Advisory Committee for Reactor Safeguards (ACRS). Once those comments have been resolved, the staff will present its positions, along with a long-term implementation schedule from the licensee, in the final version of this report

Using Multi-Viewpoint Contracts for Negotiation of Embedded Software Updates

Directory of Open Access Journals (Sweden)

Sönke Holthusen

2016-05-01

Full Text Available In this paper we address the issue of change after deployment in safety-critical embedded system applications. Our goal is to substitute lab-based verification with in-field formal analysis to determine whether an update may be safely applied. This is challenging because it requires an automated process able to handle multiple viewpoints such as functional correctness, timing, etc. For this purpose, we propose an original methodology for contract-based negotiation of software updates. The use of contracts allows us to cleanly split the verification effort between the lab and the field. In addition, we show how to rely on existing viewpoint-specific methods for update negotiation. We illustrate our approach on a concrete example inspired by the automotive domain.

Centre de la Manche institutional control period: after the first safety review - 59236

International Nuclear Information System (INIS)

Dutzer, Michel; Vervialle, Jean Pierre; Andre, Alain; Marchiol, Albert

2012-01-01

Centre de la Manche disposal facility is the first French surface disposal facility dedicated to low and intermediate level short lived radioactive waste. It started up in 1969. After a continuous improvement, in the design of disposal vaults, in operational modes, in the whole process of waste management, in the safety approach, the last packages were received in 1994. 527, 000 m 3 of waste packages have been disposed during the 25 years of operation. The facility was licensed for the institutional control period in 2003. The disposal vaults are covered with a multilayer capping system that includes a bituminous membrane to provide protection against rainwater infiltration. Water that might infiltrate through the membrane is collected by the bottom slab of the vaults to a pipe network implemented in an underground gallery. Measurements show an overall infiltration rate of about 3 l/m 2 /year that complies with the objective of Andra of a few liters per square meter and per year. Investigations are performed in order to assess the behavior of the membrane in the long term. For this purpose periodically samples of the bituminous membrane are taken and measurements are performed. As at the beginning of the operational period waste packages were not conditioned in accordance with the specifications that are presently prescribed to waste generators, some settlements can be observed on the ancient part or the facilities. At the end of 2009 some excavation works were performed in an area where a settlement of few tens of centimeters was observed. The integrity of the membrane could be observed and the adequacy of the selection of this option for the water-tightness of the capping system was so confirmed. Environmental monitoring includes radiological and chemical measurements for discharge, underground water and surface water. In the particular framework of Centre de la Manche, a contamination of groundwater by tritiated wastes occurred in 1976. Theses wastes were

Two Cultures in Modern Science and Technology: For Safety and Validity Does Medicine Have to Update?

Science.gov (United States)

Becker, Robert E

2016-01-11

Two different scientific cultures go unreconciled in modern medicine. Each culture accepts that scientific knowledge and technologies are vulnerable to and easily invalidated by methods and conditions of acquisition, interpretation, and application. How these vulnerabilities are addressed separates the 2 cultures and potentially explains medicine's difficulties eradicating errors. A traditional culture, dominant in medicine, leaves error control in the hands of individual and group investigators and practitioners. A competing modern scientific culture accepts errors as inevitable, pernicious, and pervasive sources of adverse events throughout medical research and patient care too malignant for individuals or groups to control. Error risks to the validity of scientific knowledge and safety in patient care require systemwide programming able to support a culture in medicine grounded in tested, continually updated, widely promulgated, and uniformly implemented standards of practice for research and patient care. Experiences from successes in other sciences and industries strongly support the need for leadership from the Institute of Medicine's recommended Center for Patient Safely within the Federal Executive branch of government.

Safety Awareness & Communications Internship

Science.gov (United States)

Jefferson, Zanani

2015-01-01

The projects that I have worked on during my internships were updating the JSC Safety & Health Action Team JSAT Employee Guidebook, conducting a JSC mishap case study, preparing for JSC Today Close Call success stories, and assisting with event planning and awareness.

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

International Nuclear Information System (INIS)

2007-01-01

technical disciplines. Temporary task groups may also be established to address specific technical issues. The overall scope and technical goals have been established for CSNI for 2006-2009 (see Section III) consistent with the challenges identified in the joint CSNI/CNRA Strategic Plan. High level, top down guidance is provided to the working groups through the development of a set of safety issues and topics which define the technical areas and issues CSNI activities should focus on. The working groups then each prepare their own integrated plan that defines the specific activities and schedule for addressing the safety issues and topics and accomplishing the objectives and technical goals. In Section IV CSNI working methods are described covering priorities, project management, coordination, cooperation, communication, documentation and self assessment. The Operating Plan describes CSNI responsibility and organisation, overall scope of work and working methods, and is supplemented by the so-called CSNI Activity Report, which contains a description of the updated status of the approved specific activities for all Working Groups (WGs), including new proposals set forth for CSNI approval. While the present document remains basically unchanged in the performance period, the CSNI Activity Report is updated every six months, in correspondence of the CSNI meetings

Setting the standard: The IAEA safety standards set the global reference

International Nuclear Information System (INIS)

Williams, L.

2003-01-01

For the IAEA, setting and promoting standards for nuclear radiation, waste, and transport safety have been priorities from the start, rooted in the Agency's 1957 Statute. Today, a corpus of international standards are in place that national regulators and industries in many countries are applying, and more are being encouraged and assisted to follow them. Considerable work is done to keep safety standards updated and authoritative. They cover five main areas: the safety of nuclear facilities; radiation protection and safety of radiation sources; safe management of radioactive waste; safe transport of radioactive material; and thematic safety areas, such as emergency preparedness or legal infrastructures. Overall, the safety standards reflect an international consensus on what constitutes a high level of safety for protecting people and the environment. All IAEA Member States can nominate experts for the Agency standards committees and provide comments on draft standards. Through this ongoing cycle of review and feedback, the standards are refined, updated, and extended where needed

Automated driving and its effects on the safety ecosystem: How do compatibility issues affect the transition period?

NARCIS (Netherlands)

van Loon, R.J.; Martens, Marieke Hendrikje

2015-01-01

Different components of automated vehicles are being made available commercially as we speak. Much research has been conducted into these components and many of these have been studied with respect to their effects on safety, but the transition period from non-automated driving to fully automated

Automated driving and its effect on the safety ecosystem: how do compatibility issues affect the transition period?

NARCIS (Netherlands)

Loon, R.J. van; Martens, M.H.

2015-01-01

Different components of automated vehicles are being made available commercially as we speak. Much research has been conducted into these components and many of these have been studied with respect to their effects on safety, but the transition period from non-automated driving to fully automated

Human factors evaluation of man-machine interface for periodic safety review of nuclear power plants

International Nuclear Information System (INIS)

Lee, Yong Hee; Lee, Jung Woon; Park, Jae Chang; Hwang, In Koo; Lee, Hyun Cheol; Jang, Tong Il; Ku, Jin Young; Kim, Soo Jin

2004-12-01

This report describes the research results of human factors assessment on the MMI(Man Machine Interface) equipment as part of Periodic Safety Review(PSR) of Nuclear Power Plants(NPPs). As MMI is a key factor among human factors to be reviewed in PSR, we reviewed the MMI components of nuclear power plants in aspect of human factors engineering. The availability, suitability, and effectiveness of the MMI devices were chosen to be reviewed. The MMI devices were investigated through the review of design documents related to the MMI, survey of control panels, evaluation of experts, and experimental assessment. Checklists were used to perform this assessment and record the review results. The items mentioned by the expert comments to review in detail in relation with task procedures were tested by experiments with operators' participation. For some questionable issues arisen during this MMI review, operator workload and possibility of errors in operator actions were analysed. The reviewed MMI devices contain MCR(Main Control Room), SPDS(Safety Parameter Display System), RSP(Remote Shutdown Panel), and the selected LCBs(Local Control Boards) importantly related to safety. As results of the assessments, any significant problem challenging the safety was not found on human factors in the MMI devices. However, several small items to be changed and improved in suitability of MMI devices were discovered. An action plan is recommended to accommodate the suggestions and review comments. It will enhance the plant safety on MMI area

Updating the Nomographical Diagrams for Dimensioning the Beams

OpenAIRE

Pop Maria T.

2015-01-01

In order to reduce the time period needed for structures design it is strongly recommended to use nomographical diagrams. The base for formation and updating the nomographical diagrams, stands on the charts presented by different technical publications. The updated charts use the same algorithm and calculation elements as the former diagrams in accordance to the latest prescriptions and European standards. The result consists in a chart, having the same properties, similar with the nomogragra...

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

International Nuclear Information System (INIS)

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

2015-01-01

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

Periodical test program in depth revision

International Nuclear Information System (INIS)

Feltin, C.; Zermizoglou, R.

1987-11-01

Inspection visits made to different sites during 1980 and 1981 evidenced the need to extend and define more precisely the periodical tests performed on safety related systems; thus Electricite de France was requested by the Safety Authorities to re-examine the periodical test program for all safety related systems. This paper presents the methodology adopted by Electricite de France in order to perform an exhaustive analysis of the periodical test program for the 900 and 1300 MWe plants, and the organization set up at the IPSN at one hand and Electricite de France on the other hand for the purpose of elaborating a periodical test program which would be ratified by the Safety Authorities

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

Managing preventive occupational health and safety activities in Danish enterprises during a period of financial crisis

DEFF Research Database (Denmark)

Andersen, Hans H. K.; Bach, Elsa

2017-01-01

The onset of the financial crisis in 2008 has put pressure on enterprises that in turn have downsized and reorganized. Research has shown that economic recession has an effect on psychological and behavioral health that is attributed to working environment problems. The objective of this study is...... focus on the management of preventive workplace health and safety activities in enterprises during a period of economic recession....... is to unravel whether the onset of a general economic recession has had an impact on companies’ and public institutions’ preventive occupational health and safety activities. Hypotheses of the role of pro-cyclical and countercyclical effects are presented. This study is based on a survey of enterprise...... preventive occupational health safety activities. The baseline for the survey was established, in 2006 before the onset of the recession, with a follow up in 2011. Findings are discussed that support both the pro-cyclical and the countercyclical hypotheses. It is concluded that there is a need for a special...

Results of evaluation of periodic safety review for No. 1 plant in Fukushima No. 1 Nuclear Power Station, Tokyo Electric Power Co., Inc

International Nuclear Information System (INIS)

1994-01-01

No. 1 plant in Fukushima No. 1 Nuclear Power Station started the commercial power generation in March, 1971, and has continued the operation for more than 23 years. During this period, the countermeasures to troubles, periodic inspections, and the maintenance by the electric power company have been carried out. These states are to be recollected from the viewpoints of the comprehensive evaluation of the operation experiences and the reflection of the latest technological knowledge, and the safety and reliability are to be further improved in the periodic safety review. Agency of Natural Resources and Energy evaluated the report of the periodic safety review for No. 1 plant in Fukushima No. 1 Nuclear Power Station, and summarized the results. The course of the evaluation of the report is shown. The facility utilization factor was 50.1% on the average of about 23 years, but in the last 10 years, it was improved to 59.7%. In the last five years, the rate of occurrence of unexpected shutdown was 0.4 times/year. These are the results of preventive maintenance and the improvement of the facilities and operation management. Operation management, maintenance management, fuel management, radiation control, radioactive waste management and the reflection of the experience of troubles and the latest technological knowledge to the improvement of safety have been carried out properly. The work plan for disaster prevention was established. (K.I.)

Safety inspections to TRIGA reactors

International Nuclear Information System (INIS)

Byszewski, W.

1988-01-01

The operational safety advisory programme was created to provide useful assistance and advice from an international perspective to research reactor operators and regulators on how to enhance operational safety and radiation protection on their reactors. Safety missions cover not only the operational safety of reactors themselves, but also the safety of associated experimental loops, isotope laboratories and other experimental facilities. Safety missions are also performed on request in other Member States which are interested in receiving impartial advice and assistance in order to enhance the safety of research reactors. The results of the inspections have shown that in some countries there are problems with radiation protection practices and nuclear safety. Very often the Safety Analysis Report is not updated, regulatory supervision needs clarification and improvement, maintenance procedures should be more formalised and records and reports are not maintained properly. In many cases population density around the facility has increased affecting the validity of the original safety analysis

Training Presentation for NASA Civil Helicopter Safety Website

Science.gov (United States)

Iseler, Laura

2002-01-01

NASA civil helicopter safety News & Updates include the following: Mar. 2002. The Air Medical Operations Survey has been completed! Check it out! Also accessible via the Mission pages under Air Medical Mission. Air Medical and Law Enforcement Mission pages have been added. They are accessible via the Mission pages. The Public Use, Personal, Offshore, Law Enforcement, External Load, Business and Gyro accident pages (accessable via the Mission page) have been updated. Feb. 2002. A Words of Wisdom section has been added. You can access it by clicking the Library button. A link to a Corporate Accident Response Plan has been added to the Accident page. The AMs, Aerial Application and Instruction accident pages (accessable via the Mission page) have been updated. Jan. 2002. A new searchable safety article database has been added. You can access it by clicking the Library button. The 2001 accident summaries have been updated and the statistics have been compiled - check it out by clicking the accident tab to the left. Dec. 2001. Please read the FAA Administrator's memo regarding the latest FBI warning. 3ee the FAA column - Fall 2001 Read it now!

Food Safety: MedlinePlus Health Topic

Science.gov (United States)

... Food and Drug Administration) Also in Spanish Animal Cloning and Food Safety (Food and Drug Administration) Chemicals ... Bethesda, MD 20894 U.S. Department of Health and Human Services National Institutes of Health Page last updated ...

Safety analysis for research reactors

International Nuclear Information System (INIS)

2008-01-01

The aim of safety analysis for research reactors is to establish and confirm the design basis for items important to safety using appropriate analytical tools. The design, manufacture, construction and commissioning should be integrated with the safety analysis to ensure that the design intent has been incorporated into the as-built reactor. Safety analysis assesses the performance of the reactor against a broad range of operating conditions, postulated initiating events and other circumstances, in order to obtain a complete understanding of how the reactor is expected to perform in these situations. Safety analysis demonstrates that the reactor can be kept within the safety operating regimes established by the designer and approved by the regulatory body. This analysis can also be used as appropriate in the development of operating procedures, periodic testing and inspection programmes, proposals for modifications and experiments and emergency planning. The IAEA Safety Requirements publication on the Safety of Research Reactors states that the scope of safety analysis is required to include analysis of event sequences and evaluation of the consequences of the postulated initiating events and comparison of the results of the analysis with radiological acceptance criteria and design limits. This Safety Report elaborates on the requirements established in IAEA Safety Standards Series No. NS-R-4 on the Safety of Research Reactors, and the guidance given in IAEA Safety Series No. 35-G1, Safety Assessment of Research Reactors and Preparation of the Safety Analysis Report, providing detailed discussion and examples of related topics. Guidance is given in this report for carrying out safety analyses of research reactors, based on current international good practices. The report covers all the various steps required for a safety analysis; that is, selection of initiating events and acceptance criteria, rules and conventions, types of safety analysis, selection of

Eighth ITER technical meeting on safety and environment

International Nuclear Information System (INIS)

Gordon, C.; Raeder, J.

2000-01-01

From November 27 to 30, 2000 the Eighth ITER Technical Meeting on Safety and Environment was held by the ITER Joint Central Team (JCT) at the Garching Joint Work Site, which also hosts the ITER Safety, Environment and Health Group (SEHG). At this meeting, safety experts from the Home Teams (HT) worked together with the SEHG members towards the following main objectives: review of Generic Site Safety Report (GSSR) results and drafts; review of the Plant Design Description (PDD) summary of safety; update on the status of the R and D tasks contributing to GSSR

Historical Development of the Governmental, Legal and Regulatory Framework for Nuclear Safety in Japan. Annex I of Technical Volume 2

International Nuclear Information System (INIS)

2015-01-01

The governmental and public organizations responsible for policy and safety regulation in Japan have evolved significantly during the period in which the Japanese nuclear power industry has operated. The IAEA’s Integrated Regulatory Review Service (IRRS) mission to Japan in 2007 commended Japan’s updating of its legislative and governmental framework to strengthen arrangements for nuclear safety in light of the incidents which had occurred. A view of these past developments is helpful to understand the origins of the regulatory framework in place at the time of the accident at the Fukushima Daiichi nuclear power plant (NPP), and to assess the prospects for the further institutional reforms that Japan has implemented following this accident. Shiroyama has identified three periods in the evolution of the governmental and regulatory organizations prior to the accident at the Fukushima Daiichi NPP

ELFR: The European Lead Fast Reactor. Design, Safety Approach and Safety Characteristics

International Nuclear Information System (INIS)

Alemberti, Alessandro

2012-01-01

• In the framework of the LEADER project, the safety approach for a Lead cooled fast reactor has been defined and, in particular, all the possible challenges to the main safety functions and their mechanisms have been specified, in order to better define the needed provisions. • On the basis of the above and taking into account the results of the safety analyses performed during previous project (ELSY), a reference configuration of the ELFR plant has been consolidated, by improving and updating the plant design features. In particular, the emerged safety concerns have been analyzed in the LEADER project and a new set of design options and safety provisions have been proposed. • The combination of favourable Lead coolant inherent characteristics and plant design features, specifically developed to face identified challenges, resulted in a very robust and forgiving design, even in very extreme conditions, as a Fukushima-like scenario

Automatic Barometric Updates from Ground-Based Navigational Aids

Science.gov (United States)

1990-03-12

ro fAutomatic Barometric Updates US Department from of Transportation Ground-Based Federal Aviation Administration Navigational Aids Office of Safety...tighter vertical spacing controls , particularly for operations near Terminal Control Areas (TCAs), Airport Radar Service Areas (ARSAs), military climb and...E.F., Ruth, J.C., and Williges, B.H. (1987). Speech Controls and Displays. In Salvendy, G., E. Handbook of Human Factors/Ergonomics, New York, John

Updates to building-code maps for the 2015 NEHRP recommended seismic provisions

Science.gov (United States)

Luco, Nicolas; Bachman, Robert; Crouse, C.B; Harris, James R.; Hooper, John D.; Kircher, Charles A.; Caldwell, Phillp; Rukstales, Kenneth S.

2015-01-01

With the 2014 update of the U.S. Geological Survey (USGS) National Seismic Hazard Model (NSHM) as a basis, the Building Seismic Safety Council (BSSC) has updated the earthquake ground motion maps in the National Earthquake Hazards Reduction Program (NEHRP) Recommended Seismic Provisions for New Buildings and Other Structures, with partial funding from the Federal Emergency Management Agency. Anticipated adoption of the updated maps into the American Society of Civil Engineers Minimum Design Loads for Building and Other Structures and the International Building and Residential Codes is underway. Relative to the ground motions in the prior edition of each of these documents, most of the updated values are within a ±20% change. The larger changes are, in most cases, due to the USGS NSHM updates, reasons for which are given in companion publications. In some cases, the larger changes are partly due to a BSSC update of the slope of the fragility curve that is used to calculate the risk-targeted ground motions, and/or the introduction by BSSC of a quantitative definition of “active faults” used to calculate deterministic ground motions.

Enhancement of safety at nuclear facilities in Pakistan

International Nuclear Information System (INIS)

Ahmad, S.A.; Hayat, T.; Azhar, W.

2006-01-01

Pakistan is benefiting from nuclear technology mostly in health and energy sectors as well as agriculture and industry and has an impeccable safety record. At the national level uses of nuclear technology started in 1955 resulting in the operation of Karachi Radioisotope Center, Karachi, in December 1960. Pakistan Nuclear Safety Committee (PNSC) was formulated in 1964 with subsequent promulgation of Pakistan Atomic Energy Commission (PAEC) Ordinance in 1965 to cope with the anticipated introduction of a research reactor, namely PARR-I, and a nuclear power plant, namely KANUPP. Since then Pakistan's nuclear program has expanded to include numerous nuclear facilities of varied nature. This program has definite economic and social impacts by producing electricity, treating and diagnosing cancer patients, and introducing better crop varieties. Appropriate radiation protection includes a number of measures including database of sealed radiation sources at PAEC operated nuclear facilities, see Table l, updated during periodic physical verification of these sources, strict adherence to the BSS-115, IAEA recommended enforcement of zoning at research reactors and NPPs, etc. Pakistan is party to several international conventions and treaties, such as Convention of Nuclear Safety and Early Notification, to improve and enhance safety at its nuclear facilities. In addition Pakistan generally and PAEC particularly believes in a blend of prudent regulations and good/best practices. This is described in this paper. (Author)

Analytical tool for the periodic safety analysis of NPP according to the PSA guideline. Vol. 1

International Nuclear Information System (INIS)

Balfanz, H.P.; Boehme, E.; Musekamp, W.; Hussels, U.; Becker, G.; Behr, H.; Luettgert, H.

1994-01-01

The SAIS (Safety Analysis and Informationssystem) Programme System is based on an integrated data base, which consists of a plant-data and a PSA related data part. Using SAIS analyses can be performed by special tools, which are connected directly to the data base. Two main editors, RISA+ and DEDIT, are used for data base management. The access to the data base is done via different types of pages, which are displayed on a displayed on a computer screen. The pages are called data sheets. Sets of input and output data sheets were implemented, such as system or component data sheets, fault trees or event trees. All input information, models and results needed for updated results of PSA (Living PSA) can be stored in the SAIS. The programme system contains the editor KVIEW which guarantees consistency of the stored data, e.g. with respect to names and codes of components and events. The information contained in the data base are called in by a standardized users guide programme, called Page Editor. (Brunsbuettel on reference NPP). (orig./HP) [de

Genetics Home Reference: hypokalemic periodic paralysis

Science.gov (United States)

... M, Franques J, Bendahhou S, Lory P, Hainque B, Fournier E, Nicole S, Fontaine B. Hypokalemic Periodic Paralysis. 2002 ... related congenital muscular dystrophy Melorheostosis Rhabdoid tumor predisposition syndrome All New & Updated Pages Reviewed : October 2017 Published : ...

Evidence-based medical review update: pharmacological and surgical treatments of Parkinson's disease: 2001 to 2004.

Science.gov (United States)

Goetz, Christopher G; Poewe, Werner; Rascol, Olivier; Sampaio, Cristina

2005-05-01

The objective of this study is to update a previous evidence-based medicine (EBM) review on Parkinson's disease (PD) treatments, adding January 2001 to January 2004 information. The Movement Disorder Society (MDS) Task Force prepared an EBM review of PD treatments covering data up to January 2001. The authors reviewed Level I (randomized clinical trials) reports of pharmacological and surgical interventions for PD, published as full articles in English (January 2001-January 2004). Inclusion criteria and ranking followed the original program and adhered to EBM methodology. For Efficacy Conclusions, treatments were designated Efficacious, Likely Efficacious, Non-Efficacious, or Insufficient Data. Four clinical indications were considered for each intervention: prevention of disease progression; treatment of Parkinsonism, as monotherapy and as adjuncts to levodopa where indicated; prevention of motor complications; treatment of motor complications. Twenty-seven new studies qualified for efficacy review, and others covered new safety issues. Apomorphine, piribedil, unilateral pallidotomy, and subthalamic nucleus stimulation moved upward in efficacy ratings. Rasagiline, was newly rated as Efficacious monotherapy for control of Parkinsonism. New Level I data moved human fetal nigral transplants, as performed to date, from Insufficient Data to Non- efficacious for the treatment of Parkinsonism, motor fluctuations, and dyskinesias. Selegiline was reassigned as Non-efficacious for the prevention of dyskinesias. Other designations did not change. In a field as active in clinical trials as PD, frequent updating of therapy-based reviews is essential. We consider a 3-year period a reasonable time frame for published updates and are working to establish a Web-based mechanism to update the report in an ongoing manner. Copyright 2005 Movement Disorder Society.

The LANDFIRE Refresh strategy: updating the national dataset

Science.gov (United States)

Nelson, Kurtis J.; Connot, Joel A.; Peterson, Birgit E.; Martin, Charley

2013-01-01

The LANDFIRE Program provides comprehensive vegetation and fuel datasets for the entire United States. As with many large-scale ecological datasets, vegetation and landscape conditions must be updated periodically to account for disturbances, growth, and natural succession. The LANDFIRE Refresh effort was the first attempt to consistently update these products nationwide. It incorporated a combination of specific systematic improvements to the original LANDFIRE National data, remote sensing based disturbance detection methods, field collected disturbance information, vegetation growth and succession modeling, and vegetation transition processes. This resulted in the creation of two complete datasets for all 50 states: LANDFIRE Refresh 2001, which includes the systematic improvements, and LANDFIRE Refresh 2008, which includes the disturbance and succession updates to the vegetation and fuel data. The new datasets are comparable for studying landscape changes in vegetation type and structure over a decadal period, and provide the most recent characterization of fuel conditions across the country. The applicability of the new layers is discussed and the effects of using the new fuel datasets are demonstrated through a fire behavior modeling exercise using the 2011 Wallow Fire in eastern Arizona as an example.

Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards. General Safety Requirements. Pt. 3 (Chinese Edition)

International Nuclear Information System (INIS)

2014-01-01

This publication is the new edition of the International Basic Safety Standards. The edition is co-sponsored by seven other international organizations — European Commission (EC/Euratom), FAO, ILO, OECD/NEA, PAHO, UNEP and WHO. It replaces the interim edition that was published in November 2011 and the previous edition of the International Basic Safety Standards which was published in 1996. It has been extensively revised and updated to take account of the latest finding of the United Nations Scientific Committee on the Effects of Atomic Radiation, and the latest recommendations of the International Commission on Radiological Protection. The publication details the requirements for the protection of people and the environment from harmful effects of ionizing radiation and for the safety of radiation sources. All circumstances of radiation exposure are considered

Radiation protection and safety of radiation sources: International basic safety standards. General safety requirements. Pt. 3 (French Edition)

International Nuclear Information System (INIS)

2016-01-01

This publication is the new edition of the International Basic Safety Standards. The edition is co-sponsored by seven other international organizations — European Commission (EC/Euratom), FAO, ILO, OECD/NEA, PAHO, UNEP and WHO. It replaces the interim edition that was published in November 2011 and the previous edition of the International Basic Safety Standards which was published in 1996. It has been extensively revised and updated to take account of the latest finding of the United Nations Scientific Committee on the Effects of Atomic Radiation, and the latest recommendations of the International Commission on Radiological Protection. The publication details the requirements for the protection of people and the environment from harmful effects of ionizing radiation and for the safety of radiation sources. All circumstances of radiation exposure are considered

Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards. General Safety Requirements. Pt. 3 (Arabic Edition)

International Nuclear Information System (INIS)

2015-01-01

This publication is the new edition of the International Basic Safety Standards. The edition is co-sponsored by seven other international organizations — European Commission (EC/Euratom), FAO, ILO, OECD/NEA, PAHO, UNEP and WHO. It replaces the interim edition that was published in November 2011 and the previous edition of the International Basic Safety Standards which was published in 1996. It has been extensively revised and updated to take account of the latest finding of the United Nations Scientific Committee on the Effects of Atomic Radiation, and the latest recommendations of the International Commission on Radiological Protection. The publication details the requirements for the protection of people and the environment from harmful effects of ionizing radiation and for the safety of radiation sources. All circumstances of radiation exposure are considered

Final disposal of spent fuel in the Finnish bedrock. Scope and requirements for site-specific safety analysis; Kaeytetyn polttoaineen loppusijoitus Suomen kallioperaeaen. Paikkakohtaisen turvallisuusanalyysin edellytykset ja mahdollisuudet

Energy Technology Data Exchange (ETDEWEB)

NONE

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.).

Four Medication Safety Tips for Older Adults

Science.gov (United States)

... Products For Consumers Home For Consumers Consumer Updates 4 Medication Safety Tips for Older Adults Share Tweet ... you are experiencing could be due to medications. 4. Review Medications with Your Health Care Provider Ideally, ...

Microprocessor controlled digital period meter

International Nuclear Information System (INIS)

Keefe, D.J.; McDowell, W.P.; Rusch, G.K.

1980-01-01

A microprocessor controlled digital period meter has been developed and tested operationally on a reactor at Argonne National Laboratory. The principle of operation is the mathematical relationship between asymptotic periods and pulse counting circuitry. This relationship is used to calculate and display the reactor periods over a range of /plus or minus/1 second to /plus or minus/999 seconds. The time interval required to update each measurement automatically varies from 8 seconds at the lowest counting rates to 2 seconds at higher counting rates. The paper will describe hardware and software design details and show the advantages of this type of Period Meter over the conventional circuits. 1 ref

Safety technical considerations on the 2012 periodic safety verification of the Beznau nuclear power plant; Sicherheitstechnische Stellungnahme zur Periodischen Sicherheitsüberprüfung 2012 des Kernkraftwerks Beznau

Energy Technology Data Exchange (ETDEWEB)

NONE

2016-12-15

According to nuclear legislation, the owner of an operational license for a nuclear power plant has to provide a periodic safety verification (PSU) every 10 years. The 'North Eastern Power Plants' company (NOK), today AXPO Power AG already performed such a PSU for the Beznau-2 nuclear reactor block (KKB2) in 2002. The Beznau-1 nuclear reactor block (KKB1) received its definitive operational license in October 1970, after test operation during 7 months. After the license for test operation received on July 16{sup th}, 1971, the operational license of KKB2 was renewed several times, each time for a certain period of validity. In 1991, NOK requested a definitive operational license for KKB2, but in 1994 the Swiss Federal Council lengthened the license for only 10 years. Moreover, it laid down that NOK has to periodically report on the safety of the facility. With its letter of August 23{sup rd}, 1998, the Federal Office of Energy defined the documents to be produced for the PSU. The extent of the PSU was defined in such a way that many documents concern the whole power plant, i.e. both nuclear reactor blocks. On December 3{sup rd}, 2004, the Swiss Federal Council granted KKB2 an operational license of limited validity. The present report reviews the 2012 PSU, which covers the time interval from January 1{sup st}, 2002, to December 31{sup st}, 2011, from the point of view of safety. It contains documents for the evaluation of both reactor blocks at KKB. The Beznau interim storage pool was also taken into consideration; it is situated on the KKB site, but, according to a decision of the Swiss Federal Council of May 23{sup rd}, 1991, it has an independent operational license. The evaluation of ageing surveillance takes the whole operational period of the facility into account, i.e. the ageing mechanisms acting as from the beginning of the operation. Moreover, important developments that occurred after the surveillance time interval have been taken into account

Next generation safety performance monitoring at signalized intersections using connected vehicle technology.

Science.gov (United States)

2014-08-01

Crash-based safety evaluation is often hampered by randomness, lack of timeliness, and rarity of crash : occurrences. This is particularly the case for technology-driven safety improvement projects that are : frequently updated or replaced by newer o...

78 FR 65932 - Updating OSHA Standards Based on National Consensus Standards; Signage

Science.gov (United States)

2013-11-04

...; Signage AGENCY: Occupational Safety and Health Administration (OSHA), Department of Labor. ACTION... accompanied its direct final rule revising its signage standards for general industry and construction. DATES... proposed rule (NPRM) along with the direct final rule (DFR) (see 78 FR 35585) updating its signage...

Neuro-oncology update: radiation safety and nursing care during interstitial brachytherapy

International Nuclear Information System (INIS)

Randall, T.M.; Drake, D.K.; Sewchand, W.

1987-01-01

Radiation control and safety are major considerations for nursing personnel during the care of patients receiving brachytherapy. Since the theory and practice of radiation applications are not part of the routine curriculum of nursing programs, the education of nurses and other health care professionals in radiation safety procedures is important. Regulatory agencies recommend that an annual safety course be given to all persons frequenting, using, or associated with patients containing radioactive materials. This article presents pertinent aspects of the principles and procedures of radiation safety, the role of personnel dose-monitoring devices, and the value of additional radiation control features, such as a lead cubicle, during interstitial brain implants. One institution's protocol and procedures for the care of high-intensity iridium-192 brain implants are discussed. Preoperative teaching guidelines and nursing interventions included in the protocol focus on radiation control principles

Study of Updating Initiating Event Frequency using Prognostics

Energy Technology Data Exchange (ETDEWEB)

Kim, Hyeonmin; Lee, Sang-Hwan; Park, Jun-seok; Kim, Hyungdae; Chang, Yoon-Suk; Heo, Gyunyoung [Kyung Hee Univ., Yongin (Korea, Republic of)

2014-10-15

The Probabilistic Safety Assessment (PSA) model enables to find the relative priority of accident scenarios, weak points in achieving accident prevention or mitigation, and insights to improve those vulnerabilities. Thus, PSA consider realistic calculation for precise and confidence results. However, PSA model still 'conservative' aspects in the procedures of developing a PSA model. One of the sources for the conservatism is caused by the assumption of safety analysis and the estimation of failure frequency. Recently, Surveillance, Diagnosis, and Prognosis (SDP) is a growing trend in applying space and aviation systems in particular. Furthermore, a study dealing with the applicable areas and state-of-the-art status of the SDP in nuclear industry was published. SDP utilizing massive database and information technology among such enabling techniques is worthwhile to be highlighted in terms of the capability of alleviating the conservatism in the conventional PSA. This paper review the concept of integrating PSA and SDP and suggest the updated methodology of Initiating Event (IE) using prognostics. For more detailed, we focus on IE of the Steam Generator Tube Rupture (SGTR) considering tube degradation. This paper is additional research of previous our suggested the research. In this paper, the concept of integrating PSA and SDP are suggested. Prognostics algorithms in SDP are applied at IE, Bes in the Level 1 PSA. As an example, updating SGTR IE and its ageing were considered. Tube ageing were analyzed by using PASTA and Monte Carlo method. After analyzing the tube ageing, conventional SGTR IE were updated by using Bayesian approach. The studied method can help to cover the static and conservatism in PSA.

Study of Updating Initiating Event Frequency using Prognostics

International Nuclear Information System (INIS)

Kim, Hyeonmin; Lee, Sang-Hwan; Park, Jun-seok; Kim, Hyungdae; Chang, Yoon-Suk; Heo, Gyunyoung

2014-01-01

The Probabilistic Safety Assessment (PSA) model enables to find the relative priority of accident scenarios, weak points in achieving accident prevention or mitigation, and insights to improve those vulnerabilities. Thus, PSA consider realistic calculation for precise and confidence results. However, PSA model still 'conservative' aspects in the procedures of developing a PSA model. One of the sources for the conservatism is caused by the assumption of safety analysis and the estimation of failure frequency. Recently, Surveillance, Diagnosis, and Prognosis (SDP) is a growing trend in applying space and aviation systems in particular. Furthermore, a study dealing with the applicable areas and state-of-the-art status of the SDP in nuclear industry was published. SDP utilizing massive database and information technology among such enabling techniques is worthwhile to be highlighted in terms of the capability of alleviating the conservatism in the conventional PSA. This paper review the concept of integrating PSA and SDP and suggest the updated methodology of Initiating Event (IE) using prognostics. For more detailed, we focus on IE of the Steam Generator Tube Rupture (SGTR) considering tube degradation. This paper is additional research of previous our suggested the research. In this paper, the concept of integrating PSA and SDP are suggested. Prognostics algorithms in SDP are applied at IE, Bes in the Level 1 PSA. As an example, updating SGTR IE and its ageing were considered. Tube ageing were analyzed by using PASTA and Monte Carlo method. After analyzing the tube ageing, conventional SGTR IE were updated by using Bayesian approach. The studied method can help to cover the static and conservatism in PSA

Safety Training: places available in October 2014

CERN Multimedia

2014-01-01

There are places available in the forthcoming Safety courses. For updates and registrations, please refer to the Safety Training Catalogue. Safety Training, HSE Unit safety-training@cern.ch Title of the course EN Title of the course FR Date Hours Language Chemical Safety ATEX Habilitation - Level 2 Habilitation ATEX - Niveau 2 16-Oct-14 to 17-Oct-14 9:00 - 17:30 French Cryogenic Safety Cryogenic Safety - Fundamentals Sécurité Cryogénie - Fondamentaux 23-Oct-14 10:00 - 12:00 English Cryogenic Safety - Helium Transfer Sécurité Cryogénie - Transfert d'hélium 30-Oct-14 9:30 - 12:00 English Electrical Safety Habilitation Electrique - Electrician Low Voltage - Initial Habilitation électrique - Électricien basse tension - Initial 02-Oct-14 to 06-Oct-14 9:00 - 17:30 English 20-Oct-14 to 22-Oct-14 9:00 -...

New ICRP recommendations and radiation safety of an NPP

International Nuclear Information System (INIS)

Janzekovic, H.

2007-01-01

In March 2007 the fundamental radiation protection recommendations used world-widely in nuclear facilities were approved by the ICRP. Implementation of radiation safety standards in an NPP is a challenging issue related to all NPP phases from planning a site and its design to its decommissioning also because if neglected it could be very difficult if not impossible to implement improvement of radiation safety later during operation or decommissioning without a substantial cost. The standards are changing with a period of 15 years which is small regarding a prolonged lifetime of many NPPs and also foreseen lifetime of new NPPs, i.e. 60 years. The new recommendations are actually an upgrading of the ICRP 60. Among other changes new sets of wR and wT are given, as well as an update of around 50 different values related to doses. Two new concepts are also tackled i.e. terrorist attacks and protection of the environment. The influence of the new recommendations on the radiation safety of NPPs can be analysed by a selection of four renewed or new concepts: types of exposure situation, dose constraints, source-related approach and safety and security. Their implementation could lead to upgrading the radiation safety of future or existing NPPs as well as of decommissioning processes. Some of the concepts were already extensively and successfully used by designers of modifications or of new NPPs, as well as by operators. (author)

DARHT: INTEGRATION OF AUTHORIZATION BASIS REQUIREMENTS AND WORKER SAFETY

International Nuclear Information System (INIS)

MC CLURE, D. A.; NELSON, C. A.; BOUDRIE, R. L.

2001-01-01

This document describes the results of consensus agreements reached by the DARHT Safety Planning Team during the development of the update of the DARHT Safety Analysis Document (SAD). The SAD is one of the Authorization Basis (AB) Documents required by the Department prior to granting approval to operate the DARHT Facility. The DARHT Safety Planning Team is lead by Mr. Joel A. Baca of the Department of Energy Albuquerque Operations Office (DOE/AL). Team membership is drawn from the Department of Energy Albuquerque Operations Office, the Department of Energy Los Alamos Area Office (DOE/LAAO), and several divisions of the Los Alamos National Laboratory. Revision 1 of the DARHT SAD had been written as part of the process for gaining approval to operate the Phase 1 (First Axis) Accelerator. Early in the planning stage for the required update of the SAD for the approval to operate both Phase 1 and Phase 2 (First Axis and Second Axis) DARHT Accelerator, it was discovered that a conflict existed between the Laboratory approach to describing the management of facility and worker safety

Building America Expert Meeting. Combustion Safety

Energy Technology Data Exchange (ETDEWEB)

Brand, Larry [Partnership for Advanced Residential Retrofit (PARR), Des Plaines, IL (United States)

2013-03-01

This is an overview of "The Best Approach to Combustion Safety in a Direct Vent World," held June 28, 2012, in San Antonio, TX. The objective of this Expert Meeting was to identify gaps and barriers that need to be addressed by future research, and to develop data-driven technical recommendations for code updates so that a common approach for combustion safety can be adopted by all members of the building energy efficiency and code communities.

Building America Expert Meeting: Combustion Safety

Energy Technology Data Exchange (ETDEWEB)

Brand, L.

2013-03-01

This is a meeting overview of 'The Best Approach to Combustion Safety in a Direct Vent World', held June 28, 2012, in San Antonio, Texas. The objective of this Expert Meeting was to identify gaps and barriers that need to be addressed by future research, and to develop data-driven technical recommendations for code updates so that a common approach for combustion safety can be adopted by all members of the building energy efficiency and code communities.

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

Science.gov (United States)

2011-03-31

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

Application of Periodic 3DPCM for Core Monitoring System

International Nuclear Information System (INIS)

Jeong, Wi-Soo; Lee, Hae-Chan; Kim, Hyeong-Seog; Lee, Chang-Kue; Park, Sang-weon; Baek, Jin-su

2014-01-01

The OASIS (Online core Analysis and Simulation System) was developed for WH type PWR which has movable in-core detector. 3DPCM (3D Power Connection Method) was also developed to measure 3D core power distribution using the fixed in-core detector signals and tested for KSNP (Korea Standard Nuclear Plant) such as OPR1000 and APR1400. According to previous study, 3DPCM coupling with neutronics code shows high accuracy. However, this method requires the neutronics code results at each calculation. Therefore, the long calculation time makes it impractical in the online monitoring system requiring the real-time 3D power distribution. In this paper, the 3DPCM based alternative methodology which called periodic 3DPCM is proposed to reduce the calculation time within the reasonable accuracy. The periodic 3DPCM is proposed to reduce the number of neutronics calculation with reasonable accuracy for the application to the online monitoring system development. The periodic 3DPCM is analyzed by 3 cases of sensitivity studies. The errors for the results of power changing operation, ASI changing simulation, and lead control rod insertion are bounded in 0.25%, 1.07%, and 1.15%, respectively. If the update time is shorten as 1 hour, the errors for power changing operation and ASI changing simulation are bounded in 0.07% and 0.56%, respectively. As a result, the update time of 1 hour and prompt update at 30% control rod position change are reasonable considering both conservativeness and effectiveness to update the prediction values. OASIS program utilizing periodic 3DPCM is verified using the plant measurement data and snapshot files which were generated during 45 days operation

Safety during MARS exercise

CERN Multimedia

2015-01-01

It is MARS(1) time again! All employed members of the CERN personnel are currently undergoing the annual MARS evaluations.   This is also a good occasion for supervisors and their supervisees to fill in or update the OHS-0-0-3 form(2) “Identification of occupational hazards”. Filling in the OHS-0-0-3 form is an opportunity to assess any safety issues related to the supervisee's activities.  Each of us should, together with our supervisor, regularly identify and assess the hazards we may be exposed to in the course of our professional activities and reflect on how to control and mitigate them. When filling in the OHS form for the first time, it is important to determine any potential hazards as well as the corresponding preventive measures, in particular training and protective equipment. When updating the form, please review the available information to ensure that it still corresponds to the current activities. The form should be updated w...

Qualified Presumption of Safety (QPS) is a generic risk assessment approach applied by the European Food Safety Authority (EFSA)

DEFF Research Database (Denmark)

Leuschner, R. G. K.; Robinson, T. P.; Hugas, M.

2010-01-01

Qualified Presumption of Safety (QPS) is a generic risk assessment approach applied by the European Food Safety Authority (EFSA) to notified biological agents aiming at simplifying risk assessments across different scientific Panels and Units. The aim of this review is to outline the implementation...... and value of the QPS assessment for EFSA and to explain its principles such as the unambiguous identity of a taxonomic unit, the body of knowledge including potential safety concerns and how these considerations lead to a list of biological agents recommended for QPS which EFSA keeps updated through...

DRY TRANSFER FACILITY CRITICALITY SAFETY CALCULATIONS

International Nuclear Information System (INIS)

C.E. Sanders

2005-01-01

This design calculation updates the previous criticality evaluation for the fuel handling, transfer, and staging operations to be performed in the Dry Transfer Facility (DTF) including the remediation area. The purpose of the calculation is to demonstrate that operations performed in the DTF and RF meet the nuclear criticality safety design criteria specified in the ''Project Design Criteria (PDC) Document'' (BSC 2004 [DIRS 171599], Section 4.9.2.2), the nuclear facility safety requirement in ''Project Requirements Document'' (Canori and Leitner 2003 [DIRS 166275], p. 4-206), the functional/operational nuclear safety requirement in the ''Project Functional and Operational Requirements'' document (Curry 2004 [DIRS 170557], p. 75), and the functional nuclear criticality safety requirements described in the ''Dry Transfer Facility Description Document'' (BSC 2005 [DIRS 173737], p. 3-8). A description of the changes is as follows: (1) Update the supporting calculations for the various Category 1 and 2 event sequences as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2005 [DIRS 171429], Section 7). (2) Update the criticality safety calculations for the DTF staging racks and the remediation pool to reflect the current design. This design calculation focuses on commercial spent nuclear fuel (SNF) assemblies, i.e., pressurized water reactor (PWR) and boiling water reactor (BWR) SNF. U.S. Department of Energy (DOE) Environmental Management (EM) owned SNF is evaluated in depth in the ''Canister Handling Facility Criticality Safety Calculations'' (BSC 2005 [DIRS 173284]) and is also applicable to DTF operations. Further, the design and safety analyses of the naval SNF canisters are the responsibility of the U.S. Department of the Navy (Naval Nuclear Propulsion Program) and will not be included in this document. Also, note that the results for the Monitored Geologic Repository (MGR) Site specific Cask (MSC) calculations are limited to the

Human Factors Evaluation of Man-Machine Interface for Periodic Safety Review of Yonggwang Unit no. 1, 2

International Nuclear Information System (INIS)

Lee, Yong Hee; Lee, Jung Woon; Park, Jae Chang

2006-01-01

This report describes the research results of human factors assessment on the MMI(Man Machine Interface) equipment as part of Periodic Safety Review(PSR) of Yonggwang Unit no. 1, 2. As MMI is a key factor among human factors to be reviewed in PSR, we reviewed the MMI components of nuclear power plants in aspect of human factors engineering. The availability, suitability, and effectiveness of the MMI devices were chosen to be reviewed. The MMI devices were investigated through the review of design documents related to the MMI, survey of control panels, evaluation of experts, and experimental assessment. Checklists were used to perform this assessment and record the review results. The items mentioned by the expert comments to review in detail in relation with task procedures were tested by experiments with operators' participation. For some questionable issues arisen during this MMI review, operator workload and possibility of errors in operator actions were analysed. The reviewed MMI devices contain MCR(Main Control Room), SPDS(Safety Parameter Display System), RSP(Remote Shutdown Panel), and the selected LCBs(Local Control Boards) importantly related to safety. As results of the assessments, any significant problem challenging the safety was not found on human factors in the MMI devices. However, several small items to be changed and improved in suitability of MMI devices were discovered. An action plan is recommended to accommodate the suggestions and review comments. It will enhance the plant safety on MMI area

Human Factors Evaluation of Man-Machine Interface for Periodic Safety Review of Yonggwang Unit no. 1, 2

Energy Technology Data Exchange (ETDEWEB)

Lee, Yong Hee; Lee, Jung Woon; Park, Jae Chang (and others)

2006-01-15

This report describes the research results of human factors assessment on the MMI(Man Machine Interface) equipment as part of Periodic Safety Review(PSR) of Yonggwang Unit no. 1, 2. As MMI is a key factor among human factors to be reviewed in PSR, we reviewed the MMI components of nuclear power plants in aspect of human factors engineering. The availability, suitability, and effectiveness of the MMI devices were chosen to be reviewed. The MMI devices were investigated through the review of design documents related to the MMI, survey of control panels, evaluation of experts, and experimental assessment. Checklists were used to perform this assessment and record the review results. The items mentioned by the expert comments to review in detail in relation with task procedures were tested by experiments with operators' participation. For some questionable issues arisen during this MMI review, operator workload and possibility of errors in operator actions were analysed. The reviewed MMI devices contain MCR(Main Control Room), SPDS(Safety Parameter Display System), RSP(Remote Shutdown Panel), and the selected LCBs(Local Control Boards) importantly related to safety. As results of the assessments, any significant problem challenging the safety was not found on human factors in the MMI devices. However, several small items to be changed and improved in suitability of MMI devices were discovered. An action plan is recommended to accommodate the suggestions and review comments. It will enhance the plant safety on MMI area.

DATMAN: A reliability data analysis program using Bayesian updating

International Nuclear Information System (INIS)

Becker, M.; Feltus, M.A.

1996-01-01

Preventive maintenance (PM) techniques focus on the prevention of failures, in particular, system components that are important to plant functions. Reliability-centered maintenance (RCM) improves on the PM techniques by introducing a set of guidelines by which to evaluate the system functions. It also minimizes intrusive maintenance, labor, and equipment downtime without sacrificing system performance when its function is essential for plant safety. Both the PM and RCM approaches require that system reliability data be updated as more component failures and operation time are acquired. Systems reliability and the likelihood of component failures can be calculated by Bayesian statistical methods, which can update these data. The DATMAN computer code has been developed at Penn State to simplify the Bayesian analysis by performing tedious calculations needed for RCM reliability analysis. DATMAN reads data for updating, fits a distribution that best fits the data, and calculates component reliability. DATMAN provides a user-friendly interface menu that allows the user to choose from several common prior and posterior distributions, insert new failure data, and visually select the distribution that matches the data most accurately

Updates to the Demographic and Spatial Allocation Models to ...

Science.gov (United States)

EPA announced the availability of the draft report, Updates to the Demographic and Spatial Allocation Models to Produce Integrated Climate and Land Use Scenarios (ICLUS) for a 30-day public comment period. The ICLUS version 2 (v2) modeling tool furthered land change modeling by providing nationwide housing development scenarios up to 2100. ICLUS V2 includes updated population and land use data sets and addressing limitations identified in ICLUS v1 in both the migration and spatial allocation models. The companion user guide describes the development of ICLUS v2 and the updates that were made to the original data sets and the demographic and spatial allocation models. [2017 UPDATE] Get the latest version of ICLUS and stay up-to-date by signing up to the ICLUS mailing list. The GIS tool enables users to run SERGoM with the population projections developed for the ICLUS project and allows users to modify the spatial allocation housing density across the landscape.

Safety equipment list for the 241-SY-101 RAPID mitigation project

Energy Technology Data Exchange (ETDEWEB)

MORRIS, K.L.

1999-06-29

This document provides the safety classification for the safety (safety class and safety RAPID Mitigation Project. This document is being issued as the project SEL until the supporting authorization basis documentation, this document will be superseded by the TWRS SEL (LMHC 1999), documentation istlralized. Upon implementation of the authorization basis significant) structures, systems, and components (SSCS) associated with the 241-SY-1O1 which will be updated to include the information contained herein.

Safety equipment list for the 241-SY-101 RAPID mitigation project

International Nuclear Information System (INIS)

Morris, K.L.

1999-01-01

This document provides the safety classification for the safety (safety class and safety RAPID Mitigation Project. This document is being issued as the project SEL until the supporting authorization basis documentation, this document will be superseded by the TWRS SEL (LMHC 1999), documentation istlralized. Upon implementation of the authorization basis significant) structures, systems, and components (SSCS) associated with the 241-SY-1O1 which will be updated to include the information contained herein

New risks and trends in the safety and health of women at work

OpenAIRE

Flaspöler, E; Hauke, A; Koppisch, D; Reinert, D; Koukoulaki, T; Vilkevicius, G; Žemės, L; Águila Martínez-Casariego, M; Baquero Martínez, M; González Lozar, L; Vega Martínez, S; López Riera, S; Carter, L; Leah, C; Gervais, R

2013-01-01

In 2009 and 2010, the Agency commissioned an update to its previous research on gender issues at\\ud work (EU-OSHA, 2003), which found that inequality both within and outside the workplace can have\\ud an effect on the health and safety of women at work. This report provides that update and the first\\ud figures on the effects of the recent economic downturn on women at work. It aims to fulfil the task\\ud outlined by the European strategy on health and safety at work (EC, 2002) for EU-OSHA’s Eur...

Update on pigment dispersion syndrome and pigmentary glaucoma.

Science.gov (United States)

Okafor, Kingsley; Vinod, Kateki; Gedde, Steven J

2017-03-01

The present article reviews the clinical features and pathogenesis of pigment dispersion syndrome and pigmentary glaucoma and provides an update regarding their diagnosis and management. Newer imaging modalities including ultrasound biomicroscopy and anterior segment optical coherence tomography facilitate visualization of the iris concavity characteristic of eyes with pigment dispersion syndrome and pigmentary glaucoma. Patients with pigmentary glaucoma may be distinguished from those with other glaucoma types by the presence of typical symptoms, personality type, and patterns of diurnal intraocular pressure fluctuation. Although laser iridotomy has been shown to alter iris anatomy in pigmentary glaucoma, it is not proven to slow visual field progression. Multiple trials have validated the safety and efficacy of filtering surgery in treating pigmentary glaucoma, with fewer studies published on the role of micro-invasive glaucoma surgery. Literature from the review period has further defined the unique clinical characteristics of pigment dispersion syndrome and pigmentary glaucoma. Laser surgery has a limited role in the management of these entities, whereas trabeculectomy remains an acceptable first-line surgical treatment. Further studies are needed to define the potential application of the newer micro-invasive glaucoma procedures in pigmentary glaucoma.

78 FR 35585 - Updating OSHA Standards Based on National Consensus Standards; Signage

Science.gov (United States)

2013-06-13

...; Signage AGENCY: Occupational Safety and Health Administration (OSHA), Department of Labor. ACTION: Notice... Administration (``OSHA'' or ``the Agency'') proposes to update its general industry and construction signage... standards, ANSI Z53.1-1967, Z35.1-1968, and Z35.2-1968, in its signage standards, thereby providing...

77 FR 2126 - Pipeline Safety: Implementation of the National Registry of Pipeline and Liquefied Natural Gas...

Science.gov (United States)

2012-01-13

... Natural Gas Operators AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No...: ``Pipeline Safety: Updates to Pipeline and Liquefied Natural Gas Reporting Requirements.'' The final rule...

Nuclear criticality safety program for environmental restoration projects

International Nuclear Information System (INIS)

Marble, R.C.; Brown, T.D.

1994-05-01

The Fernald Environmental Management Project (FEMP), formerly known as the Feed Materials Production Center (FMPC), is located on a 1050 acre site approximately twenty miles northwest of Cincinnati, Ohio. The production area of the site covers approximately 136 acres in the central portion of the site. Surrounding the core production area is a buffer consisting of leased grazing land, reforested land, and unused areas. The uranium processing facility was designed and constructed in the early 1950s. During the period from 1952 to 1989 the site produced uranium feed material and uranium products used in the United States weapons complex. Production at the site ended in 1989, when the site was shut down for what was expected to be a short period of time. However, the FUTC was permanently shut down in 1991, and the site's mission was changed from production to environmental restoration. The objective of this paper is to give an update on activities at the Fernald Site and to describe the Nuclear Criticality Safety issues that are currently being addressed

77 FR 68717 - Updating OSHA Standards Based on National Consensus Standards; Head Protection

Science.gov (United States)

2012-11-16

..., 1918, and 1926 [Docket No. OSH-2011-0184] RIN 1218-AC65 Updating OSHA Standards Based on National Consensus Standards; Head Protection AGENCY: Occupational Safety and Health Administration (OSHA), Labor. ACTION: Proposed rule; withdrawal. SUMMARY: With this notice, OSHA is withdrawing the proposed rule that...

Long-term follow-up of MCL patients treated with single-agent ibrutinib: updated safety and efficacy results.

Science.gov (United States)

Wang, Michael L; Blum, Kristie A; Martin, Peter; Goy, Andre; Auer, Rebecca; Kahl, Brad S; Jurczak, Wojciech; Advani, Ranjana H; Romaguera, Jorge E; Williams, Michael E; Barrientos, Jacqueline C; Chmielowska, Ewa; Radford, John; Stilgenbauer, Stephan; Dreyling, Martin; Jedrzejczak, Wieslaw Wiktor; Johnson, Peter; Spurgeon, Stephen E; Zhang, Liang; Baher, Linda; Cheng, Mei; Lee, Dana; Beaupre, Darrin M; Rule, Simon

2015-08-06

Ibrutinib, an oral inhibitor of Bruton tyrosine kinase, is approved for patients with mantle cell lymphoma (MCL) who have received one prior therapy. We report the updated safety and efficacy results from the multicenter, open-label phase 2 registration trial of ibrutinib (median 26.7-month follow-up). Patients (N = 111) received oral ibrutinib 560 mg once daily, and those with stable disease or better could enter a long-term extension study. The primary end point was overall response rate (ORR). The median patient age was 68 years (range, 40-84), with a median of 3 prior therapies (range, 1-5). The median treatment duration was 8.3 months; 46% of patients were treated for >12 months, and 22% were treated for ≥2 years. The ORR was 67% (23% complete response), with a median duration of response of 17.5 months. The 24-month progression-free survival and overall survival rates were 31% (95% confidence interval [CI], 22.3-40.4) and 47% (95% CI, 37.1-56.9), respectively. The most common adverse events (AEs) in >30% of patients included diarrhea (54%), fatigue (50%), nausea (33%), and dyspnea (32%). The most frequent grade ≥3 infections included pneumonia (8%), urinary tract infection (4%), and cellulitis (3%). Grade ≥3 bleeding events in ≥2% of patients were hematuria (2%) and subdural hematoma (2%). Common all-grade hematologic AEs were thrombocytopenia (22%), neutropenia (19%), and anemia (18%). The prevalence of infection, diarrhea, and bleeding was highest for the first 6 months of therapy and less thereafter. With longer follow-up, ibrutinib continues to demonstrate durable responses and favorable safety in relapsed/refractory MCL. The trial is registered to www.ClinicalTrials.gov as #NCT01236391. © 2015 by The American Society of Hematology.

Updating of states in operational hydrological models

Science.gov (United States)

Bruland, O.; Kolberg, S.; Engeland, K.; Gragne, A. S.; Liston, G.; Sand, K.; Tøfte, L.; Alfredsen, K.

2012-04-01

Operationally the main purpose of hydrological models is to provide runoff forecasts. The quality of the model state and the accuracy of the weather forecast together with the model quality define the runoff forecast quality. Input and model errors accumulate over time and may leave the model in a poor state. Usually model states can be related to observable conditions in the catchment. Updating of these states, knowing their relation to observable catchment conditions, influence directly the forecast quality. Norway is internationally in the forefront in hydropower scheduling both on short and long terms. The inflow forecasts are fundamental to this scheduling. Their quality directly influence the producers profit as they optimize hydropower production to market demand and at the same time minimize spill of water and maximize available hydraulic head. The quality of the inflow forecasts strongly depends on the quality of the models applied and the quality of the information they use. In this project the focus has been to improve the quality of the model states which the forecast is based upon. Runoff and snow storage are two observable quantities that reflect the model state and are used in this project for updating. Generally the methods used can be divided in three groups: The first re-estimates the forcing data in the updating period; the second alters the weights in the forecast ensemble; and the third directly changes the model states. The uncertainty related to the forcing data through the updating period is due to both uncertainty in the actual observation and to how well the gauging stations represent the catchment both in respect to temperatures and precipitation. The project looks at methodologies that automatically re-estimates the forcing data and tests the result against observed response. Model uncertainty is reflected in a joint distribution of model parameters estimated using the Dream algorithm.

It’s all about safety signs!

CERN Multimedia

2013-01-01

Their first occurrence may date back to the Egyptian hieroglyphs, but today they can be found everywhere: on our clothes labels as care labels, in train stations and airports to guide us, during the Olympics to identify various sports, on our dashboards, etc.   Safety wise, they are used to indicate a danger, a prohibition, an obligation, a safety exit, firefighting equipment, etc. The HSE Unit has decided to update the 150 safety signs used on the CERN site and, to correspond with this, recently published a Safety Guideline GS-1-0-1, available on the Safety Unit website. The Guideline contains more than 150 safety signs as well as diverse information regarding the meaning of the signs, their location and how to use them. The Guideline will shortly be completed with a new Safety Rule that will replace the former Security Code A3, “Safety colours and safety signs”. Please be informed that you also have the option to create new safety signs, provided that you first g...

Engineering and Safety Partnership Enhances Safety of the Space Shuttle Program (SSP)

Science.gov (United States)

Duarte, Alberto

2007-01-01

Project Management must use the risk assessment documents (RADs) as tools to support their decision making process. Therefore, these documents have to be initiated, developed, and evolved parallel to the life of the project. Technical preparation and safety compliance of these documents require a great deal of resources. Updating these documents after-the-fact not only requires substantial increase in resources - Project Cost -, but this task is also not useful and perhaps an unnecessary expense. Hazard Reports (HRs), Failure Modes and Effects Analysis (FMEAs), Critical Item Lists (CILs), Risk Management process are, among others, within this category. A positive action resulting from a strong partnership between interested parties is one way to get these documents and related processes and requirements, released and updated in useful time. The Space Shuttle Program (SSP) at the Marshall Space Flight Center has implemented a process which is having positive results and gaining acceptance within the Agency. A hybrid Panel, with equal interest and responsibilities for the two larger organizations, Safety and Engineering, is the focal point of this process. Called the Marshall Safety and Engineering Review Panel (MSERP), its charter (Space Shuttle Program Directive 110 F, April 15, 2005), and its Operating Control Plan emphasizes the technical and safety responsibilities over the program risk documents: HRs; FMEA/CILs; Engineering Changes; anomalies/problem resolutions and corrective action implementations, and trend analysis. The MSERP has undertaken its responsibilities with objectivity, assertiveness, dedication, has operated with focus, and has shown significant results and promising perspectives. The MSERP has been deeply involved in propulsion systems and integration, real time technical issues and other relevant reviews, since its conception. These activities have transformed the propulsion MSERP in a truly participative and value added panel, making a

77 FR 16471 - Pipeline Safety: Implementation of the National Registry of Pipeline and Liquefied Natural Gas...

Science.gov (United States)

2012-03-21

... Registry of Pipeline and Liquefied Natural Gas Operators AGENCY: Pipeline and Hazardous Materials Safety... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration 49 CFR Parts... Register (75 FR 72878) titled: ``Pipeline Safety: Updates to Pipeline and Liquefied Natural Gas Reporting...

Therapeutic results and safety of postoperative radiotherapy for keloid after repeated Cesarean section in immediate postpartum period

International Nuclear Information System (INIS)

Kim Ju Ree; Lee, Sang Hoon

2012-01-01

To evaluate the effectiveness and safety of postoperative radiotherapy for the treatment of keloid scars administered immediately after Cesarean section. A total of 26 postpartum patients with confirmed keloids resulting from previous Cesarean sections received either 12 or 15 Gy radiotherapy. The radiotherapy was divided into three 6 MeV electron beam fractions administered during the postpartum period immediately following the fi nal Cesarean section. To evaluate ovarian safety, designated doses of radiation were estimated at the calculated depth of the ovaries using a solid plate phantom and an ionization chamber with the same lead cutout as was used for the treatment of Cesarean section operative scars and a tissue equivalent bolus. In total, the control rate was 77% (20 patients), while six (23%) developed focally elevated keloids (ranging from 0.5 to 2 cm in length) in the middle of the primary abdominal scar. Five patients experienced mild hyperpigmentation. Nonetheless, most patients (96%) were satisfied with the treatment results. The estimated percentage of the applied radiation doses that reached the calculated depth of the ovaries ranged from 0.0033% to 0.0062%. When administered during the immediate postpartum period, postoperative electron beam radiotherapy for repeated Cesarean section scars is generally safe and produces good cosmetic results with minimal toxicity.

Therapeutic results and safety of postoperative radiotherapy for keloid after repeated Cesarean section in immediate postpartum period

Energy Technology Data Exchange (ETDEWEB)

Kim Ju Ree; Lee, Sang Hoon [Cheil General Hospital and Women' s Healthcare Center, Kwandong University College of Medicine, Seoul (Korea, Republic of)

2012-06-15

To evaluate the effectiveness and safety of postoperative radiotherapy for the treatment of keloid scars administered immediately after Cesarean section. A total of 26 postpartum patients with confirmed keloids resulting from previous Cesarean sections received either 12 or 15 Gy radiotherapy. The radiotherapy was divided into three 6 MeV electron beam fractions administered during the postpartum period immediately following the fi nal Cesarean section. To evaluate ovarian safety, designated doses of radiation were estimated at the calculated depth of the ovaries using a solid plate phantom and an ionization chamber with the same lead cutout as was used for the treatment of Cesarean section operative scars and a tissue equivalent bolus. In total, the control rate was 77% (20 patients), while six (23%) developed focally elevated keloids (ranging from 0.5 to 2 cm in length) in the middle of the primary abdominal scar. Five patients experienced mild hyperpigmentation. Nonetheless, most patients (96%) were satisfied with the treatment results. The estimated percentage of the applied radiation doses that reached the calculated depth of the ovaries ranged from 0.0033% to 0.0062%. When administered during the immediate postpartum period, postoperative electron beam radiotherapy for repeated Cesarean section scars is generally safe and produces good cosmetic results with minimal toxicity.

Development and Presentation of the Drigg Post-Closure Safety Case

International Nuclear Information System (INIS)

Kelly, Eugene; Watts, Len; Grimwood, Paul

2001-01-01

Drigg is an operational facility for the near-surface disposal of solid low level radioactive waste (LLW). The disposal facility is located in Cumbria, north-west England, near the Sellafield nuclear site, and is owned and operated by British Nuclear Fuels plc (BNFL). Disposals at Drigg are carried out under the terms of an authorisation granted by the UK Environment Agency. Periodically the Drigg authorisation is subject to formal regulatory review. The current regulatory guidance, 'Disposal Facilities on Land for Low and Intermediate Level Radioactive Wastes: Guidance on Requirements for Authorisation' (the GRA) was published in 1997 and contains guidance on the principles and requirements against which the Environment Agency will consider applications for disposal authorisation. BNFL has undertaken to produce an updated Drigg postclosure safety case (PCSC) in September 2002 to support the next authorisation review. In preparation for this, BNFL published a 'Status Report on the Development of the 2002 Drigg PCSC' in March 2000. This paper discusses the main components of the Drigg PCSC and how they relate to each other. Central to the safety case will be a systematic, post-closure radiological safety assessment (PCRSA). However the main focus of this paper is on the other main components of the PCSC which are presented in conjunction with the PCRSA to make a complete and integrated safety case. In addition other confidence building activities which are key to developing and presenting the safety case are discussed, in particular communications with the stakeholders

Extraglottic airway devices: technology update

Directory of Open Access Journals (Sweden)

Sharma B

2017-08-01

Full Text Available Bimla Sharma, Chand Sahai, Jayashree Sood Department of Anaesthesiology, Pain and Perioperative Medicine, Sir Ganga Ram Hospital, New Delhi, India Abstract: Extraglottic airway devices (EADs have revolutionized the field of airway management. The invention of the laryngeal mask airway was a game changer, and since then, there have been several innovations to improve the EADs in design, functionality, safety and construction material. These have ranged from changes in the shape of the mask, number of cuffs and material used, like rubber, polyvinylchloride and latex. Phthalates, which were added to the construction material in order to increase device flexibility, were later omitted when this chemical was found to have serious adverse reproductive outcomes. The various designs brought out by numerous companies manufacturing EADs resulted in the addition of several devices to the airway market. These airway devices were put to use, many of them with inadequate or no evidence base regarding their efficacy and safety. To reduce the possibility of compromising the safety of the patient, the Difficult Airway Society (DAS formed the Airway Device Evaluation Project Team (ADEPT to strengthen the evidence base for airway equipment and vet the new extraglottic devices. A preuse careful analysis of the design and structure may help in better understanding of the functionality of a particular device. In the meantime, the search for the ideal EAD continues. Keywords: extraglottic airway devices, laryngeal mask airway, other extraglottic airway devices, safety, technology update

Current regulatory developments concerning the implementation of probabilistic safety analyses for external hazards in Germany

International Nuclear Information System (INIS)

Krauss, Matias; Berg, Heinz-Peter

2014-01-01

Ministry for Environment, Nature Conservation and Nuclear Safety (BMU). This expert group, led by the Federal Office for Radiation Protection (BfS), has the task to advise the BMU on all methodological issues for the implementation of probabilistic safety analyses and has elaborated two publications on methods and data for PSA with the aim to support a unified application of the PSA in Germany. With the publication 'Safety requirements for nuclear power plants', a modern version of a German nuclear safety regulations has been published. In this regulation the broad experience of the application of the periodic safety reviews have been incorporated as a key element of regulatory supervision. Further key findings from the European safety review of nuclear power plants were taken into account after the accident at Fukushima. The revision also paid special attention to the requirements and recommendations of WENRA and IAEA. In addition, the recommendations and guidelines of the Nuclear Safety Standards Commission (KTA) and the expert group on Probabilistic Safety Analysis (PSA FAK) have also been updated. The activities of the updates have been focused the natural external hazards 'earthquake' and 'flooding' in the German regulations: - Probabilistic assessment for retrofit measures in individual cases for all operating modes and the PSA level 1 and level 2 is possible. - Deterministic and probabilistic site hazard analysis for the events 'earthquake' and 'flood' are required. - For the event 'earthquake' according to IAEA plants receives a minimum design comparable to 0.1 g >concept. - Furthermore, a seismic instrumentation independent of the location of intensity is required for each installation. - The importance of quality assured plant walk downs to determine the specified plant conditions was explicitly emphasized and required measures to ensure. - Furthermore, the existing methods for their applicability verified the associated generic data base for PSA updated. - The

Flammable gas tank safety program: Technical basis for gas analysis and monitoring

International Nuclear Information System (INIS)

Estey, S.D.

1998-01-01

Several Hanford waste tanks have been observed to exhibit periodic releases of significant quantities of flammable gases. Because potential safety issues have been identified with this type of waste behavior, applicable tanks were equipped with instrumentation offering the capability to continuously monitor gases released from them. This document was written to cover three primary areas: (1) describe the current technical basis for requiring flammable gas monitoring, (2) update the technical basis to include knowledge gained from monitoring the tanks over the last three years, (3) provide the criteria for removal of Standard Hydrogen Monitoring System(s) (SHMS) from a waste tank or termination of other flammable gas monitoring activities in the Hanford Tank farms

77 FR 68684 - Updating OSHA Standards Based on National Consensus Standards; Head Protection

Science.gov (United States)

2012-11-16

..., 1918, and 1926 [Docket No. OSHA-2011-0184] RIN 1218-AC65 Updating OSHA Standards Based on National Consensus Standards; Head Protection AGENCY: Occupational Safety and Health Administration (OSHA), Labor. ACTION: Final rule; confirmation of effective date. SUMMARY: OSHA is confirming the effective date of its...

Length of stay following percutaneous coronary intervention: An expert consensus document update from the society for cardiovascular angiography and interventions.

Science.gov (United States)

Seto, Arnold H; Shroff, Adhir; Abu-Fadel, Mazen; Blankenship, James C; Boudoulas, Konstantinos Dean; Cigarroa, Joaquin E; Dehmer, Gregory J; Feldman, Dmitriy N; Kolansky, Daniel M; Lata, Kusum; Swaminathan, Rajesh V; Rao, Sunil V

2018-04-24

Since the publication of the 2009 SCAI Expert Consensus Document on Length of Stay Following percutaneous coronary intervention (PCI), advances in vascular access techniques, stent technology, and antiplatelet pharmacology have facilitated changes in discharge patterns following PCI. Additional clinical studies have demonstrated the safety of early and same day discharge in selected patients with uncomplicated PCI, while reimbursement policies have discouraged unnecessary hospitalization. This consensus update: (1) clarifies clinical and reimbursement definitions of discharge strategies, (2) reviews the technological advances and literature supporting reduced hospitalization duration and risk assessment, and (3) describes changes to the consensus recommendations on length of stay following PCI (Supporting Information Table S1). These recommendations are intended to support reasonable clinical decision making regarding postprocedure length of stay for a broad spectrum of patients undergoing PCI, rather than prescribing a specific period of observation for individual patients. © 2018 Wiley Periodicals, Inc.

PSA Update Procedures, an Ultimate Need for Living PSA

International Nuclear Information System (INIS)

Hegedus, D.

1998-01-01

Nuclear facilities by their complex nature, change with time. These changes can be both physical (plant modification, etc.), operational (enhanced procedures, etc.) and organizational. In addition, there are also changes in our understanding of the plant, due to operational experience, data collection, technology enhancements, etc. Therefore, it is imperative that PSA model must be frequently up-dated or modified to reflect these changes. Over the last ten years. these has been a remarkable growth of the use of Probabilistic Safety Assessments (PSAs). The most rapidly growing area of the PSA Applications is their use to support operational decision-making. Many of these applications are characterized by the potential for not only improving the safety level but also for providing guidance on the optimal use of resources and reducing regulatory burden. To enable a wider use of the PSA model as a tool for safety activities it is essential to maintain the model in a controlled state. Moreover, to fulfill requirements for L iving PSA , the PSA model has to be constantly updated and/or monitored to reflect the current plant configuration. It should be noted that the PSA model should not only represent the plant design but should also represent the operational and emergency procedures. To keep the PSA model up-to-date several issues should be clearly defined including: - Responsibility should be divided among the PSA group, - Procedures for implementing changes should be established, and - QA requirements/program should be established to assure documentation and reporting. (author)

Occupational exposure in nuclear medicine in Portugal in the 1999-2003 period

International Nuclear Information System (INIS)

Martins, M. B.; Alves, J. G.; Abrantes, J. N.; Roda, A. R.

2007-01-01

The annual doses received by the staff of nuclear medicine departments from public hospitals and private clinics and evaluated by the Individual Monitoring Service of the Radiological Protection and Nuclear Safety Dept. (DPRSN) of the Nuclear and Technological Inst. (ITN) in Portugal, in the 5 y period from 1999 to 2003, are analysed and presented in this paper. In the 1999-2003 period, ITN-DPRSN monitored on an average 462 workers from nuclear medicine departments, which represents 6% of the 8000 workers of the medical field (approximately). The medical sector represents 80-85% of all the monitored population in Portugal. The professions of the monitored workers at nuclear medicine departments were identified by the respective departments as administrative, auxiliary, medical doctor, nuclear medicine technician, nurse, pharmacist and physicist. This information was collected at the onset of the monitoring and was updated over the last 3 y. The annual whole-body doses evaluated in the period 1999-2003 were used to derive the distribution of workers by dose intervals for every profession. The respective annual average doses and annual collective doses, as well as, the total average and total collective doses for the nuclear medicine sector were also determined and are presented. Internal radiation hasn't been monitored. (authors)

Construction safety and waste management an economic analysis

CERN Document Server

Li, Rita Yi Man

2015-01-01

This monograph presents an analysis of construction safety problems and on-site safety measures from an economist’s point of view. The book includes examples from both emerging countries, e.g. China and India, and developed countries, e.g. Australia and Hong Kong. Moreover, the author covers an analysis on construction safety knowledge sharing by means of updatable mobile technology such as apps in Androids and iOS platform mobile devices. The target audience comprises primarily researchers and experts in the field but the book may also be beneficial for graduate students.

Using Addenda in Documented Safety Analysis Reports

International Nuclear Information System (INIS)

Swanson, D.S.; Thieme, M.A.

2003-01-01

This paper discusses the use of addenda to the Radioactive Waste Management Complex (RWMC) Documented Safety Analysis (DSA) located at the Idaho National Engineering and Environmental Laboratory (INEEL). Addenda were prepared for several systems and processes at the facility that lacked adequate descriptive information and hazard analysis in the DSA. They were also prepared for several new activities involving unreviewed safety questions (USQs). Ten addenda to the RWMC DSA have been prepared since the last annual update

Development of safety principles for the design of future nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-06-01

The main purpose of this TECDOC is to propose updates to existing safety principles which could be used as a basis for developing safety principles for the design of future NPPs. Accordingly, this document is intended to be useful to reactor designers, owners, operators, researchers and regulators. It is also expected that this document can contribute to international harmonization of safety approaches, and that it will help ensure that future reactors will be designed worldwide to a high standard of safety. As such, these proposed updates are intended to provide general guidance which, if carefully and properly implemented, will result in reactor designs with enhanced safety characteristics beyond those currently in operation. This enhancement results from the fact that the proposals are derived from the lessons learned from more recent operational experience, R and D, design, testing, and analysis developed over the past decade or so, as well as from attempts to reflect the current trends in reactor design, such as the introduction of new technologies. 8 refs, 3 figs.

Development of safety principles for the design of future nuclear power plants

International Nuclear Information System (INIS)

1995-06-01

The main purpose of this TECDOC is to propose updates to existing safety principles which could be used as a basis for developing safety principles for the design of future NPPs. Accordingly, this document is intended to be useful to reactor designers, owners, operators, researchers and regulators. It is also expected that this document can contribute to international harmonization of safety approaches, and that it will help ensure that future reactors will be designed worldwide to a high standard of safety. As such, these proposed updates are intended to provide general guidance which, if carefully and properly implemented, will result in reactor designs with enhanced safety characteristics beyond those currently in operation. This enhancement results from the fact that the proposals are derived from the lessons learned from more recent operational experience, R and D, design, testing, and analysis developed over the past decade or so, as well as from attempts to reflect the current trends in reactor design, such as the introduction of new technologies. 8 refs, 3 figs

Hypertension in the Neonatal Period: An Update.

Science.gov (United States)

Pillai, Anish; Sharma, Deepak; Kadam, Pratichi

2016-01-01

There has been a growing interest among neonatologists and paediatricians regarding identification and evaluation of hypertension in the neonatal period. Despite the emergent normative data on blood pressure values in term and preterm neonates over the last two decades, there is still controversy regarding correct definition and classification of hypertension. This article will discuss the current definitions, available normative data and etiology of neonatal hypertension. There is paucity of records in terms of efficacy of antihypertensive drugs in this specific population and management is usually experience based, causing considerable heterogeneity amongst different units. This review article will also cover the evaluation, management, outcomes and follow up of neonatal hypertension with latest advances in this field. Copyright© Bentham Science Publishers; For any queries, please email at epub@benthamscience.org.

Cost update technology, safety, and costs of decommissioning a reference uranium hexafluoride conversion plant

International Nuclear Information System (INIS)

Miles, T.L.; Liu, Y.

1995-08-01

The purpose of this study is to update the cost estimates developed in a previous report, NUREG/CR-1757 (Elder 1980) for decommissioning a reference uranium hexafluoride conversion plant from the original mid-1981 dollars to values representative of January 1993. The cost updates were performed by using escalation factors derived from cost index trends over the past 11.5 years. Contemporary price quotes wee used for costs that have increased drastically or for which is is difficult to find a cost trend. No changes were made in the decommissioning procedures or cost element requirements assumed in NUREG/CR-1757. This report includes only information that was changed from NUREG/CR-1757. Thus, for those interested in detailed descriptions and associated information for the reference uranium hexafluoride conversion plant, a copy of NUREG/CR-1757 will be needed

Technical Letter Report: Evaluation and Analysis of a Few International Periodic Safety Review Summary Reports

Energy Technology Data Exchange (ETDEWEB)

Chopra, Omesh K. [Argonne National Lab., IL (United States). Environmental Science Division; Diercks, Dwight R. [Argonne National Lab., IL (United States). Nuclear Engineering Division; Ma, David Chia-Chiun [Argonne National Lab., IL (United States). Environmental Science Division; Garud, Yogendra S. [Argonne National Lab., IL (United States). Environmental Science Division

2013-12-17

At the request of the United States (U.S.) government, the International Atomic Energy Agency (IAEA) assembled a team of 20 senior safety experts to review the regulatory framework for the safety of operating nuclear power plants in the United States. This review focused on the effectiveness of the regulatory functions implemented by the NRC and on its commitment to nuclear safety and continuous improvement. One suggestion resulting from that review was that the U.S. Nuclear Regulatory Commission (NRC) incorporate lessons learned from periodic safety reviews (PSRs) performed in other countries as an input to the NRC’s assessment processes. In the U.S., commercial nuclear power plants (NPPs) are granted an initial 40-year operating license, which may be renewed for additional 20-year periods, subject to complying with regulatory requirements. The NRC has established a framework through its inspection, and operational experience processes to ensure the safe operation of licensed nuclear facilities on an ongoing basis. In contrast, most other countries do not impose a specific time limit on the operating licenses for NPPs, they instead require that the utility operating the plant perform PSRs, typically at approximately 10-year intervals, to assure continued safe operation until the next assessment. The staff contracted with Argonne National Laboratory (Argonne) to perform a pilot review of selected translated PSR assessment reports and related documentation from foreign nuclear regulatory authorities to identify any potential new regulatory insights regarding license renewal-related topics and NPP operating experience (OpE). A total of 14 PSR assessment documents from 9 countries were reviewed. For all of the countries except France, individual reports were provided for each of the plants reviewed. In the case of France, three reports were provided that reviewed the performance assessment of thirty-four 900-MWe reactors of similar design commissioned between 1978

Technical Letter Report: Evaluation and Analysis of a Few International Periodic Safety Review Summary Reports

International Nuclear Information System (INIS)

Chopra, Omesh K.; Diercks, Dwight R.; Ma, David Chia-Chiun; Garud, Yogendra S.

2013-01-01

At the request of the United States (U.S.) government, the International Atomic Energy Agency (IAEA) assembled a team of 20 senior safety experts to review the regulatory framework for the safety of operating nuclear power plants in the United States. This review focused on the effectiveness of the regulatory functions implemented by the NRC and on its commitment to nuclear safety and continuous improvement. One suggestion resulting from that review was that the U.S. Nuclear Regulatory Commission (NRC) incorporate lessons learned from periodic safety reviews (PSRs) performed in other countries as an input to the NRC's assessment processes. In the U.S., commercial nuclear power plants (NPPs) are granted an initial 40-year operating license, which may be renewed for additional 20-year periods, subject to complying with regulatory requirements. The NRC has established a framework through its inspection, and operational experience processes to ensure the safe operation of licensed nuclear facilities on an ongoing basis. In contrast, most other countries do not impose a specific time limit on the operating licenses for NPPs, they instead require that the utility operating the plant perform PSRs, typically at approximately 10-year intervals, to assure continued safe operation until the next assessment. The staff contracted with Argonne National Laboratory (Argonne) to perform a pilot review of selected translated PSR assessment reports and related documentation from foreign nuclear regulatory authorities to identify any potential new regulatory insights regarding license renewal-related topics and NPP operating experience (OpE). A total of 14 PSR assessment documents from 9 countries were reviewed. For all of the countries except France, individual reports were provided for each of the plants reviewed. In the case of France, three reports were provided that reviewed the performance assessment of thirty-four 900-MWe reactors of similar design commissioned between 1978 and

Update on the state of play of Animal Health and Welfare and Environmental Impact of Animals derived from SCNT Cloning and their Offspring, and Food Safety of Products Obtained from those Animals

OpenAIRE

European Food Safety Authority

2012-01-01

The European Food Safety Authority (EFSA) received in December 2011, a request from the European Commission for an update on the possible scientific developments for cloning of farmed animals for food production purposes. The present Statement follows the EFSA 2009 and 2010 Statements and the EFSA 2008 Scientific Opinion, and is based on peer reviewed scientific literature published since the EFSA 2010 Statement, information made available to EFSA following a call for data, and discu...

About the necessity to update the Radiological safety and protection regulations of the National Institute of Nuclear Research (ININ); Sobre la necesidad de actualizar el reglamento de proteccion y seguridad radiologica del ININ

Energy Technology Data Exchange (ETDEWEB)

Alvarez R, J.T. [Instituto Nacional de Investigaciones Nucleares, Salazar (Mexico). Dept. de Metrologia

1997-07-01

It is argued the necessity to update the Radiological safety and Protection regulations (Review 3) of ININ, with the purpose that it implements the ICRU operative magnitudes system. Such a system used with radiological protection purposes. The objective of this system is to do an estimation of the effective equivalent dose H{sub E} and/or the Effective dose E, proposed in the ICRP 26 and ICRU 60 dose limits systems respectively. (Author)

Safety culture in the nuclear field

International Nuclear Information System (INIS)

2005-09-01

The council of IAEA governors ratified twelve elemental principles of physical protection of nuclear matters and installations. These principles will be included in the future updating of the international convention on the physical protection. The F basic principle proposes a definition of the safety culture and recommends that its implementation and its perenniality to be a reality in the concerned organisms.It appears as necessary to precise the concept of safety culture. The twelve principles are as follow: A State liability, B liability during international transports, C legislative and regulatory framework, D competent authority, E operators liability, F safety culture, G threats, H graduated approach, I deep defence, J assurance of the quality, K emergency plan, L confidentiality. The present document is complementary of INSAG-4, 1991 (safety series number 75, INSAG-4 safety culture, a report by the international nuclear safety advisory group, IAEA, 1991) that presents a concept of safety culture. It proposes also, in a particular chapter, the comparisons( common points and specificities) between safety culture and security culture. (N.C.)

Safety design guides for seismic requirements for CANDU 9

International Nuclear Information System (INIS)

Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young; A. C. D. Wright

1996-03-01

This safety design guide for seismic requirements for CANDU 9 describes the seismic design philosophy, defines the applicable earthquakes and identifies the structures and systems requiring seismic qualification to ensure that the essential safety function can be adequately satisfied following earthquake. The detailed requirements for structures, systems and components which must be seismically qualified are specified in the Appendix. The change status of the regulatory requirements, code and standards should be traced and this safety design guide shall be updated accordingly. 1 fig., (Author) .new

An industry update: the latest developments in therapeutic delivery.

Science.gov (United States)

Steinbach, Oliver C

2017-10-01

The present industry update covers the period 1-30 June 2017, with information sourced from company press releases, regulatory and patent agencies as well as scientific literature. The combination of drug and devices such as improved, safer injectables (see various market reports, companies Adamis and Baxter), patches (Microdermis) and (nano)carriers are moving increasingly from the R&D stage into clinical trials and toward the market. This addresses increased safety and effectiveness requirements, limiting physico-chemical properties of active ingredients, cost-effectiveness and patient comfort through ease of use. Further attention in the market is on local delivery methods (such as intraocular by Icon Bioscience, Glaukos) and the sheer infinite possibilities of nanotechnology such as LDL nanocarriers, microneedles and hydrogel cubes. Another 21st century key technology area is mobile applications (Vital Art and Science) and connected devices (SmartPill, Pop Test Devices) which are increasingly finding their way into the drug delivery field to enable, for example, closed loop monitoring of drug dosing in trials and of patients with their care providers. Not surprisingly companies are increasingly utilizing convergence to combine their diverse capabilities (Vetter Pharma/Microdermis, TXCell/Lentigen Technology).

NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 11, June 2009

International Nuclear Information System (INIS)

2009-06-01

The current issue presents information about the following topics: Nuclear Safety Review for the Year 2008; Feedback from IRS Topical Studies and Events Applied to Safety Standards; Education and Training Programmes at the IAEA Department of Nuclear Safety and Security; Peer Review of Operational Safety Performance (PROSPER)

Primary circuit water chemistry during shutdown period at Kalinin NPP

International Nuclear Information System (INIS)

Gorbatenko, S.; Otchenashev, G.; Yurmanov, V.

2005-01-01

The primary circuit water chemistry feature at Kalinin NPP is using of special up-dated regime during the period of unit shutdown for refueling. The main objective of up-dated regime is removing from the circuit long time living corrosion products on SVO-2 ion exchange filters with the purpose of dose rates reduction from the equipment and in such a way reduction of maintenance personnel overexposure. (N.T.)

Safety of Fluoroquinolones: An Update

Directory of Open Access Journals (Sweden)

L Mandell

2002-01-01

Full Text Available The fluoroquinolone class of antimicrobials has been in clinical use for over 13 years. During that period, some representatives of the class have been extensively prescribed, such as ciprofloxacin and levofloxacin, while others have seen minimal use and have been restricted or withdrawn, namely, trovafloxacin and grepafloxacin. Manipulation of the fluoroquinolone structure by substituting a range of moieties around the core has yielded enhanced antibacterial activity, but in some cases this has come at a price. Specific substitutions are discussed in relation to particular recognized adverse events. In the present paper, newly introduced fluoroquinolones, such as moxifloxacin and gatifloxacin, are examined in terms of anticipated class effects and recent clinical experience. These antimicrobials are associated with reactions such as diarrhea, nausea, headache and other typical antimicrobial phenomena at rates less than 5%. New fluoroquinolone agents should be examined carefully in light of structural findings until adequate clinical data are amassed.

Construction and updating of a public events questionnaire for repeated measures longitudinal studies

Directory of Open Access Journals (Sweden)

Martha eNoone

2014-03-01

Full Text Available Impairments of retrospective memory and cases of retrograde amnesia are often seen in clinical settings. A measure of the proportion of memories retained over a specified time can be useful in clinical situations and public events questionnaires may be valuable in this respect. However, consistency of retention of public events memory has rarely been studied in the same participants. In addition, when used in a research context, public events questionnaires require updating to ensure questions are of equivalent age with respect to when the test is taken. This paper describes an approach to constructing and updating a Public Events Questionnaire (PEQ for use with a sample that is recruited and followed-up over a long time-period. Internal consistency, parallel-form reliability, test-retest reliability and secondary validity analyses were examined for three versions of the PEQ that were updated every six months. Versions 2 and 3 of the questionnaire were reliable across and within versions and for recall and recognition. Change over time was comparable across each version of the PEQ. These results show that PEQs can be regularly updated in a standardised fashion to allow use throughout studies with long recruitment periods.

Construction and updating of a public events questionnaire for repeated measures longitudinal studies.

Science.gov (United States)

Noone, Martha; Semkovska, Maria; Carton, Mary; Dunne, Ross; Horgan, John-Paul; O'Kane, Breige; McLoughlin, Declan M

2014-01-01

Impairments of retrospective memory and cases of retrograde amnesia are often seen in clinical settings. A measure of the proportion of memories retained over a specified time can be useful in clinical situations and public events questionnaires may be valuable in this respect. However, consistency of retention of public events memory has rarely been studied in the same participants. In addition, when used in a research context, public events questionnaires require updating to ensure questions are of equivalent age with respect to when the test is taken. This paper describes an approach to constructing and updating a Public Events Questionnaire (PEQ) for use with a sample that is recruited and followed-up over a long time-period. Internal consistency, parallel-form reliability, test-retest reliability, and secondary validity analyses were examined for three versions of the PEQ that were updated every 6 months. Versions 2 and 3 of the questionnaire were reliable across and within versions and for recall and recognition. Change over time was comparable across each version of the PEQ. These results show that PEQs can be regularly updated in a standardized fashion to allow use throughout studies with long recruitment periods.

ILK statement on determining operation periods for nuclear power plants in Germany; ILK-Stellungnahme zur Festlegung von Betriebszeiten fuer Kernkfraftwerke in Deutschland

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-09-15

The question of how long nuclear power plants (NPPs) can be safely operated while maintaining a high safety standard played an important role in the worldwide expert discussion in recent years. Far-reaching agreement exists on which reviews and measures to undertake in order to safely operate such plants over longer time periods. In most countries operating licenses for NPPs are not limited in time; this is also the case for Germany. However, the authorization for power operation expires if the plant has used up its approved electricity generation quota. This quota corresponds to a value established in the Atomic Energy Act (AtG) for the individual unit that is based on an operating time of 32 years. On the basis of operating experiences gathered with plants currently in operation and also due to available research findings, the ILK believes that there are no safetyrelated reasons for limiting the operating time of nuclear power plants a priori. The ILK notes that the German NPPs have a high safety standard that is constantly monitored by the regulatory authority. Periodic safety reviews (PSRs), which are performed every ten years, are part of this process. The ILK also takes the view, however, that in the case of very long operating periods, it makes sense to make the continued operation depend on a renewed evaluation (of the plant). This requires demonstrating that the plant displays a level of safety that corresponds to the requirements for the future operating period. The ILK recommends the following approach: - The limitation of production quotas currently laid down in the German Atomic Energy Act should be lifted; - In addition to maintaining the current safety standard, licensees should examine improvement measures for the further reduction of the residual risk and, where appropriate, apply these. The effectiveness of the PSR in its current form should be assessed and the guidelines for their application should be updated, if necessary; - After an operating

Contrast media. Safety issues and ESUR guidelines. 3. ed.

International Nuclear Information System (INIS)

Thomsen, Henrik S.; Webb, Judith A.W.

2014-01-01

Fully updates the previous edition and includes new chapters on various complex topics. Represents a unique and unparalleled source of information on the many safety issues relating to different contrast media. Includes chapters on acute and delayed non-renal adverse reactions and on renal adverse reactions. Presented in a handy, easy-to-use format. In 1994 the European Society of Urogenital Radiology (ESUR) set up a committee to consider the safety of contrast media used for diagnostic imaging. Subsequently the committee questioned ESUR members, reviewed the literature, proposed guidelines, and discussed these proposals with participants at the annual symposia of the society. The end result of this work was the successful first edition of this book, published in 2006, which was followed by an equally successful second edition in 2009. This third edition not only fully updates the previous edition, but also includes new chapters on complex topics such as use of contrast media in children and practical aspects of off-label contrast media use. The authorship includes members, past members, and non-members of the Contrast Media Safety Committee.

Hazard screening application guide. Safety Analysis Report Update Program

Energy Technology Data Exchange (ETDEWEB)

None

1992-06-01

The basic purpose of hazard screening is to group precesses, facilities, and proposed modifications according to the magnitude of their hazards so as to determine the need for and extent of follow on safety analysis. A hazard is defined as a material, energy source, or operation that has the potential to cause injury or illness in human beings. The purpose of this document is to give guidance and provide standard methods for performing hazard screening. Hazard screening is applied to new and existing facilities and processes as well as to proposed modifications to existing facilities and processes. The hazard screening process evaluates an identified hazards in terms of the effects on people, both on-site and off-site. The process uses bounding analyses with no credit given for mitigation of an accident with the exception of certain containers meeting DOT specifications. The process is restricted to human safety issues only. Environmental effects are addressed by the environmental program. Interfaces with environmental organizations will be established in order to share information.

Computer virus information update CIAC-2301

Energy Technology Data Exchange (ETDEWEB)

Orvis, W.J.

1994-01-15

While CIAC periodically issues bulletins about specific computer viruses, these bulletins do not cover all the computer viruses that affect desktop computers. The purpose of this document is to identify most of the known viruses for the MS-DOS and Macintosh platforms and give an overview of the effects of each virus. The authors also include information on some windows, Atari, and Amiga viruses. This document is revised periodically as new virus information becomes available. This document replaces all earlier versions of the CIAC Computer virus Information Update. The date on the front cover indicates date on which the information in this document was extracted from CIAC`s Virus database.

Forklift safety a practical guide to preventing powered industrial truck incidents and injuries

CERN Document Server

Swartz, George

1999-01-01

Written for the more than 1.5 million powered industrial truck operators and supervisors in general industry, as well as those in the construction and marine industries, this Second Edition provides an updated guide to training operators in safety and complying with OSHA's 1999 forklift standard. This edition of Forklift Safety includes a new chapter devoted to the new OSHA 1910.178 standard and new information regarding dock safety, narrow aisle trucks, off-dock incidents, tip-over safety, pallet safety, and carbon monoxide.

Green light for the methodology file. Periodical safety review 2016 has begun

International Nuclear Information System (INIS)

2014-01-01

Every ten years, the organisational framework and the facilities of the Belgian Nuclear Research Center SCK-CEN are subject to an encompassing safety evaluation. Together with initiatives arising from the stress tests, a large number of safety studies and actions are scheduled until 2018. The article discusses the ongoing safety review.

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

CERN Document Server

Smith, David J

2010-01-01

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

Preclosure Safety Analysis Guide

International Nuclear Information System (INIS)

D.D. Orvis

2003-01-01

A preclosure safety analysis (PSA) is a required element of the License Application (LA) for the high- level radioactive waste repository at Yucca Mountain. This guide provides analysts and other Yucca Mountain Repository Project (the Project) personnel with standardized methods for developing and documenting the PSA. The definition of the PSA is provided in 10 CFR 63.2, while more specific requirements for the PSA are provided in 10 CFR 63.112, as described in Sections 1.2 and 2. The PSA requirements described in 10 CFR Part 63 were developed as risk-informed performance-based regulations. These requirements must be met for the LA. The PSA addresses the safety of the Geologic Repository Operations Area (GROA) for the preclosure period (the time up to permanent closure) in accordance with the radiological performance objectives of 10 CFR 63.111. Performance objectives for the repository after permanent closure (described in 10 CFR 63.113) are not mentioned in the requirements for the PSA and they are not considered in this guide. The LA will be comprised of two phases: the LA for construction authorization (CA) and the LA amendment to receive and possess (R and P) high-level radioactive waste (HLW). PSA methods must support the safety analyses that will be based on the differing degrees of design detail in the two phases. The methods described herein combine elements of probabilistic risk assessment (PRA) and deterministic analyses that comprise a risk-informed performance-based safety analysis. This revision to the PSA guide was prepared for the following objectives: (1) To correct factual and typographical errors. (2) To provide additional material suggested from reviews by the Project, the U.S. Department of Energy (DOE), and U.S. Nuclear Regulatory Commission (NRC) Staffs. (3) To update material in accordance with approaches and/or strategies adopted by the Project. In addition, a principal objective for the planned revision was to ensure that the methods and

ILK statement about the BMU project of updating nuclear rules and regulations

International Nuclear Information System (INIS)

2007-01-01

In 2003, the German Federal Ministry for the Environment (BMU) started its ''Updating Nuclear Rules and Regulations'' project. Proposals to this effect are currently in revision phase B. They comprise a total of eleven main topics, referred to as modules, under the heading of ''Basic Principles of Safety of Nuclear Power Plants - Safety Requirements in Accordance with the State of the Art.'' The International Nuclear Technology Committee (ILK), in 2005, dealt with the requirements to be met in an up-to-date code of nuclear rules and regulations. Its findings were published in a total of 10 recommendations. The current revision B of the 11 modules contains no discernible incorporation of these recommendations. ILK therefore once more dealt with the BMU project. A summary of its deliberations is available. ILK finds that the safety requirements to be met by nuclear power plants as outlined in the BMU draft are unable to support the implementation of the German Atomic Energy Act. In earlier statements, ILK had written that it deemed updating the code of rules and regulations desirable. The existing draft contains many elements serving this purpose, such as the inclusion of off-power conditions and a more pronounced incorporation of matters of organization and management. The main shortcomings of the present draft are identified and analyzed. (orig.)

SCALE 5: Powerful new criticality safety analysis tools

International Nuclear Information System (INIS)

Bowman, Stephen M.; Hollenbach, Daniel F.; Dehart, Mark D.; Rearden, Bradley T.; Gauld, Ian C.; Goluoglu, Sedat

2003-01-01

Version 5 of the SCALE computer software system developed at Oak Ridge National Laboratory, scheduled for release in December 2003, contains several significant new modules and sequences for criticality safety analysis and marks the most important update to SCALE in more than a decade. This paper highlights the capabilities of these new modules and sequences, including continuous energy flux spectra for processing multigroup problem-dependent cross sections; one- and three-dimensional sensitivity and uncertainty analyses for criticality safety evaluations; two-dimensional flexible mesh discrete ordinates code; automated burnup-credit analysis sequence; and one-dimensional material distribution optimization for criticality safety. (author)

NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 10, March 2009

International Nuclear Information System (INIS)

2009-03-01

The current issue contains information about the following meetings: Application of the Code of Conduct on the Safety of Research Reactors (the 'Code'). Environmental Modelling for Radiation Safety (EMRAS II); Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (the Joint Convention). The document also gives an overview on International Nuclear Security Advisory Service (INSServ)

Safety evaluation report related to the operation of Millstone Nuclear Power Station, Unit No. 3 (Docket No. 50-423)

International Nuclear Information System (INIS)

1985-09-01

The Safety Evaluation Report issued in August 1984 provided the results of the NRC staff review of Northeast Nuclear Energy Company's application for a license to operate the Millstone Nuclear Power Station, Unit No. 3. Supplement No. 1 to that report, issued in March 1985 updated the information contained in the Safety Evaluation Report and addressed the ACRS Report issued on September 10, 1984. The Report, Supplement No. 2 updates the information contained in the Safety Evaluation Report and Supplement No. 1 and addresses prior unresolved items. The facility is located in Waterford Township, New London, Connecticut. 11 refs., 9 tabs

Update on Intra-Arterial Chemotherapy for Retinoblastoma

Directory of Open Access Journals (Sweden)

Mario Zanaty

2014-01-01

Full Text Available The tools for managing retinoblastoma have been increasing in the past decade. While globe-salvage still relies heavily on intravenous chemotherapy, tumors in advanced stage that failed chemotherapy are now referred for intra-arterial chemotherapy (IAC to avoid enucleation. However, IAC still has many obstacles to overcome. We present an update on the indications, complications, limitations, success, and technical aspects of IAC. Given its safety and high efficacy, it is expected that IAC will replace conventional strategies and will become a first-line option even for tumors that are amenable for other strategies.

Neural basis for dynamic updating of object representation in visual working memory.

Science.gov (United States)

Takahama, Sachiko; Miyauchi, Satoru; Saiki, Jun

2010-02-15

In real world, objects have multiple features and change dynamically. Thus, object representations must satisfy dynamic updating and feature binding. Previous studies have investigated the neural activity of dynamic updating or feature binding alone, but not both simultaneously. We investigated the neural basis of feature-bound object representation in a dynamically updating situation by conducting a multiple object permanence tracking task, which required observers to simultaneously process both the maintenance and dynamic updating of feature-bound objects. Using an event-related design, we separated activities during memory maintenance and change detection. In the search for regions showing selective activation in dynamic updating of feature-bound objects, we identified a network during memory maintenance that was comprised of the inferior precentral sulcus, superior parietal lobule, and middle frontal gyrus. In the change detection period, various prefrontal regions, including the anterior prefrontal cortex, were activated. In updating object representation of dynamically moving objects, the inferior precentral sulcus closely cooperates with a so-called "frontoparietal network", and subregions of the frontoparietal network can be decomposed into those sensitive to spatial updating and feature binding. The anterior prefrontal cortex identifies changes in object representation by comparing memory and perceptual representations rather than maintaining object representations per se, as previously suggested. Copyright 2009 Elsevier Inc. All rights reserved.

Technology Road-map Update for Generation IV Nuclear Energy Systems

International Nuclear Information System (INIS)

2014-01-01

This Technology Road-map Update provides an assessment of progress made by the Generation IV International Forum (GIF) in the development of the six systems selected when the original Technology Road-map was published in 2002. More importantly, it provides an overview of the major R and D objectives and milestones for the coming decade, aiming to achieve the Generation IV goals of sustainability, safety and reliability, economic competitiveness, proliferation resistance and physical protection. Lessons learnt from the Fukushima Daiichi nuclear power plant accident are taken into account to ensure that Generation IV systems attain the highest levels of safety, with the development of specific safety design criteria that are applicable across the six systems. Accomplishing the ten-year R and D objectives set out in this new Road-map should allow the more advanced Generation IV systems to move towards the demonstration phase. (authors)

The nuclear law: safety. 2006-2010

International Nuclear Information System (INIS)

Bringuier, P.

2010-01-01

The author discusses the legal evolutions related to nuclear safety between 2006 and 2010. He identifies three main topics of unequal importance. Firstly, he comments the implementation of an international reference framework which has been completed at the European level and which aims at the harmonization of safety and security rules. Secondly, he comments the creation of the French Nuclear Safety Authority (ASN, Autorite de Surete Nucleaire). Thirdly, he comments the recast of the standard framework in order to update the French law with respect to the international reference framework. This leaded to a new distribution of power and authority, to more complete and constraining procedures, and to the definition of procedures for each step of an installation life cycle

242-A evaporator safety analysis report

International Nuclear Information System (INIS)

Campbell, T.A.

1998-01-01

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

Prostate specific antigen - brief update on its clinical use | Heyns ...

African Journals Online (AJOL)

Prostate specific antigen - brief update on its clinical use. ... (45 years in those with a family history of prostate cancer and – possibly – African men); ... PSA doubling time (the period it takes for the PSA to double) correlates with the prognosis ...

NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 12, September 2009

International Nuclear Information System (INIS)

2009-09-01

The current issue presents information about the following topics: Nuclear Security Report 2009; G8 Nuclear Safety and Security Group (NSSG); Uranium Production Site Appraisal Team (UPSAT); New Entrant Nuclear Power Programmes Safety Guide on the Establishment of the Safety Infrastructure (DS424)

Comparative approach between nuclear safety and security

International Nuclear Information System (INIS)

2009-04-01

Adopting the definition of nuclear safety and nuclear security as they are specified by IAEA glossaries, this report first outlines that these both notions refer to similar risks but with causes of different nature. They discuss the notions of transparency and confidentiality and outline that security and safety both aims at the protection of population and of the environment. They discuss their organisational principles, notice that both have their own legal and regulatory framework, that authorities have expertise on both, that the responsibility is distributed among operators and the State, and that safety and security cultures are complementary. They analyse the design, exploitation and management principles of security and safety approaches: graded approach, defence-in-depth, synergy between security and safety, same daily monitoring requirement, same necessity to address the return on experience, same need to update a referential, a more constrained exchange of good practices in safety, a necessity to deal with their respective requirements, elaboration of emergency plans, performance of exercises

The Policy on Gender Equality in Denmark - Update

DEFF Research Database (Denmark)

Agustin, Lise Rolandsen

Upon request of the FEMM committee, this in-depth analysis updates a previous note published in October 2011 and describes Danish policies, practices and legislation within the area of women's rights and gender equality, covering the period from October 2011, when the Social Democrat-led government...... took office, to April 2015. During this period, the focus has been put on gender-based violence, leave policies, pay statistics, gender segregation in the labour market and in education, as well as sexual and reproductive health and rights. Earmarked leave for fathers and gender quota on company boards...

Kozloduy nuclear power plant. Units 1-4. Status of safety assessment activities. Rev. 2

International Nuclear Information System (INIS)

1999-01-01

This paper presents the results of the status of safety assessment activities carried out by the Kozloduy Nuclear Power Plant (KNPP) in order to evaluate the current status of the safety of its reactor units 1-4. The steam supply system of this units is based of the reactor WWER-440/ B-230, which is a PWR of Russian design developed according to the safety standards in force in USSR in late 60-s. Now a days 10 reactor units of this type are in operation in four NPPs. Despite of efforts of the different plants to implement safety improvements measures during first 10-15 years of operation of this type of reactor its major safety problems were not eliminated and were a subject of international concern. The systematic evaluation of the deficiencies of the original design of this type of reactors have been initiated by IAEA in the beginning of 1990 and brought to developing a comprehensive list of safety problems which required urgent implementation of safety measures in all plants. To solve this problems in 1991 KNPP initiated implementation of so called 'short term' safety improvement program, developed with the help of WANO under agreement with Bulgarian Nuclear Safety Authority (BNSA) and consortium RISKAUDIT. The program was based on a stage approach and was foreseen to be implemented by tree stages in very tight time schedule in order to achieve significant and rapid improvements of the level of safety in operation of the units. The Short Tenn Program was implemented between the years 1991 and 1997 thanks of the strong safety commitment of NEK and KNPP staff and the broad international cooperation and financial support. Important part of resources were supplied under PHARE program of CEC, EBRD grant agreement and EDF support. The plant current safety level analysis has been performed using IAEA analytical methodology according to 50-SG-O12 standard 'Periodic safety review of operational nuclear power plants'. The approach and criteria for acceptable safety level

Project SFR 1 SAR-08. Update of priority of FEPs from Project SAFE

International Nuclear Information System (INIS)

Gordon, Anna; Loefgren, Martin; Lindgren, Maria

2008-03-01

SFR 1 is a repository for final disposal of low and intermediate level radioactive waste produced at Swedish nuclear power plants, as well as at Swedish industrial, research, and medical treatment facilities. The repository obtained operational license in March 1988. The aim of Project SFR 1 SAR-08 is to perform an updated safety analysis, according to requirements in the regulations. A major difference between this and previous safety analyses is that repository safety should be demonstrated for 100,000 years after repository closure. This should be compared with the time frame of the safety assessment in Project SAFE that was 10,000 years. Due to the extended time frame, permafrost and glaciation have to be considered in the reference evolution of Project SFR 1 SAR-08. Other rationales for the update are recent input from the authorities concerning SAFE documents and the SFR 1 repository, as well as new data concerning the SFR 1 inventory. This report describes the outcome of revisiting the qualitative FEP (Features, Events and Processes) analysis carried out within Project SAFE for the SFR 1 repository. Each and every interaction definition, as defined in SAFE, has been examined with the aim at assuring that the SAFE interaction matrices are also applicable for SAR-08. It was found that this is generally the case, but seven new interactions were defined in order to make the interaction matrices more applicable for SAR-08. The priority of all interactions assigned priority 1 and many interactions assigned priority 2 in SAFE have been carefully examined. The examination has been made in the context of the general initial and boundary conditions that should also form the basis for the SAR-08 main scenario and less probable scenarios. In 48 cases, the priority of the interaction needed upgrading, compared to in SAFE. In a majority of these cases, the upgrade is due to the extended time frame of the safety assessment, from 10,000 years in SAFE to 100,000 years in SAR

Project SFR 1 SAR-08. Update of priority of FEPs from Project SAFE

Energy Technology Data Exchange (ETDEWEB)

Gordon, Anna (Swedish Nuclear Fuel and Waste Management Co., Stockholm (SE)); Loefgren, Martin; Lindgren, Maria (Kemakta Konsult AB, Stockholm (SE)) (eds.)

2008-03-15

SFR 1 is a repository for final disposal of low and intermediate level radioactive waste produced at Swedish nuclear power plants, as well as at Swedish industrial, research, and medical treatment facilities. The repository obtained operational license in March 1988. The aim of Project SFR 1 SAR-08 is to perform an updated safety analysis, according to requirements in the regulations. A major difference between this and previous safety analyses is that repository safety should be demonstrated for 100,000 years after repository closure. This should be compared with the time frame of the safety assessment in Project SAFE that was 10,000 years. Due to the extended time frame, permafrost and glaciation have to be considered in the reference evolution of Project SFR 1 SAR-08. Other rationales for the update are recent input from the authorities concerning SAFE documents and the SFR 1 repository, as well as new data concerning the SFR 1 inventory. This report describes the outcome of revisiting the qualitative FEP (Features, Events and Processes) analysis carried out within Project SAFE for the SFR 1 repository. Each and every interaction definition, as defined in SAFE, has been examined with the aim at assuring that the SAFE interaction matrices are also applicable for SAR-08. It was found that this is generally the case, but seven new interactions were defined in order to make the interaction matrices more applicable for SAR-08. The priority of all interactions assigned priority 1 and many interactions assigned priority 2 in SAFE have been carefully examined. The examination has been made in the context of the general initial and boundary conditions that should also form the basis for the SAR-08 main scenario and less probable scenarios. In 48 cases, the priority of the interaction needed upgrading, compared to in SAFE. In a majority of these cases, the upgrade is due to the extended time frame of the safety assessment, from 10,000 years in SAFE to 100,000 years in SAR

Project SFR 1 SAR-08. Update of priority of FEPs from Project SAFE

Energy Technology Data Exchange (ETDEWEB)

Gordon, Anna [Swedish Nuclear Fuel and Waste Management Co., Stockholm (SE); Loefgren, Martin; Lindgren, Maria [Kemakta Konsult AB, Stockholm (SE); eds.

2008-03-15

SFR 1 is a repository for final disposal of low and intermediate level radioactive waste produced at Swedish nuclear power plants, as well as at Swedish industrial, research, and medical treatment facilities. The repository obtained operational license in March 1988. The aim of Project SFR 1 SAR-08 is to perform an updated safety analysis, according to requirements in the regulations. A major difference between this and previous safety analyses is that repository safety should be demonstrated for 100,000 years after repository closure. This should be compared with the time frame of the safety assessment in Project SAFE that was 10,000 years. Due to the extended time frame, permafrost and glaciation have to be considered in the reference evolution of Project SFR 1 SAR-08. Other rationales for the update are recent input from the authorities concerning SAFE documents and the SFR 1 repository, as well as new data concerning the SFR 1 inventory. This report describes the outcome of revisiting the qualitative FEP (Features, Events and Processes) analysis carried out within Project SAFE for the SFR 1 repository. Each and every interaction definition, as defined in SAFE, has been examined with the aim at assuring that the SAFE interaction matrices are also applicable for SAR-08. It was found that this is generally the case, but seven new interactions were defined in order to make the interaction matrices more applicable for SAR-08. The priority of all interactions assigned priority 1 and many interactions assigned priority 2 in SAFE have been carefully examined. The examination has been made in the context of the general initial and boundary conditions that should also form the basis for the SAR-08 main scenario and less probable scenarios. In 48 cases, the priority of the interaction needed upgrading, compared to in SAFE. In a majority of these cases, the upgrade is due to the extended time frame of the safety assessment, from 10,000 years in SAFE to 100,000 years in SAR

IAEA codes and guides for safety of nuclear power plants

International Nuclear Information System (INIS)

Raisic, N.

1980-01-01

The objectives and scope of the Agency's programme of nuclear safety standards are described and the role of these documents in regulation of nuclear power im Member States is discussed. For each of the five areas of safety standards development, i.e. siting, design, operation, quality assurance and governmental organization, a set of principles underlying requirements and recommendations contained in the Code of Practice and Safety Guides will be presented. Safety Guides in each of the five areas will be reviewed in respect of the scope and content. A consideration will be given to the future development of the safety standards and to the revision and updating of the published documents. (orig./RW)

NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security. Issue no. 4, June 2007

International Nuclear Information System (INIS)

2007-04-01

This newsletter contains information on the Centre for Advanced Safety Assessment Tools (CASAT), the new strategy for the recovery of radioactive sources, the Technical Support Organization Conference and a message form the Director of the Division of Nuclear Installation Safety. To improve the efficiency of safety assessment methods, ensure transparency in their validation and application and establish an excellent knowledge base and training programmes, the IAEA's Centre for Advanced Safety Assessment Tools (CASAT) has therefore been formed. The Centre addresses the need for continuous technical support mechanisms for safety assessment methods. It provides support to Member States to enhance their safety assessment capabilities for present and future generations of nuclear systems, with a special focus on countries with a developing nuclear technology and nuclear safety infrastructure. It serves as a consolidated repository of relevant safety analysis knowledge, provides for focused training including advanced analytical simulations, and supports collaboration on safety assessment projects among Member States. The resources provided through CASAT include codes, models, databases, verification and validation information, analytical procedures and guides. The main purpose of the recently established Radioactive Source Technical Coordination Group (RSTCG) is to facilitate the technical coordination of activities of the IAEA related to the control and management of radioactive sources through the development of common approaches in technical matters and to advise the management of the relevant Divisions. It is the task of the RSTCG to provide the programme managers of the participating divisions/sections with a common opinion/advice on technical issues related to the control and management of radioactive sources. The RSTCG members obtain, inter alia from programme managers, information on all relevant project proposals, and share relevant materials in due time to

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.)

International conference on the operational safety performance in nuclear installations. Contributed papers

International Nuclear Information System (INIS)

2005-01-01

In 2001, the IAEA organized an 'International Conference on Topical Issues in Nuclear Safety'. The issues discussed during the conference were: (1) risk- informed decision-making; (2) influence of external factors on safety; (3) safety of fuel cycle facilities; (4) safety of research reactors; and (5) safety performance indicators. Senior nuclear safety decision makers reviewed the issues and formulated recommendations for future actions by national and international organizations. In 2004, the IAEA organized an 'International Conference on Topical Issues in Nuclear Safety' in Beijing China. The issues discussed during the conference were: (1) changing environment - coping with diversity and globalization; (2) operating experience - managing changes effectively; (3) regulatory management systems - adapting to changes in the environment; and (4) long term operations - maintaining safety margins while extending plant lifetimes. The results of this conference confirmed the importance of operators and regulators of nuclear facilities meeting periodically to share experience and opinion on emerging issues and future challenges of the nuclear industry. Substantial progress has been made, and continues to be made by Member States in enhancing the safety of nuclear installations worldwide. At the same time, more attention is being given to other areas of nuclear safety. The safety standards for research reactors are being updated and new standards are planned on the safety of other facilities in the nuclear fuel cycle. The Agency has taken a lead role in this effort and is receiving much support from its Member States to gain international consensus in these areas. The objective of the conference is to foster the exchange of information on operational safety performance and operating experience in nuclear installations, with the aim of consolidating an international consensus on: - the present status of these issues; - emerging issues with international implications

Technical guidelines for the seismic safety re-evaluation at Eastern European NPPs

International Nuclear Information System (INIS)

Godoy, A.R.; Guerpinar, A.

2001-01-01

The paper describes one of the outcomes of the Engineering Safety Review Services (ESRS) that the IAEA provides as an element of the Agency's national, regional and interregional technical assistance and co-operation programmes and other extrabudgetary programmes to assess the safety of nuclear facilities. This refers to the establishment of detailed guidelines for conducting the seismic safety re-evaluation of existing nuclear power plants in Eastern European countries in line with updated criteria and current international practice. (author)

Safety analysis SFR 1. Long-term safety

Energy Technology Data Exchange (ETDEWEB)

2008-12-15

An updated assessment of the long-term safety of SKB's final repository for radioactive operational waste, SFR 1, is presented in this report. The report is included in the safety analysis report for SFR 1. The most recent account of long-term safety was submitted to the regulatory authorities in 2001. The present report has been compiled on SKB's initiative to address the regulatory authorities' viewpoints regarding the preceding account of long-term safety. Besides the new mode of working with safety functions there is another important difference between the 2001 safety assessment and the current assessment: The time horizon in the current assessment has been extended to 100,000 years in order to include the effect of future climate changes. The purpose of this renewed assessment of the long-term safety of SFR 1 is to show with improved data that the repository is capable of protecting human health and the environment against ionizing radiation in a long-term perspective. This is done by showing that calculated risks lie below the risk criteria stipulated by the regulatory authorities. SFR 1 is built to receive, and after closure serve as a passive repository for, low. and intermediate-level radioactive waste. The disposal chambers are situated in rock beneath the sea floor, covered by about 60 metres of rock. The underground part of the facility is reached via two tunnels whose entrances are near the harbour. The repository has been designed so that it can be abandoned after closure without further measures needing to be taken to maintain its function. The waste in SFR 1 is short-lived low- and intermediate-level waste. After 100 years the activity is less than half, and after 1,000 years only about 2% of the original activity remains. The report on long-term safety comprises eleven chapters. Chapter 1 Introduction. The chapter describes the purpose, background, format and contents of SAR-08, applicable regulations and injunctions, and the regulatory

Safety analysis SFR 1. Long-term safety

International Nuclear Information System (INIS)

2008-12-01

An updated assessment of the long-term safety of SKB's final repository for radioactive operational waste, SFR 1, is presented in this report. The report is included in the safety analysis report for SFR 1. The most recent account of long-term safety was submitted to the regulatory authorities in 2001. The present report has been compiled on SKB's initiative to address the regulatory authorities' viewpoints regarding the preceding account of long-term safety. Besides the new mode of working with safety functions there is another important difference between the 2001 safety assessment and the current assessment: The time horizon in the current assessment has been extended to 100,000 years in order to include the effect of future climate changes. The purpose of this renewed assessment of the long-term safety of SFR 1 is to show with improved data that the repository is capable of protecting human health and the environment against ionizing radiation in a long-term perspective. This is done by showing that calculated risks lie below the risk criteria stipulated by the regulatory authorities. SFR 1 is built to receive, and after closure serve as a passive repository for, low. and intermediate-level radioactive waste. The disposal chambers are situated in rock beneath the sea floor, covered by about 60 metres of rock. The underground part of the facility is reached via two tunnels whose entrances are near the harbour. The repository has been designed so that it can be abandoned after closure without further measures needing to be taken to maintain its function. The waste in SFR 1 is short-lived low- and intermediate-level waste. After 100 years the activity is less than half, and after 1,000 years only about 2% of the original activity remains. The report on long-term safety comprises eleven chapters. Chapter 1 Introduction. The chapter describes the purpose, background, format and contents of SAR-08, applicable regulations and injunctions, and the regulatory

Safety analysis SFR 1. Long-term safety

Energy Technology Data Exchange (ETDEWEB)

2008-12-15

An updated assessment of the long-term safety of SKB's final repository for radioactive operational waste, SFR 1, is presented in this report. The report is included in the safety analysis report for SFR 1. The most recent account of long-term safety was submitted to the regulatory authorities in 2001. The present report has been compiled on SKB's initiative to address the regulatory authorities' viewpoints regarding the preceding account of long-term safety. Besides the new mode of working with safety functions there is another important difference between the 2001 safety assessment and the current assessment: The time horizon in the current assessment has been extended to 100,000 years in order to include the effect of future climate changes. The purpose of this renewed assessment of the long-term safety of SFR 1 is to show with improved data that the repository is capable of protecting human health and the environment against ionizing radiation in a long-term perspective. This is done by showing that calculated risks lie below the risk criteria stipulated by the regulatory authorities. SFR 1 is built to receive, and after closure serve as a passive repository for, low. and intermediate-level radioactive waste. The disposal chambers are situated in rock beneath the sea floor, covered by about 60 metres of rock. The underground part of the facility is reached via two tunnels whose entrances are near the harbour. The repository has been designed so that it can be abandoned after closure without further measures needing to be taken to maintain its function. The waste in SFR 1 is short-lived low- and intermediate-level waste. After 100 years the activity is less than half, and after 1,000 years only about 2% of the original activity remains. The report on long-term safety comprises eleven chapters. Chapter 1 Introduction. The chapter describes the purpose, background, format and contents of SAR-08, applicable regulations and injunctions, and the

An Updated Examination of Aviation Accidents Associated with Turbulence, Wind Shear and Thunderstorm

Science.gov (United States)

Evans, Joni K.

2014-01-01

One of the technical challenges within the Atmospheric Environment Safety Technologies (AEST) Project of the Aviation Safety Program was to "improve and expand remote sensing and mitigation of hazardous atmospheric environments and phenomena"1. In 2012, the author performed an analysis comparing various characteristics of accidents associated with different types of atmospheric hazard environments2. This document reports an update to that analysis which was done in preparation for presenting these findings at the 2015 annual meeting of the Transportation Research Board. Specifically, an additional three years of data were available, and a time-trend analysis was added.

The Nordic nuclear safety research 1990-93. Evalution and executive summary

International Nuclear Information System (INIS)

Marcus, F.

1994-11-01

A four-year Nordic research programme in the field of nuclear safety was carried through from 1990 through 1993, performed under the auspices of the Nordic Committee for Nuclear Safety Research, NKS. The aim has been to increase knowledge required to judge the safety of nuclear installations in and around the Nordic areas, and to improve and harmonize emergency preparedness. There were 19 individual projects within the four main section of the programme: Emergency preparedness, Waste and decommissioning, Radioecology, and Reactor safety. The programme was evaluated in 1994 by five evaluators, and the main emphasis was on general questions. The evaluators recommend that project plans are revised at mid-term, for updating. During the project period, NKS should use specified criteria to judge progress and success. Time tables must be adhered to. Recommendations deal with reporting and presentation of results, project leaders must disseminate information at the professional level and organize seminars. The NKS annual reports should be conceived so that they can also be used for external information. NKS should establish a policy aimed at enhanced information on its projects. Final reports should contain conclusions and recommendations which can subsequently be followed up. Directors of the competent authorities in the Nordic countries should be requested to give their views on the recommendations, and also industry, on the usefulness of results. It is proposed that NKS consider presentation of the outcome to responsible ministers and their staff. These recommendations were taken into account during 1994. (AB)

Draft pilot report - Approaches to the resolution of safety issues

International Nuclear Information System (INIS)

2006-01-01

comparative analysis of the status of resolution of the safety issues in the member countries as it would require additional time and manpower. Nonetheless, it can be maintained as a living document and updated periodically as needed

Update schemes of multi-velocity floor field cellular automaton for pedestrian dynamics

Science.gov (United States)

Luo, Lin; Fu, Zhijian; Cheng, Han; Yang, Lizhong

2018-02-01

Modeling pedestrian movement is an interesting problem both in statistical physics and in computational physics. Update schemes of cellular automaton (CA) models for pedestrian dynamics govern the schedule of pedestrian movement. Usually, different update schemes make the models behave in different ways, which should be carefully recalibrated. Thus, in this paper, we investigated the influence of four different update schemes, namely parallel/synchronous scheme, random scheme, order-sequential scheme and shuffled scheme, on pedestrian dynamics. The multi-velocity floor field cellular automaton (FFCA) considering the changes of pedestrians' moving properties along walking paths and heterogeneity of pedestrians' walking abilities was used. As for parallel scheme only, the collisions detection and resolution should be considered, resulting in a great difference from any other update schemes. For pedestrian evacuation, the evacuation time is enlarged, and the difference in pedestrians' walking abilities is better reflected, under parallel scheme. In face of a bottleneck, for example a exit, using a parallel scheme leads to a longer congestion period and a more dispersive density distribution. The exit flow and the space-time distribution of density and velocity have significant discrepancies under four different update schemes when we simulate pedestrian flow with high desired velocity. Update schemes may have no influence on pedestrians in simulation to create tendency to follow others, but sequential and shuffled update scheme may enhance the effect of pedestrians' familiarity with environments.

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

International Nuclear Information System (INIS)

1991-12-01

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

An update on safety and immunogenicity of vaccines containing emulsion-based adjuvants.

Science.gov (United States)

Fox, Christopher B; Haensler, Jean

2013-07-01

With the exception of alum, emulsion-based vaccine adjuvants have been administered to far more people than any other adjuvant, especially since the 2009 H1N1 influenza pandemic. The number of clinical safety and immunogenicity evaluations of vaccines containing emulsion adjuvants has correspondingly mushroomed. In this review, the authors introduce emulsion adjuvant composition and history before detailing the most recent findings from clinical and postmarketing data regarding the effects of emulsion adjuvants on vaccine immunogenicity and safety, with emphasis on the most widely distributed emulsion adjuvants, MF59® and AS03. The authors also present a summary of other emulsion adjuvants in clinical development and indicate promising avenues for future emulsion-based adjuvant development. Overall, emulsion adjuvants have demonstrated potent adjuvant activity across a number of disease indications along with acceptable safety profiles.

Safety evaluation in the development of medical devices and combination products

CERN Document Server

Gad, Shayne C

2008-01-01

Capturing the growth of the global medical device market in recent years, this practical new guide is essential for all who are responsible for ensuring safety in the use and manufacture of medical devices. It has been extensively updated to reflect significant advances, incorporating combination products and helpful case examples of current real-life problems in the field.The Third Edition explores these key current trends:global device marketscontinually advancing technologythe increasing harmonization of device safety regulation worldwideEach aspect of safety evaluation is considered in ter

Safety Case for Service Contracts

Energy Technology Data Exchange (ETDEWEB)

Martinez, Israel L.

2014-07-01

Safety cases developed for the Facilities Management and Operations Center (FMOC) are based on the requirements in MN471021, Work Planning and Control Criteria for Safe Design and Operations. The FMOC performs maintenance activities in various locations at Sandia National Laboratories, New Mexico (SNL/NM). SNL/NM consists of more than 6,000,000 square feet of buildings, structures, and site infrastructure on approximately 13,000 acres of land. The FMOC performs approximately 7500 service contract work orders a year to assist with operations and maintenance at the SNL/NM site and facilities. As part of the continual improvement process, this Safety Case will be reviewed and updated, as needed, or at a minimum every three years.

75 FR 76928 - Safety Management System for Certificated Airports; Extension of Comment Period

Science.gov (United States)

2010-12-10

...-0997; Notice No. 10-14] RIN 2120-AJ38 Safety Management System for Certificated Airports; Extension of... holder to establish a safety management system (SMS) for its entire airfield environment (including... ``Safety Management System for Certificated Airports'' (75 FR 62008). Comments to that document were to be...

NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 6, March 2008

International Nuclear Information System (INIS)

2008-03-01

The current issue presents information about the following activities: 1) International Conference on Illicit Nuclear Trafficking which took place in November 2007 in Edinburgh. The principal aim of the conference was to examine the threat and context of illicit nuclear trafficking of radioactive material, specifically, what is being done to combat such trafficking and where more needs to be done. The conference was also to consider how the obligations and commitments of the legally binding and non-binding international instruments could be and are being implemented by various States. 2) INSAG Message on Nuclear Safety Infrastructure in which the INSAG Chairman Richard Meserve addressed nuclear safety in the current context and various issues that warrant special attention. 3) approved for publication the Safety Requirements publication on Safety of Nuclear Fuel Cycle Facilities. 4) The Asian Nuclear Safety Network (ANSN)

Consideration of timescales in the finnish safety regulations for spent fuel disposal

International Nuclear Information System (INIS)

Ruokola, E.

2010-01-01

Esko Ruokola (STUK) presented an example of regulatory approach and explained that the Finnish spent fuel disposal program is progressing towards the construction license stage. The Government Decree on the Safety of Nuclear Waste Disposal which entered into force on 1 St December 2008 will be detailed by a STUK Guide that is currently being updated. These regulations distinguish three post-closure time periods for which different safety criteria are defined: The Environmentally Predictable Future: During this first period, extending up to several thousands of years, predictable environmental changes will occur. People may be exposed to the disposed radioactive substances only due to limited early failures of engineered barriers, due to e.g. fabrication defects. Disposal shall be so designed that as a consequence of expected evolutions: 1. The annual dose to the most exposed members of the public shall remain below 0.1 mSv. 2. The average annual doses to other members of the public shall remain insignificantly low. STUK provides guidance for the different elements of the safety assessment including potential exposure pathways, potential changes in the environment to be considered, assumption on climate change and human habits, as well as the reference conditions for the most exposed individual and people living in the surroundings. Era of Extreme Climate Changes: Beyond about 10 000 years, great climatic changes, such as permafrost and glaciation, will occur and a conservative approach is followed. For this time period, the radiation protection criteria are based on release rates of radionuclides from the geosphere to biosphere (geo-bio flux constraints). The STUK guide specifies the nuclide specific constraints for the activity release to the environment for individual radionuclides. The selected approach by STUK implies that the implementer need not to consider the biosphere scenarios when preparing his safety case for the time period discussed as the regulator

Parametric Criticality Safety Calculations for Arrays of TRU Waste Containers

Energy Technology Data Exchange (ETDEWEB)

Gough, Sean T. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-10-26

The Nuclear Criticality Safety Division (NCSD) has performed criticality safety calculations for finite and infinite arrays of transuranic (TRU) waste containers. The results of these analyses may be applied in any technical area onsite (e.g., TA-54, TA-55, etc.), as long as the assumptions herein are met. These calculations are designed to update the existing reference calculations for waste arrays documented in Reference 1, in order to meet current guidance on calculational methodology.

Lessons Learned in Preparation and Review of Safety Analysis Report of PUSPATI TRIGA Reactor in Malaysia

Energy Technology Data Exchange (ETDEWEB)

Maskin, Mazleha [Korea Advanced Institute for Science and Technology, Daejeon (Korea, Republic of); Choi, Kwang Sik [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2010-05-15

PUSPATI TRIGA Reactor (RTP) is the one and only research reactor in Malaysia. Since the day it was supplied by General Atomic (GA) in 1983, periodic safety reviews were carried out but not published in the form of a complete SAR. In fact, the original SAR (SAR 1983) document was provided by GA as soon as GA was selected as the supplier of RTP. The focus of this report is on the lessons learned from the preparation of SAR. The lessons learned were to address the preparation and regulatory review of the second SAR (SAR 2006). Realizing that safety is important as RTP is aging, the experiences and lessons learned from SAR development and updating processes are of great value for all parties involved. The purpose of this report is to consolidate and organize the lessons learned and suggest the best practice for the next SAR development both in preparation and regulatory review

Lessons Learned in Preparation and Review of Safety Analysis Report of PUSPATI TRIGA Reactor in Malaysia

International Nuclear Information System (INIS)

Maskin, Mazleha; Choi, Kwang Sik

2010-01-01

PUSPATI TRIGA Reactor (RTP) is the one and only research reactor in Malaysia. Since the day it was supplied by General Atomic (GA) in 1983, periodic safety reviews were carried out but not published in the form of a complete SAR. In fact, the original SAR (SAR 1983) document was provided by GA as soon as GA was selected as the supplier of RTP. The focus of this report is on the lessons learned from the preparation of SAR. The lessons learned were to address the preparation and regulatory review of the second SAR (SAR 2006). Realizing that safety is important as RTP is aging, the experiences and lessons learned from SAR development and updating processes are of great value for all parties involved. The purpose of this report is to consolidate and organize the lessons learned and suggest the best practice for the next SAR development both in preparation and regulatory review

76 FR 12300 - Safety Management System for Certificated Airports; Extension of Comment Period

Science.gov (United States)

2011-03-07

...-0997; Notice No. 10-14] RIN 2120-AJ38 Safety Management System for Certificated Airports; Extension of...: Background On October 7, 2010, the FAA published Notice No. 10-14, entitled ``Safety Management System for... conclusions from the safety management systems proof of concept. The FAA anticipates making this report...

Nuclear safety

International Nuclear Information System (INIS)

Tarride, Bruno

2015-10-01

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

Development of an Updated Societal-Risk Goal for Nuclear Power Safety

Energy Technology Data Exchange (ETDEWEB)

Vicki Bier; Michael Corradini; Robert Youngblood; Caleb Roh; Shuji Liu

2014-07-01

This report briefly summarizes work done in FY 2013 on the subject LDRD. The working hypothesis is that societal disruption should be addressed in a safety goal. This is motivated by the point that the Fukushima disaster resulted in very little public dose, but enormous societal disruption; a goal that addressed societal disruption would fill a perceived gap in the US NRC safety goal structure. This year's work entailed analyzing the consequences of postulated accidents at various reactor sites in the US, specifically with a view to quantifying the number of people relocated and the duration of their relocation, to see whether this makes sense as a measure of societal disruption.

Correlation between safety climate and contractor safety assessment programs in construction.

Science.gov (United States)

Sparer, Emily H; Murphy, Lauren A; Taylor, Kathryn M; Dennerlein, Jack T

2013-12-01

Contractor safety assessment programs (CSAPs) measure safety performance by integrating multiple data sources together; however, the relationship between these measures of safety performance and safety climate within the construction industry is unknown. Four hundred and one construction workers employed by 68 companies on 26 sites and 11 safety managers employed by 11 companies completed brief surveys containing a nine-item safety climate scale developed for the construction industry. CSAP scores from ConstructSecure, Inc., an online CSAP database, classified these 68 companies as high or low scorers, with the median score of the sample population as the threshold. Spearman rank correlations evaluated the association between the CSAP score and the safety climate score at the individual level, as well as with various grouping methodologies. In addition, Spearman correlations evaluated the comparison between manager-assessed safety climate and worker-assessed safety climate. There were no statistically significant differences between safety climate scores reported by workers in the high and low CSAP groups. There were, at best, weak correlations between workers' safety climate scores and the company CSAP scores, with marginal statistical significance with two groupings of the data. There were also no significant differences between the manager-assessed safety climate and the worker-assessed safety climate scores. A CSAP safety performance score does not appear to capture safety climate, as measured in this study. The nature of safety climate in construction is complex, which may be reflective of the challenges in measuring safety climate within this industry. Am. J. Ind. Med. 56:1463-1472, 2013. © 2013 Wiley Periodicals, Inc. © 2013 Wiley Periodicals, Inc.

The Update of the Mexican Health Care Formulary and Supply Catalog in the Context of the Health Technology Assessment.

Science.gov (United States)

Ríos, Pedro Rizo; Rivera, Aurora González; Oropeza, Itzel Rivas; Ramírez, Odette Campos

2014-12-01

One of the instruments Mexico has available for the optimization of resources specifically allocated to health technologies is the Health Care Formulary and Supply Catalog (Cuadro Básico y Catálogo de Insumos del Sector Salud [CBCISS]). The aim of the CBCISS is to collaborate in the optimization of public resources through the use of technologies (supplies) that have proven their safety, therapeutic efficacy, and efficiency. The importance of the CBCISS lies in the fact that all public institutions within the National Health System must use only the established technologies it contains. The implementation of strategies that strengthen the CBCISS update process allows it to be thought of as an essential regulatory tool for the introduction of health technologies, with relevant contributions to the proper selection of cost-effective interventions. It ensures that each supply included on the list meets the criteria sufficient and necessary to ensure efficacy, safety, effectiveness, and, of course, efficiency, as evidence supporting the selection of suitable technologies. The General Health Council (Consejo de Salubridad General [CSG]) is a collegial body of constitutional origin that-in accordance with its authority-prepares, updates, publishes, and distributes the CBCISS. To perform these activities, the CSG has the CBCISS Inter-institutional Commission. The CBCISS update is performed through the processes of inclusion, modification, and exclusion of supplies approved by the Interior Commission. The CBCISS update process consists of three stages: the first stage involves a test that leads to the acceptance or inadmissibility of the requests, and the other two focus on an in-depth evaluation for the ruling. This article describes the experience of health technology assessment in Mexico, presents the achievements and outlines the improvements in the process of submission of new health technologies, and presents a preliminary analysis of the submissions evaluated

Sampling and Analysis Plan Update for Groundwater Monitoring 1100-EM-1 Operable Unit

International Nuclear Information System (INIS)

DR Newcomer

1999-01-01

This document updates the sampling and analysis plan (Department of Energy/Richland Operations--95-50) to reflect current groundwater monitoring at the 1100-EM-1Operable Unit. Items requiring updating included sampling and analysis protocol, quality assurance and quality control, groundwater level measurement procedure, and data management. The plan covers groundwater monitoring, as specified in the 1993 Record of Decision, during the 5-year review period from 1995 through 1999. Following the 5-year review period, groundwater-monitoring data will be reviewed by Environmental Protection Agency to evaluate the progress of natural attenuation of trichloroethylene. Monitored natural attenuation and institutional controls for groundwater use at the inactive Horn Rapids Landfill was the selected remedy specified in the Record of Decision

Transvaginal mesh in the media following the 2011 US food and drug administration public health notification update.

Science.gov (United States)

Koo, Kevin; Gormley, E Ann

2017-02-01

Prompted by patients' changing perceptions of transvaginal mesh, this study examines how mesh has been reported in the news following the 2011 US Food and Drug Administration (FDA) updated notification about the use of mesh in the treatment of pelvic organ prolapse. Two national newspaper databases were queried for articles discussing transvaginal mesh published within 3 years of the FDA announcement. Content analysis included headline subjects, mesh-related complications, quoted sources, and the FDA recommendations. To determine whether more widely read sources publish higher quality reporting, a subgroup analysis was conducted based on newspaper circulation. Ninety-five articles met inclusion criteria. Mesh-related litigation was the most common headline subject (36 articles, 38%), and 54% of all articles referenced legal action. Fifty-seven articles (60%) cited at least one mesh-related complication. Only 18 articles (19%) quoted surgeons who use transvaginal mesh. For the FDA update, 40% of articles that first reported the announcement accurately specified that it applies to mesh for prolapse, not incontinence. This ambiguity persisted: half of all articles cited the warning, but only 23% distinguished between prolapse and incontinence. Higher newspaper circulation did not significantly improve the quality of reporting about the content or context of the FDA's recommendations. Despite frequent media coverage of transvaginal mesh and its complications since 2011, very few news sources that cited the FDA warning distinguished between prolapse and incontinence. Given prevalent reporting of mesh-related litigation, the findings raise concern about how patients perceive the safety and efficacy of transvaginal mesh, regardless of indication. Neurourol. Urodynam. 36:329-332, 2017. © 2015 Wiley Periodicals, Inc. © 2015 Wiley Periodicals, Inc.

Information services directory: An Update of 5/87

International Nuclear Information System (INIS)

1989-03-01

The Information Services Directory is intended to facilitate dissemination of information. The Directory is produced by the Information Services Division of OCRWM's Office of External Relations and Policy and will be updated periodically. This is the second such update since its issuance in August 1986. It is a reference document that lists the sources of program information available to States, Indian Tribes and the public. Chapter I of this Directory describes current program information sources, including the OCRWM Bulletin, the Electronic Bulletin Board (INFOLINK) and other periodic publications produced by OCRWM and DOE's Office of Scientific and Technical Information (OSTI). Chapter II is an index of DOE, State and Federal Agency contacts. Chapter III provides a directory of DOE technical information and includes descriptions of computerized data bases and other resources. Chapter IV enumerates Congressional Committees and Subcommittees that have jurisdiction over various components of the Civilian Radioactive Waste Management Program, and Chapter V lists DOE Reading Rooms and Information Offices, NRC Local Public Document Rooms, and public libraries in the State of Nevada that are on one or more of OCRWM's mailing lists. Chapter VI is an index of systems and Chapter VII offers listings of selected publications

Safety balance: Analysis of safety systems; Bilans de surete: analyse par les organismes de surete

Energy Technology Data Exchange (ETDEWEB)

Delage, M; Giroux, C

1990-12-01

Safety analysis, and particularly analysis of exploitation of NPPs is constantly affected by EDF and by the safety authorities and their methodologies. Periodic safety reports ensure that important issues are not missed on daily basis, that incidents are identified and that relevant actions are undertaken. French safety analysis method consists of three principal steps. First type of safety balance is analyzed at the normal start-up phase for each unit including the final safety report. This enables analysis of behaviour of units ten years after their licensing. Second type is periodic operational safety analysis performed during a few years. Finally, the third step consists of safety analysis of the oldest units with the aim to improve the safety standards. The three steps of safety analysis are described in this presentation in detail with the aim to present the objectives and principles. Examples of most recent exercises are included in order to illustrate the importance of such analyses.

Updating a Classic: "The Poisson Distribution and the Supreme Court" Revisited

Science.gov (United States)

Cole, Julio H.

2010-01-01

W. A. Wallis studied vacancies in the US Supreme Court over a 96-year period (1837-1932) and found that the distribution of the number of vacancies per year could be characterized by a Poisson model. This note updates this classic study.

Well blowout rates in California Oil and Gas District 4--Update and Trends

Energy Technology Data Exchange (ETDEWEB)

Jordan, Preston D.; Benson, Sally M.

2009-10-01

Well blowouts are one type of event in hydrocarbon exploration and production that generates health, safety, environmental and financial risk. Well blowouts are variously defined as 'uncontrolled flow of well fluids and/or formation fluids from the wellbore' or 'uncontrolled flow of reservoir fluids into the wellbore'. Theoretically this is irrespective of flux rate and so would include low fluxes, often termed 'leakage'. In practice, such low-flux events are not considered well blowouts. Rather, the term well blowout applies to higher fluxes that rise to attention more acutely, typically in the order of seconds to days after the event commences. It is not unusual for insurance claims for well blowouts to exceed US$10 million. This does not imply that all blowouts are this costly, as it is likely claims are filed only for the most catastrophic events. Still, insuring against the risk of loss of well control is the costliest in the industry. The risk of well blowouts was recently quantified from an assembled database of 102 events occurring in California Oil and Gas District 4 during the period 1991 to 2005, inclusive. This article reviews those findings, updates them to a certain extent and compares them with other well blowout risk study results. It also provides an improved perspective on some of the findings. In short, this update finds that blowout rates have remained constant from 2005 to 2008 within the limits of resolution and that the decline in blowout rates from 1991 to 2005 was likely due to improved industry practice.

Evidence-based guideline update: determining brain death in adults: report of the Quality Standards Subcommittee of the American Academy of Neurology.

Science.gov (United States)

Wijdicks, Eelco F M; Varelas, Panayiotis N; Gronseth, Gary S; Greer, David M

2010-06-08

To provide an update of the 1995 American Academy of Neurology guideline with regard to the following questions: Are there patients who fulfill the clinical criteria of brain death who recover neurologic function? What is an adequate observation period to ensure that cessation of neurologic function is permanent? Are complex motor movements that falsely suggest retained brain function sometimes observed in brain death? What is the comparative safety of techniques for determining apnea? Are there new ancillary tests that accurately identify patients with brain death? A systematic literature search was conducted and included a review of MEDLINE and EMBASE from January 1996 to May 2009. Studies were limited to adults. In adults, there are no published reports of recovery of neurologic function after a diagnosis of brain death using the criteria reviewed in the 1995 American Academy of Neurology practice parameter. Complex-spontaneous motor movements and false-positive triggering of the ventilator may occur in patients who are brain dead. There is insufficient evidence to determine the minimally acceptable observation period to ensure that neurologic functions have ceased irreversibly. Apneic oxygenation diffusion to determine apnea is safe, but there is insufficient evidence to determine the comparative safety of techniques used for apnea testing. There is insufficient evidence to determine if newer ancillary tests accurately confirm the cessation of function of the entire brain.

Work safety in the light of technological progress in mining. [Poland, accident and technology assessment for period 1950 to 1972

Energy Technology Data Exchange (ETDEWEB)

Stecko, R.

1976-01-01

This paper discusses positive and negative aspects of technological progress in black coal mining in Poland in the period from 1950 to 1972 on the basis of statistical data supplied by various institutions. Twenty three indexes characterizing both work safety and technological progress in underground coal mines are used. Equations of linear and non-linear even regression and equations of linear and non-linear multiple regression are derived on the basis of statistical records of 23 years. The equations are used to estimate indexes of work safety on the basis of technical progress indexes. It is suggested that from among 8 indexes characterizing work safety 4 are most useful and important: danger index, absenteeism index, frequency of underground fire index, and frequency of rock burst index. Analysis of the regression equation shows that technological progress in underground coal mines in Poland has caused a decrease in indexes describing: frequency of work accidents, frequency of underground fires, frequency of rock burst, and danger of underground work; and an increase in indexes characterizing: seriousness of work accidents, and absenteeism caused by work accidents. (84 refs.)

Working Memory Updating Latency Reflects the Cost of Switching between Maintenance and Updating Modes of Operation

Science.gov (United States)

Kessler, Yoav; Oberauer, Klaus

2014-01-01

Updating and maintenance of information are 2 conflicting demands on working memory (WM). We examined the time required to update WM (updating latency) as a function of the sequence of updated and not-updated items within a list. Participants held a list of items in WM and updated a variable subset of them in each trial. Four experiments that vary…

FRMAC Updates

International Nuclear Information System (INIS)

Mueller, P.

1995-01-01

This talks describes updates in the following updates in FRMAC publications concerning radiation emergencies: Monitoring and Analysis Manual; Evaluation and Assessment Manual; Handshake Series (Biannual) including exercises participated in; environmental Data and Instrument Transmission System (EDITS); Plume in a Box with all radiological data stored onto a hand-held computer; and courses given

Constructing a Bayesian network model for improving safety behavior of employees at workplaces.

Science.gov (United States)

Mohammadfam, Iraj; Ghasemi, Fakhradin; Kalatpour, Omid; Moghimbeigi, Abbas

2017-01-01

Unsafe behavior increases the risk of accident at workplaces and needs to be managed properly. The aim of the present study was to provide a model for managing and improving safety behavior of employees using the Bayesian networks approach. The study was conducted in several power plant construction projects in Iran. The data were collected using a questionnaire composed of nine factors, including management commitment, supporting environment, safety management system, employees' participation, safety knowledge, safety attitude, motivation, resource allocation, and work pressure. In order for measuring the score of each factor assigned by a responder, a measurement model was constructed for each of them. The Bayesian network was constructed using experts' opinions and Dempster-Shafer theory. Using belief updating, the best intervention strategies for improving safety behavior also were selected. The result of the present study demonstrated that the majority of employees do not tend to consider safety rules, regulation, procedures and norms in their behavior at the workplace. Safety attitude, safety knowledge, and supporting environment were the best predictor of safety behavior. Moreover, it was determined that instantaneous improvement of supporting environment and employee participation is the best strategy to reach a high proportion of safety behavior at the workplace. The lack of a comprehensive model that can be used for explaining safety behavior was one of the most problematic issues of the study. Furthermore, it can be concluded that belief updating is a unique feature of Bayesian networks that is very useful in comparing various intervention strategies and selecting the best one form them. Copyright © 2016 Elsevier Ltd. All rights reserved.

Update and revision of WHO air quality guidelines for Europe

Energy Technology Data Exchange (ETDEWEB)

Younes, M. [WHO European Centre for Environment and Health, Bilthoven (Netherlands). Bilthoven Div.

1995-12-31

The WHO Air Quality Guidelines for Europe (AQG), published in 1987, have provided a uniform basis for the development of strategies for the control of air pollution, and have contributed to the maintenance and improvement of public health in several countries. The aim of the guidelines is to provide a basis for protecting public health from adverse effects of air pollutants, and for eliminating or reducing to a minimum, those contaminants that are known or likely to be hazardous to human health and wellbeing. Since the publication of the first edition of the AQG, new scientific data in the fields of air pollution toxicology and epidemiology have accumulated and new developments in risk assessment methodologies have taken place, requiring updating and/or revision of the existing guidelines. This fact was recognized during the preparation of the initial work plan of the European Centre for Environment and Health, and it was recommended that the Centre undertake any necessary amendments and extensions to the Air Quality Guidelines. The updating procedure is being carried out in cooperation with the International Programme on Chemical Safety (IPCS) and the Commission of the European Communities (CEC) and will be implemented through working group meetings which require the preparation of working documents on specific air pollutants or mixtures and a final consultation to discuss the updated document.It was initiated by a Planning Meeting which was organized in January 1993. The purpose of the planning meeting was to set the framework for the updating and revision process, in particular to discuss the scope and purpose, the contents and the format of the revised AQG publication, to define the details of and the time schedule for the updating process and to identify the working groups needed and their way of operation. (author)

Update and revision of WHO air quality guidelines for Europe

Energy Technology Data Exchange (ETDEWEB)

Younes, M [WHO European Centre for Environment and Health, Bilthoven (Netherlands). Bilthoven Div.

1996-12-31

The WHO Air Quality Guidelines for Europe (AQG), published in 1987, have provided a uniform basis for the development of strategies for the control of air pollution, and have contributed to the maintenance and improvement of public health in several countries. The aim of the guidelines is to provide a basis for protecting public health from adverse effects of air pollutants, and for eliminating or reducing to a minimum, those contaminants that are known or likely to be hazardous to human health and wellbeing. Since the publication of the first edition of the AQG, new scientific data in the fields of air pollution toxicology and epidemiology have accumulated and new developments in risk assessment methodologies have taken place, requiring updating and/or revision of the existing guidelines. This fact was recognized during the preparation of the initial work plan of the European Centre for Environment and Health, and it was recommended that the Centre undertake any necessary amendments and extensions to the Air Quality Guidelines. The updating procedure is being carried out in cooperation with the International Programme on Chemical Safety (IPCS) and the Commission of the European Communities (CEC) and will be implemented through working group meetings which require the preparation of working documents on specific air pollutants or mixtures and a final consultation to discuss the updated document.It was initiated by a Planning Meeting which was organized in January 1993. The purpose of the planning meeting was to set the framework for the updating and revision process, in particular to discuss the scope and purpose, the contents and the format of the revised AQG publication, to define the details of and the time schedule for the updating process and to identify the working groups needed and their way of operation. (author)

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

International Nuclear Information System (INIS)

1999-01-01

resolved in other plants and which can be used in reassessing the safety of individual operating plants. The IAEA-TECDOC-1044, Generic Safety Issues for Nuclear Power Plants with Light Water Reactors and Measures Taken for Their Resolution (September 1998), is a compilation of such safety issues which is based on broad international experience. This compilation is one element within the framework of IAEA activities to assist Member States in reassessing the safety of operating nuclear power plants. It is a compilation not only of the generic safety issues identified in nuclear power plants but also, in almost all cases, the measures taken to resolve these issues. The safety issues, which are generic in nature with regard to light water reactors (LWRs), and the measures taken for their resolution, are intended for use as a reference in the reassessment of the safety of operating plants.The information contained in the main body of the TECDOC has been used to establish a database. This database has search, query and report functions. This information is thus available in an electronic form which can be selectively queried and with which reports can be produced according to the requirements of the user. The database also enables the IAEA to update the data periodically on the basis of information made available by Member States

Deterministic Safety Analysis for Nuclear Power Plants. Specific Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2012-01-01

The IAEA's Statute authorizes the Agency to establish safety standards to protect health and minimize danger to life and property - standards which the IAEA must use in its own operations, and which a State can apply by means of its regulatory provisions for nuclear and radiation safety. A comprehensive body of safety standards under regular review, together with the IAEA's assistance in their application, has become a key element in a global safety regime. In the mid-1990s, a major overhaul of the IAEA's safety standards programme was initiated, with a revised oversight committee structure and a systematic approach to updating the entire corpus of standards. The new standards that have resulted are of a high calibre and reflect best practices in Member States. With the assistance of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its safety standards. Safety standards are only effective, however, if they are properly applied in practice. The IAEA's safety services - which range in scope from engineering safety, operational safety, and radiation, transport and waste safety to regulatory matters and safety culture in organizations - assist Member States in applying the standards and appraise their effectiveness. These safety services enable valuable insights to be shared and I continue to urge all Member States to make use of them. Regulating nuclear and radiation safety is a national responsibility, and many Member States have decided to adopt the IAEA's safety standards for use in their national regulations. For the contracting parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions. The standards are also applied by designers, manufacturers and operators around the world to enhance nuclear and radiation safety in power generation, medicine, industry, agriculture, research and education

EFSA Panel on Dietetic Products, Nutrition and Allergi es (NDA) ; Scientific Opinion - Statement on the safety of the “conjugated linoleic acid (CLA) - rich oils” Clarinol ® and Tonalin TG 80 as Novel Food ingredients

DEFF Research Database (Denmark)

Tetens, Inge

that the additional information provided does not contain evidence thath would modify its previous conclusions regarding the effects of CLA on insulin sensitivity/glucose metabolism, blood lipids, lipid peroxidation, or subclinical inflammation. The Panel also considers that the new studies provided do not address......Following a request from the European Commission, the Panel on Dietetic Products, Nutrition and Allergies was asked to update its opinions on the safety of the conjugated linoleic acid (CLA)-rich oils Clarinol® and Tonalin® TG 80 as Novel Food ingredients in the light of additional information...... uses and daily doses for up to six months. The safety of CLA consumption for periods longer than six months has not been established under the proposed conditions of use. The safety of CLA consumption by type-2 diabetic subjects has not been established. © European Food Safety Authority, 2012...

Introduction to 'International Handbook of Criticality Safety Benchmark Experiments'

International Nuclear Information System (INIS)

Komuro, Yuichi

1998-01-01

The Criticality Safety Benchmark Evaluation Project (CSBEP) was initiated in 1992 by the United States Department of Energy. The project quickly became an international effort as scientists from other interested countries became involved. The International Criticality Safety Benchmark Evaluation Project (ICSBEP) is now an official activity of the Organization for Economic Cooperation and Development-Nuclear Energy Agency (OECD-NEA). 'International Handbook of Criticality Safety Benchmark Experiments' was prepared and is updated year by year by the working group of the project. This handbook contains criticality safety benchmark specifications that have been derived from experiments that were performed at various nuclear critical facilities around the world. The benchmark specifications are intended for use by criticality safety engineers to validate calculation techniques used. The author briefly introduces the informative handbook and would like to encourage Japanese engineers who are in charge of nuclear criticality safety to use the handbook. (author)

Annual report on reactor safety research projects. Reporting period 2011. Progress report

International Nuclear Information System (INIS)

2011-01-01

Within its competence for energy research the Federal Ministry of Economics and Technology (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS)mbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRSF- Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/Authority Support Division of GRS. The reports as of the year 2000 are available in the Internet-based information system on results and data of reactor safety research (http://www.grs-fbw.de). The compilation of the reports is classified according to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

Annual report on reactor safety research projects. Reporting period 2014. Progress report

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-07-01

Within its competence for energy research the Federal Ministry for Economic Affairs and Energy (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/Authority Support Division of GRS. The reports as of the year 2000 are available in the lnternet-based information system on results and data of reactor safety research (http://www.grs-fbw.de). The compilation of the reports is classified according to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. lt has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties.

Annual report on reactor safety research projects. Reporting period 2013. Progress report

International Nuclear Information System (INIS)

2013-01-01

Within its competence for energy research the Federal Ministry of Economics and Technology (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS)mbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRSF- Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/Authority Support Division of GRS. The reports as of the year 2000 are available in the Internet-based information system on results and data of reactor safety research (http://www.grs-fbw.de). The compilation of the reports is classified according to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. It has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties. (orig.)

Annual report on reactor safety research projects. Reporting period 2015. Progress report

International Nuclear Information System (INIS)

2015-01-01

Within its competence for energy research the Federal Ministry for Economic Affairs and Energy (BMWi) sponsors research projects on the safety of nuclear power plants currently in operation. The objective of these projects is to provide fundamental knowledge, procedures and methods to contribute to realistic safety assessments of nuclear installations, to the further development of safety technology and to make use of the potential of innovative safety-related approaches. The Gesellschaft tor Anlagen- und Reaktorsicherheit (GRS) gGmbH, by order of the BMWi, continuously issues information on the status of such research projects by publishing semi-annual and annual progress reports within the series of GRS-F-Fortschrittsberichte (GRS-F-Progress Reports). Each progress report represents a compilation of individual reports about the objectives, work performed, results achieved, next steps of the work etc. The individual reports are ·' prepared in a standard form by the research organisations themselves as documentation of their progress in work. The progress reports are published by the Project Management Agency/Authority Support Division of GRS. The reports as of the year 2000 are available in the lnternet-based information system on results and data of reactor safety research (http://www.grs-fbw.de). The compilation of the reports is classified according to the classification system ''Joint Safety Research Index (JSRI)''. The reports are arranged in sequence of their project numbers. it has to be pointed out that the authors of the reports are responsible for the contents of this compilation. The BMWi does not take any responsibility for the correctness, exactness and completeness of the information nor for the observance of private claims of third parties.

Protocol updated for the treatment of patients in radiotherapy with implanted cardiac devices

International Nuclear Information System (INIS)

Martin Martin, G.; Bermudez Luna, R.; Rodriguez Rodriguez, C.; Lopez Fernandez, A.; Rodriguez Perez, A.; Sotoca Ruiz, A.

2013-01-01

Radiotherapy treatment can be safely performed in patients with pacemakers or implanted defibrillators, however, it is very important to ensure that the patient receives the minimum dose possible in your heart device. Is considered essential good coordination with the cardiology service before, during and after radiotherapy treatment for the patient safety. Finally we present a protocol updated to treat these patients in radiotherapy. (Author)

Updated follow-up of long-term Chalk River employees

International Nuclear Information System (INIS)

Werner, M.M.; Myers, D.K.; Morrison, D.P.

1983-08-01

Data on the follow-up of CRNL employees who died during employment or after retirement have been updated to 1982 December 31. Updated tables on mortality for AECL participants in the 1953 NRX clean-up and in the 1958 NRU decontamination are also included in this report. Preliminary mortality data on two other groups are presented here for (a) female employees of CRNL, 1966-1982 and (b) male employees of CRNL who have accumulated lifetime occupational doses of 0.2 Sv (20 rem) or more. Data on types of fatal cancer recorded for long-term male CRNL employees over the period 1966-1982 are also given. No statistically significant increases in cancer deaths were found in any of the groups analyzed

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

Effective updating process of seismic fragilities using Bayesian method and information entropy

International Nuclear Information System (INIS)

Kato, Masaaki; Takata, Takashi; Yamaguchi, Akira

2008-01-01

Seismic probabilistic safety assessment (SPSA) is an effective method for evaluating overall performance of seismic safety of a plant. Seismic fragilities are estimated to quantify the seismically induced accident sequences. It is a great concern that the SPSA results involve uncertainties, a part of which comes from the uncertainty in the seismic fragility of equipment and systems. A straightforward approach to reduce the uncertainty is to perform a seismic qualification test and to reflect the results on the seismic fragility estimate. In this paper, we propose a figure-of-merit to find the most cost-effective condition of the seismic qualification tests about the acceleration level and number of components tested. Then a mathematical method to reflect the test results on the fragility update is developed. A Bayesian method is used for the fragility update procedure. Since a lognormal distribution that is used for the fragility model does not have a Bayes conjugate function, a parameterization method is proposed so that the posterior distribution expresses the characteristics of the fragility. The information entropy is used as the figure-of-merit to express importance of obtained evidence. It is found that the information entropy is strongly associated with the uncertainty of the fragility. (author)

UPDATING NATIONAL TOPOGRAPHIC DATA BASE USING CHANGE DETECTION METHODS

Directory of Open Access Journals (Sweden)

E. Keinan

2016-06-01

Full Text Available The traditional method for updating a topographic database on a national scale is a complex process that requires human resources, time and the development of specialized procedures. In many National Mapping and Cadaster Agencies (NMCA, the updating cycle takes a few years. Today, the reality is dynamic and the changes occur every day, therefore, the users expect that the existing database will portray the current reality. Global mapping projects which are based on community volunteers, such as OSM, update their database every day based on crowdsourcing. In order to fulfil user's requirements for rapid updating, a new methodology that maps major interest areas while preserving associated decoding information, should be developed. Until recently, automated processes did not yield satisfactory results, and a typically process included comparing images from different periods. The success rates in identifying the objects were low, and most were accompanied by a high percentage of false alarms. As a result, the automatic process required significant editorial work that made it uneconomical. In the recent years, the development of technologies in mapping, advancement in image processing algorithms and computer vision, together with the development of digital aerial cameras with NIR band and Very High Resolution satellites, allow the implementation of a cost effective automated process. The automatic process is based on high-resolution Digital Surface Model analysis, Multi Spectral (MS classification, MS segmentation, object analysis and shape forming algorithms. This article reviews the results of a novel change detection methodology as a first step for updating NTDB in the Survey of Israel.

Updating National Topographic Data Base Using Change Detection Methods

Science.gov (United States)

Keinan, E.; Felus, Y. A.; Tal, Y.; Zilberstien, O.; Elihai, Y.

2016-06-01

The traditional method for updating a topographic database on a national scale is a complex process that requires human resources, time and the development of specialized procedures. In many National Mapping and Cadaster Agencies (NMCA), the updating cycle takes a few years. Today, the reality is dynamic and the changes occur every day, therefore, the users expect that the existing database will portray the current reality. Global mapping projects which are based on community volunteers, such as OSM, update their database every day based on crowdsourcing. In order to fulfil user's requirements for rapid updating, a new methodology that maps major interest areas while preserving associated decoding information, should be developed. Until recently, automated processes did not yield satisfactory results, and a typically process included comparing images from different periods. The success rates in identifying the objects were low, and most were accompanied by a high percentage of false alarms. As a result, the automatic process required significant editorial work that made it uneconomical. In the recent years, the development of technologies in mapping, advancement in image processing algorithms and computer vision, together with the development of digital aerial cameras with NIR band and Very High Resolution satellites, allow the implementation of a cost effective automated process. The automatic process is based on high-resolution Digital Surface Model analysis, Multi Spectral (MS) classification, MS segmentation, object analysis and shape forming algorithms. This article reviews the results of a novel change detection methodology as a first step for updating NTDB in the Survey of Israel.

LABOUR PROTECTION AND INDUSTRIAL SAFETY IN UKRAINE: PROBLEMS OF TRANSITION PERIOD AND PERSPECTIVE WAYS OF DEVELOPMENT

Directory of Open Access Journals (Sweden)

A. P. BOCHKOVSKY

2016-12-01

1.9 fold greater than the corresponding figure in Ukraine, and the number of subjects with regard to the issues of the labour protection and industrial safety, which are taught to students in fulfilling the work programmes at nonspecialised Polish higher educational establishments is greater than that in Ukrainian several fold. The statistical data regarding the dynamics of the accident number increase in Ukraine and their causes within a period of  “Зернові продукти і комбікорми”, 201643 http://www.grain-mixedfodders.com Зернові продукти і комбікорми Vol.64, I.4/ 2016 2015 and 2016 are presented and analysed in the context of recent negative changes including the reduction of class hours for students learning the disciplines of "Sectoral Labour Protection", "Basics of Labour Protection", "Foundations of Life Activity Safety" and "Civil protection", merging such subjects, and cancellation of the graduation project relevant sections in most HEI of Ukraine On the grounds of the research, priority directions for developing the labour protection and industrial safety in Ukraine on the stage of European integration are proposed.Based on comparative analysis of the industrial accident causes in Ukraine and EU countries this article establishes that the main accident reasons are organizational ones (50 to 70% of the total number of cases, however such indicators as the registered in Ukraine fatal cases frequency coefficient (per 1 thousand of employees and the fatal accidents-total accidents number ratio are greater than the similar indicators in Europe by about 2- and 100-fold, respectively. It is noted that the issues of improving the work safety in Ukraine towards the association with the European Union should be considered in the context of two main planes, which are associated with changes in the legislative and educational systems. Within this article, the authors analyse the main inter-sectoral and sectoral

Ice cream safety in the Dubrovnik area in the period 2006-2008

Directory of Open Access Journals (Sweden)

Jakov Zadre

2010-03-01

Full Text Available From the epidemiological point of view, ice cream is a very risky foodstuff, which is illustrated by the fact that in 2006, 18.6% (520/2796 of samples from the entire Croatian market were microbiologically unsafe and, therefore, not in compliance with food safety standards. With regards to farreaching health-related, as well as economical and promotional consequences of an alimentary infection and intoxication in the peak tourist season, the aim of this paper was to monitor the microbiological safety of ice-cream from 9 ice-cream parlours in the Dubrovnik city area during three calendar years. During 2006, 13.58% (11/70 of samples were found unsafe. The following bacteria were detected in the samples, which is a sign of non-compliance with food safety standards: representatives of family Enterobacteriaceae in 8 samples (9.87%, Staphylococcus aureus in 3 samples (3.7% and aerobic mesophillic bacteria in 3 samples (3.7%. During 2007, 13.86% (14/87 of samples were not in compliance with food safety standards due to the presence of representatives of family Enterobacteriaceae in 13 samples (12.87% and aerobic mesophillic bacteria in 2 samples (1.98%. In 2008, 9.46% (7/67 of samples were not in compliance with food safety standards due to the presence of representatives of family Enterobacteriaceae in 6 samples (8.1%, aerobic mesophillic bacteria in 2 samples (2.7% and Staphylococcus aureus in 1 sample (1.35%. Neither Salmonella spp. nor Listeria monocytogenes were isolated from any sample. The results indicate an improvement of microbiological safety of ice-cream. Moreover, it is necessary to pay more attention to hygiene during the production, storage and handling of ice-cream in order to further reduce the number of negative samples in which the presence of representatives of family Enterobacteriaceae is recorded.

Mortality and causes of death in autism spectrum disorders - An update

DEFF Research Database (Denmark)

Mouridsen, S.E.; Hansen, H.B.; Rich, B.

2008-01-01

This study compared mortality among Danish citizens with autism spectrum disorders (ASDs) with that of the general population. A clinical cohort of 341 Danish individuals with variants of ASD, previously followed over the period 1960-93, now on average 43 years of age, were updated with respect...

Safety assessment for facilities and activities. General safety requirements. Pt. 4

International Nuclear Information System (INIS)

2009-01-01

) Facilities where the mining and processing of radioactive ores (such as ores of uranium and thorium) are carried out. 'Activities' includes: (a) production, use, import and export of radiation sources for industrial, research, medical and other purposes; (b) transport of radioactive material; (c) decommissioning and dismantling of facilities and the closure of repositories for radioactive waste; (d) close-out of facilities where the mining and processing of radioactive ore was carried out; (e) activities for radioactive waste management such as the discharge of effluents; (f) remediation of sites affected by residues from past activities. Safety assessment plays an important role throughout the lifetime of the facility or activity whenever decisions on safety issues are made by the designers, the constructors, the manufacturers, the operating organization or the regulatory body. Stages in the lifetime of a facility or activity where a safety assessment is carried out, updated and used by the designers, the operating organization and the regulatory body include: (a) site evaluation for the facility or activity; (b) development of the design; (c) construction of the facility or implementation of the activity; (d) commissioning of the facility or activity; (e) commencement of operation of the facility or conduct of the activity; (f) normal operation of the facility or normal conduct of the activity; (g) modification of the design or operation; (h) periodic safety reviews;(i) life extension of the facility beyond its original design life; (j) changes in ownership or management of the facility; (k) decommissioning and dismantling of a facility; (l) closure of a repository for the disposal of radioactive waste and the post-closure phase; (m) remediation of a site and release from regulatory control. The publication is structured as follows: An introduction is followed by Section 2 which provides the basis for requiring a safety assessment to be carried out, derived from the

Safety Assessment for Facilities and Activities. General Safety Requirements. Pt. 4

International Nuclear Information System (INIS)

2009-01-01

) Facilities where the mining and processing of radioactive ores (such as ores of uranium and thorium) are carried out. 'Activities' includes: (a) production, use, import and export of radiation sources for industrial, research, medical and other purposes; (b) transport of radioactive material; (c) decommissioning and dismantling of facilities and the closure of repositories for radioactive waste; (d) close-out of facilities where the mining and processing of radioactive ore was carried out; (e) activities for radioactive waste management such as the discharge of effluents; (f) remediation of sites affected by residues from past activities. Safety assessment plays an important role throughout the lifetime of the facility or activity whenever decisions on safety issues are made by the designers, the constructors, the manufacturers, the operating organization or the regulatory body. Stages in the lifetime of a facility or activity where a safety assessment is carried out, updated and used by the designers, the operating organization and the regulatory body include: (a) site evaluation for the facility or activity; (b) development of the design; (c) construction of the facility or implementation of the activity; (d) commissioning of the facility or activity; (e) commencement of operation of the facility or conduct of the activity; (f) normal operation of the facility or normal conduct of the activity; (g) modification of the design or operation; (h) periodic safety reviews; (i) life extension of the facility beyond its original design life; (j) changes in ownership or management of the facility; (k) decommissioning and dismantling of a facility; (l) closure of a repository for the disposal of radioactive waste and the post-closure phase; (m) remediation of a site and release from regulatory control. The publication is structured as follows: An introduction is followed by Section 2 which provides the basis for requiring a safety assessment to be carried out, derived from the

Safety Assessment for Facilities and Activities. General Safety Requirements. Pt. 4

International Nuclear Information System (INIS)

2010-01-01

) Facilities where the mining and processing of radioactive ores (such as ores of uranium and thorium) are carried out. 'Activities' includes: (a) production, use, import and export of radiation sources for industrial, research, medical and other purposes; (b) transport of radioactive material; (c) decommissioning and dismantling of facilities and the closure of repositories for radioactive waste; (d) close-out of facilities where the mining and processing of radioactive ore was carried out; (e) activities for radioactive waste management such as the discharge of effluents; (f) remediation of sites affected by residues from past activities. Safety assessment plays an important role throughout the lifetime of the facility or activity whenever decisions on safety issues are made by the designers, the constructors, the manufacturers, the operating organization or the regulatory body. Stages in the lifetime of a facility or activity where a safety assessment is carried out, updated and used by the designers, the operating organization and the regulatory body include: (a) site evaluation for the facility or activity; (b) development of the design; (c) construction of the facility or implementation of the activity; (d) commissioning of the facility or activity; (e) commencement of operation of the facility or conduct of the activity; (f) normal operation of the facility or normal conduct of the activity; (g) modification of the design or operation; (h) periodic safety reviews; (i) life extension of the facility beyond its original design life; (j) changes in ownership or management of the facility; (k) decommissioning and dismantling of a facility; (l) closure of a repository for the disposal of radioactive waste and the post-closure phase; (m) remediation of a site and release from regulatory control. The publication is structured as follows: An introduction is followed by Section 2 which provides the basis for requiring a safety assessment to be carried out, derived from the

Safety Assessment for Facilities and Activities. General Safety Requirements. Pt. 4

International Nuclear Information System (INIS)

2009-01-01

installed; (i) Facilities where the mining and processing of radioactive ores (such as ores of uranium and thorium) are carried out. 'Activities' includes: (a) production, use, import and export of radiation sources for industrial, research, medical and other purposes; (b) transport of radioactive material; (c) decommissioning and dismantling of facilities and the closure of repositories for radioactive waste; (d) close-out of facilities where the mining and processing of radioactive ore was carried out; (e) activities for radioactive waste management such as the discharge of effluents; (f) remediation of sites affected by residues from past activities. Safety assessment plays an important role throughout the lifetime of the facility or activity whenever decisions on safety issues are made by the designers, the constructors, the manufacturers, the operating organization or the regulatory body. Stages in the lifetime of a facility or activity where a safety assessment is carried out, updated and used by the designers, the operating organization and the regulatory body include: (a) site evaluation for the facility or activity; (b) development of the design; (c) construction of the facility or implementation of the activity; (d) commissioning of the facility or activity; (e) commencement of operation of the facility or conduct of the activity; (f) normal operation of the facility or normal conduct of the activity; (g) modification of the design or operation; (h) periodic safety reviews;(i) life extension of the facility beyond its original design life; (j) changes in ownership or management of the facility; (k) decommissioning and dismantling of a facility; (l) closure of a repository for the disposal of radioactive waste and the post-closure phase; (m) remediation of a site and release from regulatory control. The publication is structured as follows: An introduction is followed by Section 2 which provides the basis for requiring a safety assessment to be carried out, derived

Radioactive waste management services. Safety and technical advisory services available from the IAEA

International Nuclear Information System (INIS)

2000-09-01

This brochure provides updated information about the services and assistance the International Atomic Energy Agency (IAEA) is able to render, upon request by Member States, in the area of radioactive waste management. The ultimate objective is to ensure that all wastes are managed safely and in a way which protects both individual and the environment, now and in the future. The IAEA is the sole global international organization with the statutory authority to establish safety standards for the protection of health against exposure to ionizing radiation. These include safety standards for radioactive waste management. A comprehensive set of such standards is being established, and continuously updated, under the Agency's aegis, which lay out the requirements for the safe management of all types of radioactive waste. The Agency has a further statutory obligation ro provide for the application of these standards at the request of States. The safety of radioactive waste management is not attainable through safety standards alone but requires special technology. An additional function of the IAEA is thus to foster the transfer of technology among States, including the specific technology needed to ensure safe radioactive waste management

Preliminary Integrated Safety Analysis Status Report

International Nuclear Information System (INIS)

Gwyn, D.

2001-01-01

This report provides the status of the potential Monitored Geologic Repository (MGR) Integrated Safety Analysis (EA) by identifying the initial work scope scheduled for completion during the ISA development period, the schedules associated with the tasks identified, safety analysis issues encountered, and a summary of accomplishments during the reporting period. This status covers the period from October 1, 2000 through March 30, 2001

ACP Facility Safety Surveillance System Installation

International Nuclear Information System (INIS)

You, Gil Sung; Kook, D. H.; Choung, W. M.; Ku, J. H.; Cho, I. J.; You, G. S.; Kwon, K. C.; Lee, W. K.; Lee, E. P.

2006-10-01

The Advanced spent fuel Conditioning Process is under development for effective management of spent fuel by converting UO 2 into U-metal. For demonstration of this process, α-γ type new hotcell was built in the IMEF basement. All facilities which treat radioactive materials must manage CCTV system which is under control of Health Physics department. Three main points (including hotcell rear door area) have each camera, but operators who are in charge of facility management need to check the safety of the facility immediately through the network in his office. This needs introduce additional network cameras installation and this new surveillance system is expected to update the whole safety control ability with existing system

Memory updating and mental arithmetic

Directory of Open Access Journals (Sweden)

Cheng-Ching eHan

2016-02-01

Full Text Available Is domain-general memory updating ability predictive of calculation skills or are such skills better predicted by the capacity for updating specifically numerical information? Here, we used multidigit mental multiplication (MMM as a measure for calculating skill as this operation requires the accurate maintenance and updating of information in addition to skills needed for arithmetic more generally. In Experiment 1, we found that only individual differences with regard to a task updating numerical information following addition (MUcalc could predict the performance of MMM, perhaps owing to common elements between the task and MMM. In Experiment 2, new updating tasks were designed to clarify this: a spatial updating task with no numbers, a numerical task with no calculation, and a word task. The results showed that both MUcalc and the spatial task were able to predict the performance of MMM but only with the more difficult problems, while other updating tasks did not predict performance. It is concluded that relevant processes involved in updating the contents of working memory support mental arithmetic in adults.

Expert panel on weight loss surgery: executive report update.

Science.gov (United States)

Blackburn, George L; Hutter, Matthew M; Harvey, Alan M; Apovian, Caroline M; Boulton, Hannah R W; Cummings, Susan; Fallon, John A; Greenberg, Isaac; Jiser, Michael E; Jones, Daniel B; Jones, Stephanie B; Kaplan, Lee M; Kelly, John J; Kruger, Rayford S; Lautz, David B; Lenders, Carine M; Lonigro, Robert; Luce, Helen; McNamara, Anne; Mulligan, Ann T; Paasche-Orlow, Michael K; Perna, Frank M; Pratt, Janey S A; Riley, Stancel M; Robinson, Malcolm K; Romanelli, John R; Saltzman, Edward; Schumann, Roman; Shikora, Scott A; Snow, Roger L; Sogg, Stephanie; Sullivan, Mary A; Tarnoff, Michael; Thompson, Christopher C; Wee, Christina C; Ridley, Nancy; Auerbach, John; Hu, Frank B; Kirle, Leslie; Buckley, Rita B; Annas, Catherine L

2009-05-01

Rapid shifts in the demographics and techniques of weight loss surgery (WLS) have led to new issues, new data, new concerns, and new challenges. In 2004, this journal published comprehensive evidence-based guidelines on WLS. In this issue, we've updated those guidelines to assure patient safety in this fast-changing field. WLS involves a uniquely vulnerable population in need of specialized resources and ongoing multidisciplinary care. Timely best-practice updates are required to identify new risks, develop strategies to address them, and optimize treatment. Findings in these reports are based on a comprehensive review of the most current literature on WLS; they directly link patient safety to methods for setting evidence-based guidelines developed from peer-reviewed scientific publications. Among other outcomes, these reports show that WLS reduces chronic disease risk factors, improves health, and confers a survival benefit on those who undergo it. The literature also shows that laparoscopy has displaced open surgery as the predominant approach; that government agencies and insurers only reimburse procedures performed at accredited WLS centers; that best practice care requires close collaboration between members of a multidisciplinary team; and that new and existing facilities require wide-ranging changes to accommodate growing numbers of severely obese patients. More than 100 specialists from across the state of Massachusetts and across the many disciplines involved in WLS came together to develop these new standards. We expect them to have far-reaching effects of the development of health care policy and the practice of WLS.

47 CFR 80.304 - Watch requirement during silence periods.

Science.gov (United States)

2010-10-01

....304 Section 80.304 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) SAFETY AND SPECIAL RADIO SERVICES STATIONS IN THE MARITIME SERVICES Safety Watch Requirements and Procedures Ship Station Safety Watches § 80.304 Watch requirement during silence periods. Each ship station operating on...

'On line' course for the periodical training in radiological safety of the workers of a radioactive facility

International Nuclear Information System (INIS)

Amador B, Z.H.; Ayra P, F.E.; Torres B, M.B.

2006-01-01

The results of an 'on line' course for the periodical training in radiological safety of the workers of a radioactive installation are presented. The course is developed for own specialists. The following topics are approached: the state of the art of the studies on the biological effects of the ionizing radiations, the new national regulations, the analysis of the behavior of the occupational exposure, of the obtained experiences of the radiological events, of the results of the radiological surveillance of the work positions, of the detected violations and of the behavior of the outstanding systems and the optimization. The study of the acquired experiences in the packing and the transportation of radioactive materials and the administration of the radioactive waste are included. The study of the course by one month is organized and then two convocations of theoretical exams are executed and one for the evaluation practices of the instructions and procedures. To evaluate the effectiveness of the course a survey it is applied and the later behavior of indicators of the radiological safety of the plant is analyzed. The results that are obtained show a positive balance. (Author)

Modelling blood safety

NARCIS (Netherlands)

Janssen, M.P.

2010-01-01

This thesis describes the development and application of methods and models to support decision making on safety measures aimed at preventing the transmission of infections by blood donors. Safety measures refer to screening tests for blood donors, quarantine periods for blood plasma, or methods for

Technical Basis for Electromagnetic Compatibility Regulatory Guidance Update

Energy Technology Data Exchange (ETDEWEB)

Ewing, Paul D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Korsah, Kofi [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Harrison, Thomas J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Wood, Richard Thomas [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Mays, Gary T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2016-03-01

The objective of this report is to serve as the technical basis document for the next, planned revision of this RG that highlights and provides the rationale for the recommended changes. The structure of this document follows and summarizes the several assessment activities undertaken during the course of this project to evaluate new and updated electromagnetic compatibility (EMC) standards, testing methods and limits, and relevant technology developments being incorporated into plant activities that may have EMI/RFI implications, as well as other specific issues, including impacts of electrostatic discharge (ESD) on safety equipment and impacts on increased usage of wireless devices in nuclear power plants.

An updated nuclear criticality slide rule

International Nuclear Information System (INIS)

Hopper, C.M.; Broadhead, B.L.

1998-04-01

This Volume 2 contains the functional version of the updated nuclear criticality slide rule (more accurately, sliding graphs) that is referenced in An Updated Nuclear Criticality Slide Rule: Technical Basis, NUREG/CR-6504, Vol. 1 (ORNL/TM-13322/V1). This functional slide rule provides a readily usable open-quotes in-handclose quotes method for estimating pertinent nuclear criticality accident information from sliding graphs, thereby permitting (1) the rapid estimation of pertinent criticality accident information without laborious or sophisticated calculations in a nuclear criticality emergency situation, (2) the appraisal of potential fission yields and external personnel radiation exposures for facility safety analyses, and (3) a technical basis for emergency preparedness and training programs at nonreactor nuclear facilities. The slide rule permits the estimation of neutron and gamma dose rates and integrated doses based upon estimated fission yields, distance from the fission source, and time-after criticality accidents for five different critical systems. Another sliding graph permits the estimation of critical solution fission yields based upon fissile material concentration, critical vessel geometry, and solution addition rate. Another graph provides neutron and gamma dose-reduction factors for water, steel, and concrete. Graphs from historic documents are provided as references for estimating critical parameters of various fissile material systems. Conversion factors for various English and metric units are provided for quick reference

Periodic vehicle inspection (MOT). [previously: Periodic Vehicle Inspection of cars (MOT).

NARCIS (Netherlands)

2010-01-01

In the 1980s the periodic vehicle inspection (MOT) of various categories of vehicles was introduced in the Netherlands. This fact sheet will discuss the legal framework of this measure and the research carried out into its effects on road safety, also in an international context. For instance, the

Updated reference design of a liquid metal cooled tandem mirror fusion breeder

International Nuclear Information System (INIS)

Berwald, D.H.; Whitley, R.H.; Garner, J.K.

1985-09-01

Detailed studies of key techinical issues for liquid metal cooled fusion breeder (fusion-fission hybrid blankets) have been performed during the period 1983-4. Based upon the results of these studies, the 1982 reference liquid metal cooled tandem mirror fusion breeder blanket design was updated and is described. The updated reference blankets provides increased breeding and lower technological risk in comparison with the original reference blanket. In addition to the blanket design revisions, a plant concept, cost, and fuel cycle economics assessment is provided. The fusion breeder continues to promise an economical source of fissile fuel for the indefinite future

Updated reference design of a liquid metal cooled tandem mirror fusion breeder

Energy Technology Data Exchange (ETDEWEB)

Berwald, D.H.; Whitley, R.H.; Garner, J.K.; Gromada, R.J.; McCarville, T.J.; Moir, R.W.; Lee, J.D.; Bandini, B.R.; Fulton, F.J.; Wong, C.P.C.; Maya, I.; Hoot, C.G.; Schultz, K.R.; Miller, L.G.; Beeston, J.M.; Harris, B.L.; Westman, R.A.; Ghoniem, N.M.; Orient, G.; Wolfer, M.; DeVan, J.H.; Torterelli, P.

1985-09-01

Detailed studies of key techinical issues for liquid metal cooled fusion breeder (fusion-fission hybrid blankets) have been performed during the period 1983-4. Based upon the results of these studies, the 1982 reference liquid metal cooled tandem mirror fusion breeder blanket design was updated and is described. The updated reference blankets provides increased breeding and lower technological risk in comparison with the original reference blanket. In addition to the blanket design revisions, a plant concept, cost, and fuel cycle economics assessment is provided. The fusion breeder continues to promise an economical source of fissile fuel for the indefinite future.

Study on operational safety issues in the Japanese disposal concept

International Nuclear Information System (INIS)

Suzuki, Satoru; Kitagawa, Yoshito; Hyodo, Hideaki; Kubota, Shigeru; Iijima, Masayoshi; Tamura, Akio; Ishiguro, Katsuhiko; Fujihara, Hiroshi

2014-01-01

In Japan, vitrified high-level radioactive waste (HLW) and certain types of low-level radioactive waste that results from the reprocessing of spent fuel and classified as TRU waste will be disposed of in deep geological formations. NUMO aims to ensure the safety of local residents and workers during the operational phase and after repository closure and will therefore establish a safety case for the geological disposal programme at the end of each stage of the stepwise siting process. Although the Japanese programme is still in the stage before initiation of the siting process, updating the generic (non-site-specific) safety case is required for building confidence among stakeholders. This study focuses on operational safety issues for the Japanese HLW disposal concept. (authors)

cDNA microarray screening in food safety

International Nuclear Information System (INIS)

Roy, Sashwati; Sen, Chandan K.

2006-01-01

The cDNA microarray technology and related bioinformatics tools presents a wide range of novel application opportunities. The technology may be productively applied to address food safety. In this mini-review article, we present an update highlighting the late breaking discoveries that demonstrate the vitality of cDNA microarray technology as a tool to analyze food safety with reference to microbial pathogens and genetically modified foods. In order to bring the microarray technology to mainstream food safety, it is important to develop robust user-friendly tools that may be applied in a field setting. In addition, there needs to be a standardized process for regulatory agencies to interpret and act upon microarray-based data. The cDNA microarray approach is an emergent technology in diagnostics. Its values lie in being able to provide complimentary molecular insight when employed in addition to traditional tests for food safety, as part of a more comprehensive battery of tests

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

Science.gov (United States)

Corkern, Walter H.; Munchausen, Linda L.

1983-01-01

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

Living probabilistic safety assessment (LPSA)

International Nuclear Information System (INIS)

1999-08-01

Over the past few years many nuclear power plant organizations have performed probabilistic safety assessments (PSAs) to identify and understand key plant vulnerabilities. As a result of the availability of these PSA studies, there is a desire to use them to enhance plant safety and to operate the nuclear stations in the most efficient manner. PSA is an effective tool for this purpose as it assists plant management to target resources where the largest benefit to plant safety can be obtained. However, any PSA which is to be used in this way must have a credible and defensible basis. Thus, it is very important to have a high quality 'living PSA' accepted by the plant and the regulator. With this background in mind, the IAEA has prepared this report on Living Probabilistic Safety Assessment (LPSA) which addresses the updating, documentation, quality assurance, and management and organizational requirements for LPSA. Deficiencies in the areas addressed in this report would seriously reduce the adequacy of the LPSA as a tool to support decision making at NPPs. This report was reviewed by a working group during a Technical Committee Meeting on PSA Applications to Improve NPP Safety held in Madrid, Spain, from 23 to 27 February 1998

Update on the usage and safety of epinephrine auto-injectors, 2017

Directory of Open Access Journals (Sweden)

Posner LS

2017-03-01

Full Text Available Larry S Posner,1 Carlos A Camargo Jr2 1North Bay Allergy and Asthma Associates, Inc., Napa, CA, 2Department of Emergency Medicine, Massachusetts General Hospital, Harvard Medical School, Boston, MA, USA Abstract: Anaphylaxis is a serious, potentially fatal allergic reaction. Guidelines recommend prompt intramuscular injections of epinephrine as the first-line therapy for anaphylaxis. Delayed epinephrine treatment may cause undesirable clinical outcomes, including death. In the community, epinephrine auto-injectors (EAIs are commonly used to treat anaphylaxis. This literature review examines several recent concerns regarding the safety of EAIs that may prevent the timely administration of epinephrine. Reports of cardiovascular complications are linked with epinephrine administration, although recent studies suggest that these events are much more commonly associated with intravenous epinephrine rather than with EAIs. Recent studies have also highlighted accidental injections of EAIs in patients’ or caregivers’ fingers and lacerations associated with the use of EAI in children. However, the data suggest that both accidental injections and lacerations are rare and require limited medical intervention. In addition, patients may receive conflicting information on the safety and efficacy of using expired EAIs. Overall, it is believed that the benefits of using EAIs far outweigh the potential risks of not administering an EAI. Although legitimate safety concerns are associated with EAIs, adverse events are rare. Continued training of medical providers, caregivers, and patients may be beneficial to address these concerns and reduce EAI-associated injuries while ensuring that patients receive necessary medical care. Keywords: allergy, anaphylaxis, asthma, pediatrics

System Design and the Safety Basis

International Nuclear Information System (INIS)

Ellingson, Darrel

2008-01-01

The objective of this paper is to present the Bechtel Jacobs Company, LLC (BJC) Lessons Learned for system design as it relates to safety basis documentation. BJC has had to reconcile incomplete or outdated system description information with current facility safety basis for a number of situations in recent months. This paper has relevance in multiple topical areas including documented safety analysis, decontamination and decommissioning (D and D), safety basis (SB) implementation, safety and design integration, potential inadequacy of the safety analysis (PISA), technical safety requirements (TSR), and unreviewed safety questions. BJC learned that nuclear safety compliance relies on adequate and well documented system design information. A number of PIS As and TSR violations occurred due to inadequate or erroneous system design information. As a corrective action, BJC assessed the occurrences caused by systems design-safety basis interface problems. Safety systems reviewed included the Molten Salt Reactor Experiment (MSRE) Fluorination System, K-1065 fire alarm system, and the K-25 Radiation Criticality Accident Alarm System. The conclusion was that an inadequate knowledge of system design could result in continuous non-compliance issues relating to nuclear safety. This was especially true with older facilities that lacked current as-built drawings coupled with the loss of 'historical knowledge' as personnel retired or moved on in their careers. Walkdown of systems and the updating of drawings are imperative for nuclear safety compliance. System design integration with safety basis has relevance in the Department of Energy (DOE) complex. This paper presents the BJC Lessons Learned in this area. It will be of benefit to DOE contractors that manage and operate an aging population of nuclear facilities

The art of appropriate evaluation : a guide for highway safety program managers

Science.gov (United States)

2008-08-01

The guide, updated from its original release in 1999, is intended for project managers who will oversee the evaluation of traffic safety programs. It describes the benefits of evaluation and provides an overview of the steps involved. The guide inclu...

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

Adaptive Beaconing in Mobility Aware Clustering Based MAC Protocol for Safety Message Dissemination in VANET

Directory of Open Access Journals (Sweden)

Nishu Gupta

2017-01-01

Full Text Available Majority of research contributions in wireless access in vehicular environment (WAVE/IEEE 802.11p standard focus on life critical safety-related applications. These applications require regular status update of vehicle’s position referred to as beaconing. Periodic beaconing in vehicle to vehicle communication leads to severe network congestion in the communication channel. The condition worsens under high vehicular density where it impacts reliability and upper bound latency of safety messages. In this paper, WAVE compliant enhancement to the existing IEEE 802.11p protocol is presented which targets prioritized delivery of safety messages while simultaneously provisioning the dissemination of nonsafety messages. Proposed scheme relies on dynamic generation of beacons to mitigate channel congestion and inefficient bandwidth utilization by reducing transmission frequency of beacons. Through the use of clustering mechanism, different beaconing frequencies and different data transmission rates are assigned to prioritize vehicular mobility. Through extensive simulation results, the performance of the proposed approach is evaluated in terms of a wide range of quality of service (QoS parameters for two different transmission ranges. Results show that the proposed protocol provides significant enhancement and stability of the clustered topology in vehicular ad hoc network over existing standard and other protocols with similar applications.

The Updated Multiple Star Catalog

Science.gov (United States)

Tokovinin, Andrei

2018-03-01

The catalog of hierarchical stellar systems with three or more components is an update of the original 1997 version. For 2000 hierarchies, the new Multiple Star Catalog (MSC) provides distances, component masses and periods, and supplementary information (astrometry, photometry, identifiers, orbits, notes). The MSC content and format are explained, and its incompleteness and strong observational selection are stressed. Nevertheless, the MSC can be used for statistical studies and is a valuable source for planning observations of multiple stars. Rare classes of stellar hierarchies found in the MSC (with six or seven components, extremely eccentric orbits, planar and possibly resonant orbits, hosting planets) are briefly presented. High-order hierarchies have smaller velocity dispersion compared to triples and are often associated with moving groups. The paper concludes with an analysis of the ratio of periods and separations between inner and outer subsystems. In wide hierarchies, the ratio of semimajor axes, estimated statistically, is distributed between 3 and 300, with no evidence of dynamically unstable systems.

Updating the Nomographical Diagrams for Dimensioning the Beams

Directory of Open Access Journals (Sweden)

Pop Maria T.

2015-12-01

Full Text Available In order to reduce the time period needed for structures design it is strongly recommended to use nomographical diagrams. The base for formation and updating the nomographical diagrams, stands on the charts presented by different technical publications. The updated charts use the same algorithm and calculation elements as the former diagrams in accordance to the latest prescriptions and European standards. The result consists in a chart, having the same properties, similar with the nomogragraphical diagrams already in us. As a general conclusion, even in our days, the nomographical diagrams are very easy to use. Taking into consideration the value of the moment it’s easy to find out the necessary reinforcement area and vice-verse, having the reinforcement area you can find out the capable moment. It still remains a useful opportunity for pre-sizing and designs the reinforced concrete sections.

Opinions of the well-informed persons about the nuclear reactor facility periodical inspection

International Nuclear Information System (INIS)

Aeba, Yoichi; Ishikawa, Michio; Enomoto, Toshiaki; Oomori, Katsuyoshi

2005-01-01

Falsifications of self-inspection records in the shrouds and of leakage rates for containment vessels at TEPCO nuclear power plants destroyed public trust in nuclear safety. The Nuclear Reactor Regulation Law and Electric Utility Law were amended to enhance the nuclear safety regulation system. The major improvements are that operators are legally required to conduct inspection (periodical operator inspection) and recording and keeping inspection results. The operator performs 'periodical operator inspection' regularly, and Nuclear and Industrial Safety Agency (NISA) performs periodical inspection' about particularly important facilities/function in safety. Sixteen opinions of well-informed persons about the nuclear reactor facility periodical inspection were presented in this special number. Interval of periodical inspection less than thirteen months was disputed. Maintenance activities should be more rationalized based on risk information. (T. Tanaka)

Outage time reduction in GKN II without loss of safety

International Nuclear Information System (INIS)

Sturm, J.

1999-01-01

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

Development of an Owner Engineer's independent capability in NPP safety and licensing

International Nuclear Information System (INIS)

Auglaire, M.; Bayart, D.; D'Eer, A.; Polet, F.; Vanhoenacker, L.; Zhang, J.

2002-01-01

As Owner's Engineer to Electrabel, the Belgian utility which owns and operates the 7 NPPs in Belgium, Tractebel Energy Engineering has gained considerable experience in the field of ten-yearly safety overhauls of NPPs since 1983. It has developed a methodology leading to proposing corrective actions by means of a global and integrated approach in which safety improvement costs are optimized. Safety issues addressed during those projects encompass the writing of Probabilistic Safety Assessment studies, post-TMI recommendations implementation, the installation of autocatalytic recombiners, accident studies, protection against pressurized thermal shock, impact of flooding of internal or external origin, implementation of severe accident management guidelines, re-evaluation of the environment, verification of extreme climate conditions, updating of the Safety Analysis Reports, operation review. (author)

EDF - The Inspector General's report on Nuclear Safety and Radiation Protection 2012

International Nuclear Information System (INIS)

2013-01-01

After a first chapter in which the Inspector General states his own vision of facts and results regarding nuclear safety and radiation protection for 2012, the next chapters address the following topics: the contrasted results of nuclear operating safety, the need to remain vigilant in nuclear safety management, the challenge of occupational safety, the need of new ambitious goals for radiation protection, an updated training which must be better led by line management, maintenance as a strategic issue, the long road ahead for nuclear technical information system (SDIN), the need of better attention to chemistry in operations, the new impetus of EPRs, plant life extension conditioned by nuclear safety, the mobilization of nuclear operators after Fukushima, and noteworthy operating events

77 FR 22637 - Federal Motor Vehicle Safety Standards; Accelerator Control Systems

Science.gov (United States)

2012-04-16

... revise the Federal Motor Vehicle Safety Standard for accelerator control systems (ACS) in two ways. First... Standard (FMVSS) No. 124, Accelerator Control Systems,\\2\\ in two ways. First, we are proposing to update... February 2011 final report ``Technical Assessment of Toyota Electronic Throttle Control Systems,'' the...

Safety update regarding intranasal corticosteroids for the treatment of allergic rhinitis.

Science.gov (United States)

Blaiss, Michael S

2011-01-01

Intranasal corticosteroids (INSs) are the most efficacious medication for the treatment of allergic rhinitis. In 2006, the Joint Task Force of the American College of Allergy, Asthma, and Immunology, and the American Academy of Allergy, Asthma, and Immunology, published a white paper on the potential over-the-counter switch of INS (Bielory L, Blaiss M, Fineman SM, et al. Concerns about intranasal corticosteroids for over-the-counter use: Position statement of the Joint Task Force for the American Academy of Allergy, Asthma and Immunology and the American College of Allergy, Asthma and Immunology. Ann Allergy Asthma Immunol 96:514-525, 2006). The concern of the paper was the safety of the use of these agents without oversight by a health care professional. The objective of this paper was to review published literature on the safety of INS since the publication of the task force white paper. Recent studies, which evaluated topical and systemic adverse events associated with ciclesonide (CIC), fluticasone furoate (FF), mometasone furoate (MF), triamcinolone acetonide, fluticasone propionate, budesonide, and beclomethasone dipropionate were summarized. In general, no significant topical or systemic complications were observed in these studies, although none were >1 year in duration. The newer formulations of topical corticosteroids for allergic rhinitis, such as CIC, FF, and MF, which have less systemic bioavailability, may be safer for long-term use. New studies continue to add to the reassurance of the safety of INSs in the treatment of allergic rhinitis but still do not answer the question if these agents are appropriate for long-term use without oversight by a health care professional.

20 CFR 410.501 - Payment periods.

Science.gov (United States)

2010-04-01

... 20 Employees' Benefits 2 2010-04-01 2010-04-01 false Payment periods. 410.501 Section 410.501 Employees' Benefits SOCIAL SECURITY ADMINISTRATION FEDERAL COAL MINE HEALTH AND SAFETY ACT OF 1969, TITLE IV-BLACK LUNG BENEFITS (1969- ) Payment of Benefits § 410.501 Payment periods. Benefits are paid to...

Extended biosphere dataset for safety assessment of radioactive waste geological disposal

International Nuclear Information System (INIS)

Kato, Tomoko; Suzuki, Yuji

2007-01-01

JAEA has an on-going programme of research and development relating to the safety assessment of the deep geological disposal systems of high-level radioactive waste (HLW) and transuranic waste (TRU). In the safety assessment of HLW and TRU disposal systems, biosphere assessment is necessary to estimate future radiological impacts on human beings (e.g. radiation dose). In order to estimate radiation dose, consideration needs to be given to the biosphere into which future releases of radionuclides might occur and to the associated future human behaviour. The data of some biosphere parameters needed to be updated by appropriate data sources for generic and site-specific biosphere assessment to improve reliability for the biosphere assessment, because some data published in the 1980's or the early 90's were found to be inappropriate for the recent biosphere assessment. Therefore, data of the significant parameters (especially for element-dependent) were set up on the basis of recent information, to update the generic biosphere dataset. (author)

Safety design guides for environmental qualification for CANDU 9

International Nuclear Information System (INIS)

Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young; A. C. D. Wright

1996-03-01

This safety design guide describes the safety philosophy and requirements for the environmental qualification of safety related systems and components for CANDU 9. The environmental qualification program identifies the equipments to be qualified and conditions to be used for qualification and provides comprehensive set of documentation to ensure that the qualification is complete and can be maintained for the life of the plant. A summary of the system, components and structures requiring environmental qualification is provided in the table for the guidance of the system design, and this table will be subject to change or confirmation by the environmental qualification program. Also, plant ares subject to harsh environment is provided in the figure. The change status of the regulatory requirements, code and standards should be traced and this safety design guide shall be updated accordingly. 1 tab., 5 figs. (Author) .new

Modeling Periodic Impulsive Effects on Online TV Series Diffusion.

Science.gov (United States)

Fu, Peihua; Zhu, Anding; Fang, Qiwen; Wang, Xi

Online broadcasting substantially affects the production, distribution, and profit of TV series. In addition, online word-of-mouth significantly affects the diffusion of TV series. Because on-demand streaming rates are the most important factor that influences the earnings of online video suppliers, streaming statistics and forecasting trends are valuable. In this paper, we investigate the effects of periodic impulsive stimulation and pre-launch promotion on on-demand streaming dynamics. We consider imbalanced audience feverish distribution using an impulsive susceptible-infected-removed(SIR)-like model. In addition, we perform a correlation analysis of online buzz volume based on Baidu Index data. We propose a PI-SIR model to evolve audience dynamics and translate them into on-demand streaming fluctuations, which can be observed and comprehended by online video suppliers. Six South Korean TV series datasets are used to test the model. We develop a coarse-to-fine two-step fitting scheme to estimate the model parameters, first by fitting inter-period accumulation and then by fitting inner-period feverish distribution. We find that audience members display similar viewing habits. That is, they seek new episodes every update day but fade away. This outcome means that impulsive intensity plays a crucial role in on-demand streaming diffusion. In addition, the initial audience size and online buzz are significant factors. On-demand streaming fluctuation is highly correlated with online buzz fluctuation. To stimulate audience attention and interpersonal diffusion, it is worthwhile to invest in promotion near update days. Strong pre-launch promotion is also a good marketing tool to improve overall performance. It is not advisable for online video providers to promote several popular TV series on the same update day. Inter-period accumulation is a feasible forecasting tool to predict the future trend of the on-demand streaming amount. The buzz in public social communities

Modeling Periodic Impulsive Effects on Online TV Series Diffusion.

Directory of Open Access Journals (Sweden)

Peihua Fu

Full Text Available Online broadcasting substantially affects the production, distribution, and profit of TV series. In addition, online word-of-mouth significantly affects the diffusion of TV series. Because on-demand streaming rates are the most important factor that influences the earnings of online video suppliers, streaming statistics and forecasting trends are valuable. In this paper, we investigate the effects of periodic impulsive stimulation and pre-launch promotion on on-demand streaming dynamics. We consider imbalanced audience feverish distribution using an impulsive susceptible-infected-removed(SIR-like model. In addition, we perform a correlation analysis of online buzz volume based on Baidu Index data.We propose a PI-SIR model to evolve audience dynamics and translate them into on-demand streaming fluctuations, which can be observed and comprehended by online video suppliers. Six South Korean TV series datasets are used to test the model. We develop a coarse-to-fine two-step fitting scheme to estimate the model parameters, first by fitting inter-period accumulation and then by fitting inner-period feverish distribution.We find that audience members display similar viewing habits. That is, they seek new episodes every update day but fade away. This outcome means that impulsive intensity plays a crucial role in on-demand streaming diffusion. In addition, the initial audience size and online buzz are significant factors. On-demand streaming fluctuation is highly correlated with online buzz fluctuation.To stimulate audience attention and interpersonal diffusion, it is worthwhile to invest in promotion near update days. Strong pre-launch promotion is also a good marketing tool to improve overall performance. It is not advisable for online video providers to promote several popular TV series on the same update day. Inter-period accumulation is a feasible forecasting tool to predict the future trend of the on-demand streaming amount. The buzz in public

Modeling Periodic Impulsive Effects on Online TV Series Diffusion

Science.gov (United States)

Fang, Qiwen; Wang, Xi

2016-01-01

Background Online broadcasting substantially affects the production, distribution, and profit of TV series. In addition, online word-of-mouth significantly affects the diffusion of TV series. Because on-demand streaming rates are the most important factor that influences the earnings of online video suppliers, streaming statistics and forecasting trends are valuable. In this paper, we investigate the effects of periodic impulsive stimulation and pre-launch promotion on on-demand streaming dynamics. We consider imbalanced audience feverish distribution using an impulsive susceptible-infected-removed(SIR)-like model. In addition, we perform a correlation analysis of online buzz volume based on Baidu Index data. Methods We propose a PI-SIR model to evolve audience dynamics and translate them into on-demand streaming fluctuations, which can be observed and comprehended by online video suppliers. Six South Korean TV series datasets are used to test the model. We develop a coarse-to-fine two-step fitting scheme to estimate the model parameters, first by fitting inter-period accumulation and then by fitting inner-period feverish distribution. Results We find that audience members display similar viewing habits. That is, they seek new episodes every update day but fade away. This outcome means that impulsive intensity plays a crucial role in on-demand streaming diffusion. In addition, the initial audience size and online buzz are significant factors. On-demand streaming fluctuation is highly correlated with online buzz fluctuation. Conclusion To stimulate audience attention and interpersonal diffusion, it is worthwhile to invest in promotion near update days. Strong pre-launch promotion is also a good marketing tool to improve overall performance. It is not advisable for online video providers to promote several popular TV series on the same update day. Inter-period accumulation is a feasible forecasting tool to predict the future trend of the on-demand streaming amount

An Update on the Hazards and Risks of Forensic Anthropology, Part II: Field and Laboratory Considerations.

Science.gov (United States)

Roberts, Lindsey G; Dabbs, Gretchen R; Spencer, Jessica R

2016-01-01

This paper focuses on potential hazards and risks to forensic anthropologists while working in the field and laboratory in North America. Much has changed since Galloway and Snodgrass published their seminal article addressing these issues. The increased number of forensic practitioners combined with new information about potential hazards calls for an updated review of these pathogens and chemicals. Discussion of pathogen hazards (Brucella, Borrelia burgdorferi, Yersinia pestis, Clostridium tetani and West Nile virus) includes important history, exposure routes, environmental survivability, early symptoms, treatments with corresponding morbidity and mortality rates, and decontamination measures. Additionally, data pertaining to the use of formaldehyde in the laboratory environment have resulted in updated safety regulations, and these are highlighted. These data should inform field and laboratory protocols. The hazards of working directly with human remains are discussed in a companion article, "An Update on the Hazards and Risks of Forensic Anthropology, Part I: Human Remains." © 2015 American Academy of Forensic Sciences.

77 FR 24257 - Railroad Safety Advisory Committee (RSAC); Working Group Activity Update

Science.gov (United States)

2012-04-23

... publication. Contact: Steve Clay, (202) 493-6259. Task 06-03--Medical Standards for Safety-Critical Personnel... 97-2--(Completed) Evaluating the extent to which environmental, sanitary, and other working...

Associations between safety climate and safety management practices in the construction industry.

Science.gov (United States)

Marín, Luz S; Lipscomb, Hester; Cifuentes, Manuel; Punnett, Laura

2017-06-01

Safety climate, a group-level measure of workers' perceptions regarding management's safety priorities, has been suggested as a key predictor of safety outcomes. However, its relationship with actual injury rates is inconsistent. We posit that safety climate may instead be a parallel outcome of workplace safety practices, rather than a determinant of workers' safety behaviors or outcomes. Using a sample of 25 commercial construction companies in Colombia, selected by injury rate stratum (high, medium, low), we examined the relationship between workers' safety climate perceptions and safety management practices (SMPs) reported by safety officers. Workers' perceptions of safety climate were independent of their own company's implementation of SMPs, as measured here, and its injury rates. However, injury rates were negatively related to the implementation of SMPs. Safety management practices may be more important than workers' perceptions of safety climate as direct predictors of injury rates. © 2017 Wiley Periodicals, Inc.

Online updating procedures for a real-time hydrological forecasting system

International Nuclear Information System (INIS)

Kahl, B; Nachtnebel, H P

2008-01-01

Rainfall-runoff-models can explain major parts of the natural runoff pattern but never simulate the observed hydrograph exactly. Reasons for errors are various sources of uncertainties embedded in the model forecasting system. Errors are due to measurement errors, the selected time period for calibration and validation, the parametric uncertainty and the model imprecision. In on-line forecasting systems forecasted input data is used which additionally generates a major uncertainty for the hydrological forecasting system. Techniques for partially compensating these uncertainties are investigated in the recent study in a medium sized catchment in the Austrian part of the Danube basin. The catchment area is about 1000 km2. The forecasting system consists of a semi-distributed continuous rainfall-runoff model that uses quantitative precipitation and temperature forecasts. To provide adequate system states at the beginning of the forecasting period continuous simulation is required, especially in winter. In this study two online updating methods are used and combined for enhancing the runoff forecasts. The first method is used for updating the system states at the beginning of the forecasting period by changing the precipitation input. The second method is an autoregressive error model, which is used to eliminate systematic errors in the model output. In combination those two methods work together well as each method is more effective in different runoff situations.

Periodic Safety Review of Tendon Pre-stress of Concrete Containment Building for a CA U-Type clear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Joo, Kwang Ho; Lim, Woo Sang [Korea Hydro and clear Power Co., Daejeon (Korea, Republic of)

2009-10-15

Generally, as the tendon pre-stress of concrete containment buildings at nuclear power plants decreases as time passes due to the concrete creep, concrete shrinkage and the relaxation of tendon strands, the tendon pre-stress must secure the structural integrity of these buildings by maintaining its value higher than that of the designed pre-stress during the overall service life of the nuclear power plants. Moreover, if necessary, the degree of tendon pre-stress must also guarantee the structural integrity of concrete containment buildings over their lifetimes. This paper evaluated the changes in the tendon pre-stress of a concrete containment building subject to time-limited aging as an item in a periodic safety review (PSR) of Wolsong unit 1, a CANDU-type nuclear power plant to ensure that the structural integrity can be maintained until the next PSR period after the designed lifetime.

Report on nuclear safety in EU applicant countries

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-03-01

Nuclear safety in the candidate countries to the European Union is a major issue which needs to be addressed in the frame of the enlargement process. The Heads of the nuclear safety Regulatory Bodies of the European Union member states having nuclear power plants, i.e. Belgium, Finland, France, Germany, Italy, the Netherlands, Spain, Sweden and the United Kingdom thought it was their duty to offer their assistance to the European Union institutions at a moment when the expansion of the Union is being considered. As a consequence, they decided to issue a report giving their collective opinion on nuclear safety in those applicant countries having at least one nuclear power reactor (Bulgaria, Czech Republic, Hungary, Lithuania, Romania, Slovak Republic, Slovenia) and covering: the status of the regulatory regime and regulatory body and the nuclear power plant safety status. This report is based on the knowledge they gained through multilateral assistance programmes, in particular the Phare programmes, and also through bilateral contacts. It must be stressed that in some cases, they recognised that their current knowledge was not sufficient to express a clear and exhaustive opinion. Also, it should be pointed out that the judgements are based on widely applied Western European design standards for the defence-in-depth and associated barriers. Quantitative comparisons of Probabilistic Safety Assessments have not been used as the available results are of widely different depth and quality. They also recognised that such a report could only present the situation at a given moment and they intend to periodically update it so as to reflect the changes which may occur in these countries. At this stage, the report does not cover radioactive waste or radiation protection issues in any detail. After they had taken the decision to issue this report, they decided to create an association, the Western European Nuclear Regulators Association (WENRA) in order to increase the co

Report on nuclear safety in EU applicant countries

International Nuclear Information System (INIS)

1999-03-01

Nuclear safety in the candidate countries to the European Union is a major issue which needs to be addressed in the frame of the enlargement process. The Heads of the nuclear safety Regulatory Bodies of the European Union member states having nuclear power plants, i.e. Belgium, Finland, France, Germany, Italy, the Netherlands, Spain, Sweden and the United Kingdom thought it was their duty to offer their assistance to the European Union institutions at a moment when the expansion of the Union is being considered. As a consequence, they decided to issue a report giving their collective opinion on nuclear safety in those applicant countries having at least one nuclear power reactor (Bulgaria, Czech Republic, Hungary, Lithuania, Romania, Slovak Republic, Slovenia) and covering: the status of the regulatory regime and regulatory body and the nuclear power plant safety status. This report is based on the knowledge they gained through multilateral assistance programmes, in particular the Phare programmes, and also through bilateral contacts. It must be stressed that in some cases, they recognised that their current knowledge was not sufficient to express a clear and exhaustive opinion. Also, it should be pointed out that the judgements are based on widely applied Western European design standards for the defence-in-depth and associated barriers. Quantitative comparisons of Probabilistic Safety Assessments have not been used as the available results are of widely different depth and quality. They also recognised that such a report could only present the situation at a given moment and they intend to periodically update it so as to reflect the changes which may occur in these countries. At this stage, the report does not cover radioactive waste or radiation protection issues in any detail. After they had taken the decision to issue this report, they decided to create an association, the Western European Nuclear Regulators Association (WENRA) in order to increase the co

Updating Procedures Can Reorganize the Neural Circuit Supporting a Fear Memory.

Science.gov (United States)

Kwapis, Janine L; Jarome, Timothy J; Ferrara, Nicole C; Helmstetter, Fred J

2017-07-01

Established memories undergo a period of vulnerability following retrieval, a process termed 'reconsolidation.' Recent work has shown that the hypothetical process of reconsolidation is only triggered when new information is presented during retrieval, suggesting that this process may allow existing memories to be modified. Reconsolidation has received increasing attention as a possible therapeutic target for treating disorders that stem from traumatic memories, yet little is known about how this process changes the original memory. In particular, it is unknown whether reconsolidation can reorganize the neural circuit supporting an existing memory after that memory is modified with new information. Here, we show that trace fear memory undergoes a protein synthesis-dependent reconsolidation process following exposure to a single updating trial of delay conditioning. Further, this reconsolidation-dependent updating process appears to reorganize the neural circuit supporting the trace-trained memory, so that it better reflects the circuit supporting delay fear. Specifically, after a trace-to-delay update session, the amygdala is now required for extinction of the updated memory but the retrosplenial cortex is no longer required for retrieval. These results suggest that updating procedures could be used to force a complex, poorly defined memory circuit to rely on a better-defined neural circuit that may be more amenable to behavioral or pharmacological manipulation. This is the first evidence that exposure to new information can fundamentally reorganize the neural circuit supporting an existing memory.

Development of an FPGA-based controller for safety critical application

International Nuclear Information System (INIS)

Xing, A.; De Grosbois, J.; Sklyar, V.; Archer, P.; Awwal, A.

2011-01-01

In implementing safety functions, Field Programmable Gate Arrays (FPGA) technology offers a distinct combination of benefits and advantages over microprocessor-based systems. FPGAs can be designed such that the final product is purely hardware, without any overhead runtime software, bringing the design closer to a conventional hardware-based solution. On the other hand, FPGAs can implement more complex safety logic that would generally require microprocessor-based safety systems. There are now qualified FPGA-based platforms available on the market with a credible use history in safety applications in nuclear power plants. Atomic Energy of Canada (AECL), in collaboration with RPC Radiy, has initiated a development program to define a vigorous FPGA engineering process suitable for implementing safety critical functions at the application development level. This paper provides an update on the FPGA development program along with the proposed design model using function block diagrams for the development of safety controllers in CANDU applications. (author)

Public Comment Period Open for the Draft Update to the Planning for Natural Disaster Debris Guidance and to Related Documents

Science.gov (United States)

EPA is requesting comment on the draft Planning for Natural Disaster Debris Guidance, and two other documents. The Guidance is an update of the Planning for Natural Disaster Debris guidance that EPA published in March 2008.

On the Upper Limit (Heaviest Element in the Periodic Table of Elements, and the Periodic Table of Anti-Substance

Directory of Open Access Journals (Sweden)

Khazan A.

2009-04-01

Full Text Available On the basis of the method involving equilateral hyperbolas developed by us with ref- erence to the Periodic Table, its Top Limit has been established. It is the last element with atomic mass 411.66 and serial number 155. The great value, according to our calculation, has adjacent hyperbolas whose center is the point (0; 1. With the method, it has been possible to find just one element in the Periodic Table — Rhodium, which does not demand additional calculations involving the definition of the valid axes. Cal- culations towards updating the charge of a nucleus and the quantity of neutrons in end N-Z part of the diagram by means of the serial number 155 are herein executed. The variant of the Periodic Table of Elements with the eighth period is recommended. On the basis of symmetry, with the application of the Hyperbolic Law in the Periodic Table of Elements, the existence of Anti-Substances is herein indirectly proved.

Updating OSHA Standards Based on National Consensus Standards; Eye and Face Protection. Final rule.

Science.gov (United States)

2016-03-25

On March 13, 2015, OSHA published in the Federal Register a notice of proposed rulemaking (NPRM) to revise its eye and face protection standards for general industry, shipyard employment, marine terminals, longshoring, and construction by updating the references to national consensus standards approved by the American National Standards Institute (ANSI). OSHA received no significant objections from commenters and therefore is adopting the amendments as proposed. This final rule updates the references in OSHA's eye and face standards to reflect the most recent edition of the ANSI/International Safety Equipment Association (ISEA) eye and face protection standard. It removes the oldest-referenced edition of the same ANSI standard. It also amends other provisions of the construction eye and face protection standard to bring them into alignment with OSHA's general industry and maritime standards.

Mortality and Causes of Death in Autism Spectrum Disorders: An Update

Science.gov (United States)

Mouridsen, Svend Erik; Bronnum-Hansen, Henrik; Rich, Bente; Isager, Torben

2008-01-01

This study compared mortality among Danish citizens with autism spectrum disorders (ASDs) with that of the general population. A clinical cohort of 341 Danish individuals with variants of ASD, previously followed over the period 1960-93, now on average 43 years of age, were updated with respect to mortality and causes of death. Standardized…

Prioritization of R and D programs on probabilistic reactor safety

International Nuclear Information System (INIS)

Husseiny, A.A.

1982-01-01

An interactive computer code based on the multiattribute utility theory has been developed with graphic capabilities to use in selection of probabilistic reactor safety RandD programs. Utility values and proper graphic representation are made through lottery games on the computer terminal. The code is applied to prioritize a set of RandD programs on LWR safety based on attributes including regulatory issues, institutional issues and operation problems. The methodology is described here in detail with its applications. Some of the input includes statistical distributions and subjective judgments on institutional issues. The flexibility of the approach provides a tool for decision makers whether on individual or group level to assess LWR safety priorities and continuously update their strategies

Management of pediatric keratoconus - Evolving role of corneal collagen cross-linking: An update

Directory of Open Access Journals (Sweden)

Vardhaman P Kankariya

2013-01-01

Full Text Available Pediatric keratoconus demonstrates several distinctive management issues in comparison with adult keratoconus with respect to under-diagnosis, poor compliance and modifications in treatment patterns. The major concerns comprise of the accelerated progression of the disease in the pediatric age group and management of co-morbidities such as vernal keratoconjuntivitis. Visual impairment in pediatric patients may affect social and educational development and overall negatively impact their quality of life. The treatment algorithm between adults and pediatric keratoconus has been similar; comprising mainly of visual rehabilitation with spectacles, contacts lenses (soft or rigid and keratoplasty (lamellar or penetrating depending on the stage of the disease. There is a paradigm shift in the management of keratoconus, a new treatment modality, corneal collagen crosslinking (CXL, has been utilized in adult keratoconic patients halting the progression of the disease. CXL has been utilized for over a 10 year period and based on the evidence of efficacy and safety in the adult population; this treatment has been recently utilized in management of pediatric keratoconus. This article will present an update about current management of pediatric keratoconus with special focus on CXL in this age group.

Safety of Nuclear Power Plants: Commissioning and Operation. Specific Safety Requirements

International Nuclear Information System (INIS)

2016-01-01

This publication describes the requirements to be met to ensure the safe operation of nuclear power plants. It takes into account developments in areas such as long term operation of nuclear power plants, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles. A review of Safety Requirements publications was commenced in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan. The review revealed no significant areas of weakness and resulted in just a small set of amendments to strengthen the requirements and facilitate their implementation, which are contained in the present publication

Update of CERN exchange network

CERN Multimedia

2003-01-01

An update of the CERN exchange network will be done next April. Disturbances or even interruptions of telephony services may occur from 4th to 24th April during evenings from 18:30 to 00:00 but will not exceed more than 4 consecutive hours (see tentative planning below). CERN divisions are invited to avoid any change requests (set-ups, move or removals) of telephones and fax machines from 4th to 25th April. Everything will be done to minimize potential inconveniences which may occur during this update. There will be no loss of telephone functionalities. CERN GSM portable phones won't be affected by this change. Should you need more details, please send us your questions by email to Standard.Telephone@cern.ch. DateChange typeAffected areas April 11 Update of switch in LHC 4 LHC 4 Point April 14 Update of switch in LHC 5 LHC 5 Point April 15 Update of switches in LHC 3 and LHC 2 Points LHC 3 and LHC 2 April 22 Update of switch N4 Meyrin Ouest April 23 Update of switch  N6 Prévessin Site Ap...

Updating ARI Educational Benefits Usage Data Bases for Army Regular, Reserve, and Guard: 2005 - 2006

National Research Council Canada - National Science Library

Young, Winnie

2007-01-01

This report describes the updating of ARI's educational benefits usage database with Montgomery GI Bill and Army College Fund data for Army Regular, Reserve, and Guard components over the 2005 and 2006 period...

Health and Safety Research Division progress report for period ending April 30, 1978

Energy Technology Data Exchange (ETDEWEB)

Kaye, S.V.

1978-08-01

The research goal of the Health and Safety Research Division is to conduct basic and applied research that contributes new scientific knowledge with emphasis in biophysical areas that lead to a better understanding of how alternative energy-related technologies affect man. Included in the basic research are fundamental processes that are important to understand formation, mobility, toxicity, detection, and characterization of pollutants. The applied research includes the integration of data from basic and applied studies through development of concepts and methodologies that can be used for energy-related assessments with primary focus on the health and safety of man. The division has no responsibilities for on-site health and safety.

The Safety Case and Safety Assessment for the Disposal of Radioactive Waste

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-09-15

This Safety Guide provides guidance and recommendations on meeting the safety requirements in respect of the safety case and supporting safety assessment for the disposal of radioactive waste. The safety case and supporting safety assessment provide the basis for demonstration of safety and for licensing of radioactive waste disposal facilities and assist and guide decisions on siting, design and operations. The safety case is also the main basis on which dialogue with interested parties is conducted and on which confidence in the safety of the disposal facility is developed. This Safety Guide is relevant for operating organizations preparing the safety case as well as for the regulatory body responsible for developing the regulations and regulatory guidance that determine the basis and scope of the safety case. Contents: 1. Introduction; 2. Demonstrating the safety of radioactive waste disposal; 3. Safety principles and safety requirements; 4. The safety case for disposal of radioactive waste; 5. Radiological impact assessment for the period after closure; 6. Specific issues; 7. Documentation and use of the safety case; 8. Regulatory review process.

Spent nuclear fuel project cold vacuum drying facility safety equipment list

International Nuclear Information System (INIS)

IRWIN, J.J.

1999-01-01

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

Decentralized Consistent Updates in SDN

KAUST Repository

Nguyen, Thanh Dang

2017-04-10

We present ez-Segway, a decentralized mechanism to consistently and quickly update the network state while preventing forwarding anomalies (loops and blackholes) and avoiding link congestion. In our design, the centralized SDN controller only pre-computes information needed by the switches during the update execution. This information is distributed to the switches, which use partial knowledge and direct message passing to efficiently realize the update. This separation of concerns has the key benefit of improving update performance as the communication and computation bottlenecks at the controller are removed. Our evaluations via network emulations and large-scale simulations demonstrate the efficiency of ez-Segway, which compared to a centralized approach, improves network update times by up to 45% and 57% at the median and the 99th percentile, respectively. A deployment of a system prototype in a real OpenFlow switch and an implementation in P4 demonstrate the feasibility and low overhead of implementing simple network update functionality within switches.

Recent Updates on the Systemic and Local Safety of Intranasal Steroids.

Science.gov (United States)

Jang, Tae Young; Kim, Young Hyo

2016-01-01

Allergic rhinitis is a global health problem, and its prevalence rate and socioeconomic burden continue to increase. Intranasal steroid (INS) is the first treatment choice in the majority of patients, because of its ability to effectively control allergic symptoms. However, patients and clinicians are concerned about the potential adverse effects of prolonged INS use. We performed to review for evaluating systemic and local safety of INS use, by searching MEDLINE, EMBASE, and Cochrane Library database for identification of relevant articles. In the present study, the systemic bioavailabilities of several commercially available INSs were researched, and then systemic safeties were reviewed with focus on suppression of the hypothalamus-pituitary-adrenal axis and their effects on pediatric growth. In addition, local adverse effects, such as, epistaxis and nasal septal perforation, were investigated. Finally, the authors proposed some techniques in order to avoid these complications. INSs offer a safe, effective means of treating allergic rhinitis in the short- and long-term with no or minimal adverse systemic and local effects. Copyright© Bentham Science Publishers; For any queries, please email at epub@benthamscience.org.

International laser-safety regulations: a status update

Science.gov (United States)

Weiner, Robert M.

1990-07-01

There is an increase in international laser safety requirements as part of the emphasis on world-wide standardization of products and regulations. In particular the documents which will evolve from the 1992 consolidation efforts of the European Community (EC) will impact both laser manufacturers and users. This paper provides a discussion of the current status of the various laser radiation standards. NORTH AMERICAN REQUIREMENTS United States Requirements on manufacturers from the Food and Drug Administration (FDA) have been in effect since 1975. The Center for Devices and Radiological Health (CDRH) within that agency ensures that these mandatory requirements [1] are satisfied. The CDRH regulations include the division of products into classes depending on their potential for hazard criteria for power measurement and requirements for product features labels and manuals and records and reports. Manufacturers must test products and certify that they comply with the CDRH requirements. User requirements are found in a standard published by the American National Standards Institute (ANSI) and in requirements from several individual states. Specific ANSI standards have also been published for fiber communications systems [34] and for lasers in medical applications [35]. Please note that the Appendix includes additional information on the standards discussed in this paper including sources for obtaining the documents. Canada In the past Canada has had requirements for two specified product categories (bar code scanners and educational lasers) [26 These will be replaced

Thyroid radiofrequency ablation: Updates on innovative devices and techniques

Energy Technology Data Exchange (ETDEWEB)

Park, Hye Sun; Baek, Jung Hwan; Chung, Sae Rom; Choi, Young Jun; Lee, Jeong Hyun [Dept. of Radiology and Research Institute of Radiology, University of Ulsan College of Medicine, Asan Medical Center, Seoul (Korea, Republic of); Park, Auh Whan [Dept. of Radiology, Vascular and Interventional Radiology Section, University of Virginia Health System, Charlottesville (United States)

2017-08-01

Radiofrequency ablation (RFA) is a well-known, effective, and safe method for treating benign thyroid nodules and recurrent thyroid cancers. Thyroid-dedicated devices and basic techniques for thyroid RFA were introduced by the Korean Society of Thyroid Radiology (KSThR) in 2012. Thyroid RFA has now been adopted worldwide, with subsequent advances in devices and techniques. To optimize the treatment efficacy and patient safety, understanding the basic and advanced RFA techniques and selecting the optimal treatment strategy are critical. The goal of this review is to therefore provide updates and analysis of current devices and advanced techniques for RFA treatment of benign thyroid nodules and recurrent thyroid cancers.

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

International Nuclear Information System (INIS)

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

1995-04-01

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

Introduction of the Amendment of IAEA Safety Requirements Reflected Lessons Learned from Fukushima Nuclear Accident

Energy Technology Data Exchange (ETDEWEB)

Ahn, Sang-Kyu; Ahn, Hyung-Joon; Kim, Sun-Hae; Cheong, Jae-Hak [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2015-10-15

for the design basis for the installation and their associated uncertainties; consideration of hazards due to surface faulting and flooding; monitoring of hazards and periodic review of site specific hazards; strengthening the prevention of unacceptable radiological consequences to the public and the environment; preventing severe accident through strengthening the plant design basis, including strengthening the independence of level four of defense in- depth, consideration of external hazards and sufficient margins; periodic safety review; emergency preparedness; feedback of operating experience. The following examples of the IAEA requirements to mitigate the consequences of DECs are: role of the government and the regulatory body for emergency preparedness and response, strengthening severe accident mitigation measures; well defined and updated accident management program.

77 FR 51943 - Procedures for Safety Investigations

Science.gov (United States)

2012-08-28

... rule, Procedures for Safety Investigations, which published July 27, 2012 in the Federal Register, 77... DEFENSE NUCLEAR FACILITIES SAFETY BOARD 10 CFR Part 1708 Procedures for Safety Investigations AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Proposed rule; extension of comment period...

Safety-licensing assessment of NASAP reactor concepts and fuel cycle facilities

International Nuclear Information System (INIS)

Lipinski, W.C.; Prohammer, F.G.; van Erp, J.B.; Seefeldt, W.B.

1978-06-01

Assessments are presented of the safety/licensability of reactor concepts based on information supplied by the Nonproliferation Alternative Systems Assessment Program (NASAP) characterization contractors in their updated responses to the data package for NASAP Rolling Report II. The assessment of the LMFBR includes information from a characterization contractor on alternate fuel cycles but does not include information provided by a characterization contractor on plant-related safety issues. The information provided by the characterization contractors was supplemented by assessments provided by the U. S. Nuclear Regulatory Commission

Environmental Development Plan for Transportation Energy Conservation. FY 79 update