National Library of Energy BETA

Sample records for risk informed safety

  1. 7th Workshop on Risk Informed Regulation and Safety Culture

    Office of Energy Efficiency and Renewable Energy (EERE)

    The 7th Workshop on Risk Informed Regulation and Safety Culture was one of a series of workshops designed by the Office of Nuclear Energy in concert with experts from the Idaho National Laboratory to assist China in developing a comprehensive, successful and efficient Risk-Informed Regulatory framework.

  2. A risk-informed approach to safety margins analysis

    SciTech Connect (OSTI)

    Curtis Smith; Diego Mandelli

    2013-07-01

    The Risk Informed Safety Margins Characterization (RISMC) Pathway is a systematic approach developed to characterize and quantify safety margins of nuclear power plant structures, systems and components. The model has been tested on the Advanced Test Reactor (ATR) at Idaho National Lab.

  3. Risk Informed Safety Margin Characterization (RISMC) Advanced Test Reactor

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Demonstration Case Study | Department of Energy (RISMC) Advanced Test Reactor Demonstration Case Study Risk Informed Safety Margin Characterization (RISMC) Advanced Test Reactor Demonstration Case Study Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about light water reactor design, operation, and plant life extension. A

  4. Risk Informed Margins Management as part of Risk Informed Safety Margin Characterization

    SciTech Connect (OSTI)

    Curtis Smith

    2014-06-01

    The ability to better characterize and quantify safety margin is important to improved decision making about Light Water Reactor (LWR) design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margin management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. In addition, as research and development in the LWR Sustainability (LWRS) Program and other collaborative efforts yield new data, sensors, and improved scientific understanding of physical processes that govern the aging and degradation of plant SSCs needs and opportunities to better optimize plant safety and performance will become known. To support decision making related to economics, readability, and safety, the Risk Informed Safety Margin Characterization (RISMC) Pathway provides methods and tools that enable mitigation options known as risk informed margins management (RIMM) strategies.

  5. Risk Informed Safety Margin Characterization Case Study: Selection of

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Electrical Equipment To Be Subjected to Environmental Qualification | Department of Energy Case Study: Selection of Electrical Equipment To Be Subjected to Environmental Qualification Risk Informed Safety Margin Characterization Case Study: Selection of Electrical Equipment To Be Subjected to Environmental Qualification Reference 1 discussed key elements of the process for developing a margins-based "safety case" to support safe and efficient operation for an extended period. The

  6. Risk-Informed Safety Margin Characterization Methods Development Work

    SciTech Connect (OSTI)

    Smith, Curtis L; Ma, Zhegang; Tom Riley; Mandelli, Diego; Nielsen, Joseph W; Alfonsi, Andrea; Rabiti, Cristian

    2014-09-01

    This report summarizes the research activity developed during the Fiscal year 2014 within the Risk Informed Safety Margin and Characterization (RISMC) pathway within the Light Water Reactor Sustainability (LWRS) campaign. This research activity is complementary to the one presented in the INL/EXT-??? report which shows advances Probabilistic Risk Assessment Analysis using RAVEN and RELAP-7 in conjunction to novel flooding simulation tools. Here we present several analyses that prove the values of the RISMC approach in order to assess risk associated to nuclear power plants (NPPs). We focus on simulation based PRA which, in contrast to classical PRA, heavily employs system simulator codes. Firstly we compare, these two types of analyses, classical and RISMC, for a Boiling water reactor (BWR) station black out (SBO) initiating event. Secondly we present an extended BWR SBO analysis using RAVEN and RELAP-5 which address the comments and suggestions received about he original analysis presented in INL/EXT-???. This time we focus more on the stochastic analysis such probability of core damage and on the determination of the most risk-relevant factors. We also show some preliminary results regarding the comparison between RELAP5-3D and the new code RELAP-7 for a simplified Pressurized Water Reactors system. Lastly we present some conceptual ideas regarding the possibility to extended the RISMC capabilities from an off-line tool (i.e., as PRA analysis tool) to an online-tool. In this new configuration, RISMC capabilities can be used to assist and inform reactor operator during real accident scenarios.

  7. Integrating Safety Assessment Methods using the Risk Informed Safety Margins Characterization (RISMC) Approach

    SciTech Connect (OSTI)

    Curtis Smith; Diego Mandelli

    2013-03-01

    Safety is central to the design, licensing, operation, and economics of nuclear power plants (NPPs). As the current light water reactor (LWR) NPPs age beyond 60 years, there are possibilities for increased frequency of systems, structures, and components (SSC) degradations or failures that initiate safety significant events, reduce existing accident mitigation capabilities, or create new failure modes. Plant designers commonly “over-design” portions of NPPs and provide robustness in the form of redundant and diverse engineered safety features to ensure that, even in the case of well-beyond design basis scenarios, public health and safety will be protected with a very high degree of assurance. This form of defense-in-depth is a reasoned response to uncertainties and is often referred to generically as “safety margin.” Historically, specific safety margin provisions have been formulated primarily based on engineering judgment backed by a set of conservative engineering calculations. The ability to better characterize and quantify safety margin is important to improved decision making about LWR design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margin management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. In addition, as research and development (R&D) in the LWR Sustainability (LWRS) Program and other collaborative efforts yield new data, sensors, and improved scientific understanding of physical processes that govern the aging and degradation of plant SSCs needs and opportunities to better optimize plant safety and performance will become known. To support decision making related to economics, readability, and safety, the RISMC Pathway provides methods and tools that enable mitigation options known as margins management strategies. The purpose of the RISMC Pathway R&D is to support plant decisions for risk-informed

  8. Risk Assessment in Support of DOE Nuclear Safety, Risk Information Notice, June 2010

    Broader source: Energy.gov [DOE]

    On August 12, 2009, the Defense Nuclear Facilities Safety Board(DNFSB) issued Recommendation 2009‐1, Risk Assessment Methodologies at Defense Nuclear Facilities. Thisrecommendation focused on the...

  9. Treatment of Passive Component Reliability in Risk-Informed Safety Margin Characterization FY 2010 Report

    SciTech Connect (OSTI)

    Robert W Youngblood

    2010-09-01

    The Risk-Informed Safety Margin Characterization (RISMC) pathway is a set of activities defined under the U.S. Department of Energy (DOE) Light Water Reactor Sustainability Program. The overarching objective of RISMC is to support plant life-extension decision-making by providing a state-of-knowledge characterization of safety margins in key systems, structures, and components (SSCs). A technical challenge at the core of this effort is to establish the conceptual and technical feasibility of analyzing safety margin in a risk-informed way, which, unlike conventionally defined deterministic margin analysis, is founded on probabilistic characterizations of SSC performance.

  10. 7th Workshop on Risk Informed Regulation and Safety Culture ...

    Energy Savers [EERE]

    their PRA. However, Qinshan will hire two U.S. PRA firms to develop its "Generation Risk Analysis" model. This summer, a team of Qinshan PSA personnel will visit South Texas...

  11. RISK-INFORMED BALANCING OF SAFETY, NONPROLIFERATION, AND ECONOMICS FOR THE SFR

    SciTech Connect (OSTI)

    Apostolakis, George; Driscoll, Michael; Golay, Michael; Kadak, Andrew; Todreas, Neil; Aldmir, Tunc; Denning, Richard; Lineberry, Michael

    2011-10-20

    A substantial barrier to the implementation of Sodium-cooled Fast Reactor (SFR) technology in the short term is the perception that they would not be economically competitive with advanced light water reactors. With increased acceptance of risk-informed regulation, the opportunity exists to reduce the costs of a nuclear power plant at the design stage without applying excessive conservatism that is not needed in treating low risk events. In the report, NUREG-1860, the U.S. Nuclear Regulatory Commission describes developmental activities associated with a risk-informed, scenario-based technology neutral framework (TNF) for regulation. It provides quantitative yardsticks against which the adequacy of safety risks can be judged. We extend these concepts to treatment of proliferation risks. The objective of our project is to develop a risk-informed design process for minimizing the cost of electricity generation within constraints of adequate safety and proliferation risks. This report describes the design and use of this design optimization process within the context of reducing the capital cost and levelized cost of electricity production for a small (possibly modular) SFR. Our project provides not only an evaluation of the feasibility of a risk-informed design process but also a practical test of the applicability of the TNF to an actual advanced, non-LWR design. The report provides results of five safety related and one proliferation related case studies of innovative design alternatives. Applied to previously proposed SFR nuclear energy system concepts We find that the TNF provides a feasible initial basis for licensing new reactors. However, it is incomplete. We recommend improvements in terms of requiring acceptance standards for total safety risks, and we propose a framework for regulation of proliferation risks. We also demonstrate methods for evaluation of proliferation risks. We also suggest revisions to scenario-specific safety risk acceptance standards

  12. Risk-Informing Safety Reviews for Non-Reactor Nuclear Facilities

    SciTech Connect (OSTI)

    Mubayi, V.; Azarm, A.; Yue, M.; Mukaddam, W.; Good, G.; Gonzalez, F.; Bari, R.A.

    2011-03-13

    This paper describes a methodology used to model potential accidents in fuel cycle facilities that employ chemical processes to separate and purify nuclear materials. The methodology is illustrated with an example that uses event and fault trees to estimate the frequency of a specific energetic reaction that can occur in nuclear material processing facilities. The methodology used probabilistic risk assessment (PRA)-related tools as well as information about the chemical reaction characteristics, information on plant design and operational features, and generic data about component failure rates and human error rates. The accident frequency estimates for the specific reaction help to risk-inform the safety review process and assess compliance with regulatory requirements.

  13. Risk-Informed Safety Margin Characterization (RISMC): Integrated Treatment of Aleatory and Epistemic Uncertainty in Safety Analysis

    SciTech Connect (OSTI)

    R. W. Youngblood

    2010-10-01

    The concept of “margin” has a long history in nuclear licensing and in the codification of good engineering practices. However, some traditional applications of “margin” have been carried out for surrogate scenarios (such as design basis scenarios), without regard to the actual frequencies of those scenarios, and have been carried out with in a systematically conservative fashion. This means that the effectiveness of the application of the margin concept is determined in part by the original choice of surrogates, and is limited in any case by the degree of conservatism imposed on the evaluation. In the RISMC project, which is part of the Department of Energy’s “Light Water Reactor Sustainability Program” (LWRSP), we are developing a risk-informed characterization of safety margin. Beginning with the traditional discussion of “margin” in terms of a “load” (a physical challenge to system or component function) and a “capacity” (the capability of that system or component to accommodate the challenge), we are developing the capability to characterize probabilistic load and capacity spectra, reflecting both aleatory and epistemic uncertainty in system response. For example, the probabilistic load spectrum will reflect the frequency of challenges of a particular severity. Such a characterization is required if decision-making is to be informed optimally. However, in order to enable the quantification of probabilistic load spectra, existing analysis capability needs to be extended. Accordingly, the INL is working on a next-generation safety analysis capability whose design will allow for much more efficient parameter uncertainty analysis, and will enable a much better integration of reliability-related and phenomenology-related aspects of margin.

  14. Light Water Reactor Sustainability Program Risk Informed Safety Margin Characterization (RISMC) Advanced Test Reactor Demonstration Case Study

    SciTech Connect (OSTI)

    Curtis Smith; David Schwieder; Cherie Phelan; Anh Bui; Paul Bayless

    2012-08-01

    Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). Consequently, the ability to better characterize and quantify safety margin holds the key to improved decision making about LWR design, operation, and plant life extension. A systematic approach to characterization of safety margins and the subsequent margins management options represents a vital input to the licensee and regulatory analysis and decision making that will be involved. The purpose of the RISMC Pathway R&D is to support plant decisions for risk-informed margins management with the aim to improve economics, reliability, and sustain safety of current NPPs. Goals of the RISMC Pathway are twofold: (1) Develop and demonstrate a risk-assessment method coupled to safety margin quantification that can be used by NPP decision makers as part of their margin recovery strategies. (2) Create an advanced “RISMC toolkit” that enables more accurate representation of NPP safety margin. This report describes the RISMC methodology demonstration where the Advanced Test Reactor (ATR) was used as a test-bed for purposes of determining safety margins. As part of the demonstration, we describe how both the thermal-hydraulics and probabilistic safety calculations are integrated and used to quantify margin management strategies.

  15. The Development of Dynamic Human Reliability Analysis Simulations for Inclusion in Risk Informed Safety Margin Characterization Frameworks

    SciTech Connect (OSTI)

    Jeffrey C. Joe; Diego Mandelli; Ronald L. Boring; Curtis L. Smith; Rachel B. Shirley

    2015-07-01

    The United States Department of Energy is sponsoring the Light Water Reactor Sustainability program, which has the overall objective of supporting the near-term and the extended operation of commercial nuclear power plants. One key research and development (R&D) area in this program is the Risk-Informed Safety Margin Characterization pathway, which combines probabilistic risk simulation with thermohydraulic simulation codes to define and manage safety margins. The R&D efforts to date, however, have not included robust simulations of human operators, and how the reliability of human performance or lack thereof (i.e., human errors) can affect risk-margins and plant performance. This paper describes current and planned research efforts to address the absence of robust human reliability simulations and thereby increase the fidelity of simulated accident scenarios.

  16. Improved Sampling Algorithms in the Risk-Informed Safety Margin Characterization Toolkit

    SciTech Connect (OSTI)

    Mandelli, Diego; Smith, Curtis Lee; Alfonsi, Andrea; Rabiti, Cristian; Cogliati, Joshua Joseph

    2015-09-01

    The RISMC approach is developing advanced set of methodologies and algorithms in order to perform Probabilistic Risk Analyses (PRAs). In contrast to classical PRA methods, which are based on Event-Tree and Fault-Tree methods, the RISMC approach largely employs system simulator codes applied to stochastic analysis tools. The basic idea is to randomly perturb (by employing sampling algorithms) timing and sequencing of events and internal parameters of the system codes (i.e., uncertain parameters) in order to estimate stochastic parameters such as core damage probability. This approach applied to complex systems such as nuclear power plants requires to perform a series of computationally expensive simulation runs given a large set of uncertain parameters. These types of analysis are affected by two issues. Firstly, the space of the possible solutions (a.k.a., the issue space or the response surface) can be sampled only very sparsely, and this precludes the ability to fully analyze the impact of uncertainties on the system dynamics. Secondly, large amounts of data are generated and tools to generate knowledge from such data sets are not yet available. This report focuses on the first issue and in particular employs novel methods that optimize the information generated by the sampling process by sampling unexplored and risk-significant regions of the issue space: adaptive (smart) sampling algorithms. They infer system response from surrogate models constructed from existing samples and predict the most relevant location of the next sample. It is therefore possible to understand features of the issue space with a small number of carefully selected samples. In this report, we will present how it is possible to perform adaptive sampling using the RISMC toolkit and highlight the advantages compared to more classical sampling approaches such Monte-Carlo. We will employ RAVEN to perform such statistical analyses using both analytical cases but also another RISMC code: RELAP-7.

  17. Risk Assessment & Management Information

    Broader source: Energy.gov [DOE]

    NRC - A Proposed Risk Management Regulatory Framework, April 2012 Risk Assessment Technical Experts Working Group (RWG) web page DOE Standard on Development and Use of Probabilistic Risk Assessment in DOE Nuclear Safety Applications (draft), December 2010 Consortium for Risk Evaluation with Stakeholder Participation Workshop on Risk Assessment and Safety Decision Making Under Uncertainty

  18. Risk-Informed Safety Margin Characterization Case Study: Selection of Electrical Equipment to Be Subjected to Environmental Qualification

    SciTech Connect (OSTI)

    D. P. Blanchard; R. W. Youngblood

    2014-06-01

    The Risk-Informed Safety Margin Characterization (RISMC) pathway of the DOE’s Light Water Reactor Sustainability (LWRS) program focuses on advancing the state of the art in safety analysis and risk assessment to support decision-making on nuclear power plant operation well beyond the originally designed lifetime of the plants (i.e., beyond 60 years). Among the issues being addressed in RISMC is the significance of SSC aging and how confident we are about our understanding of its impact on the margin between the loads SSCs are expected to see during normal operation and accident conditions, and the SSC capacities (their ability to resist those loads) as the SSCs age. In this paper, a summary is provided of a case study that examines SSC aging from an environmental qualification (EQ) perspective. The case study illustrates how the state of knowledge regarding SSC margin can be characterized given the overall integrated plant design, and was developed to demonstrate a method for deciding on which cables to focus, which cables are not so important from an environmental qualification margin standpoint, and what plant design features or operating characteristics determine the role that environmental qualification plays in establishing a safety case on which decisions regarding margin can be made. The selection of cables for which demonstration of margin with respect to aging and environmental challenges uses a technique known as Prevention Analysis. Prevention Analysis is a Boolean method for optimal selection of SSCs (that is, those combinations of SSCs both necessary and sufficient to meet a predetermined selection criterion) in a manner that allows demonstration that plant-level safety can be demonstrated by the collection of selected SSCs alone. Choosing the set of SSCs that is necessary and sufficient to satisfy the safety objectives, and demonstrating that the safety objectives can be met effectively, determines where resources are best allocated to assure SSC

  19. Reduced Order Model Implementation in the Risk-Informed Safety Margin Characterization Toolkit

    SciTech Connect (OSTI)

    Mandelli, Diego; Smith, Curtis L.; Alfonsi, Andrea; Rabiti, Cristian; Cogliati, Joshua J.; Talbot, Paul W.; Rinaldi, Ivan; Maljovec, Dan; Wang, Bei; Pascucci, Valerio; Zhao, Haihua

    2015-09-01

    The RISMC project aims to develop new advanced simulation-based tools to perform Probabilistic Risk Analysis (PRA) for the existing fleet of U.S. nuclear power plants (NPPs). These tools numerically model not only the thermo-hydraulic behavior of the reactor primary and secondary systems but also external events temporal evolution and components/system ageing. Thus, this is not only a multi-physics problem but also a multi-scale problem (both spatial, µm-mm-m, and temporal, ms-s-minutes-years). As part of the RISMC PRA approach, a large amount of computationally expensive simulation runs are required. An important aspect is that even though computational power is regularly growing, the overall computational cost of a RISMC analysis may be not viable for certain cases. A solution that is being evaluated is the use of reduce order modeling techniques. During the FY2015, we investigated and applied reduced order modeling techniques to decrease the RICM analysis computational cost by decreasing the number of simulations runs to perform and employ surrogate models instead of the actual simulation codes. This report focuses on the use of reduced order modeling techniques that can be applied to any RISMC analysis to generate, analyze and visualize data. In particular, we focus on surrogate models that approximate the simulation results but in a much faster time (µs instead of hours/days). We apply reduced order and surrogate modeling techniques to several RISMC types of analyses using RAVEN and RELAP-7 and show the advantages that can be gained.

  20. Risk and Safety Assessment

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal ... Natural Gas Supercritical CO2-Brayton Cycle Geothermal Safety, Security & ...

  1. Safety Staff Contact Information

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Safety Staff Contact Information Print Contact Extension Location CONTROL ROOM (24/7) 4969 80-140 Floor Operations Floor Operators 7464 (RING) 80-159 Building Manager This e-mail address is being protected from spambots. You need JavaScript enabled to view it 7358 80-151 Building Emergency Team (BET) This e-mail address is being protected from spambots. You need JavaScript enabled to view it (Leader) This e-mail address is being protected from spambots. You need JavaScript enabled to view it

  2. Safety Staff Contact Information

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Safety Staff Contact Information Print Contact Extension Location CONTROL ROOM (24/7) 4969 80-140 Floor Operations Floor Operators 7464 (RING) 80-159 Building Manager This e-mail address is being protected from spambots. You need JavaScript enabled to view it 7358 80-151 Building Emergency Team (BET) This e-mail address is being protected from spambots. You need JavaScript enabled to view it (Leader) This e-mail address is being protected from spambots. You need JavaScript enabled to view it

  3. Safety Staff Contact Information

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Safety Staff Contact Information Print Contact Extension Location CONTROL ROOM (24/7) 4969 80-140 Floor Operations Floor Operators 7464 (RING) 80-159 Building Manager This e-mail address is being protected from spambots. You need JavaScript enabled to view it 7358 80-151 Building Emergency Team (BET) This e-mail address is being protected from spambots. You need JavaScript enabled to view it (Leader) This e-mail address is being protected from spambots. You need JavaScript enabled to view it

  4. Safety Staff Contact Information

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Safety Staff Contact Information Print Contact Extension Location CONTROL ROOM (24/7) 4969 80-140 Floor Operations Floor Operators 7464 (RING) 80-159 Building Manager This e-mail address is being protected from spambots. You need JavaScript enabled to view it 7358 80-151 Building Emergency Team (BET) This e-mail address is being protected from spambots. You need JavaScript enabled to view it (Leader) This e-mail address is being protected from spambots. You need JavaScript enabled to view it

  5. Risk and Safety Assessment

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    and Safety Assessment - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Energy Defense Waste Management Programs Advanced

  6. HANFORD SAFETY ANALYSIS & RISK ASSESSMENT HANDBOOK (SARAH)

    SciTech Connect (OSTI)

    EVANS, C B

    2004-12-21

    The purpose of the Hanford Safety Analysis and Risk Assessment Handbook (SARAH) is to support the development of safety basis documentation for Hazard Category 2 and 3 (HC-2 and 3) U.S. Department of Energy (DOE) nuclear facilities to meet the requirements of 10 CFR 830, ''Nuclear Safety Management''. Subpart B, ''Safety Basis Requirements.'' Consistent with DOE-STD-3009-94, Change Notice 2, ''Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses'' (STD-3009), and DOE-STD-3011-2002, ''Guidance for Preparation of Basis for Interim Operation (BIO) Documents'' (STD-3011), the Hanford SARAH describes methodology for performing a safety analysis leading to development of a Documented Safety Analysis (DSA) and derivation of Technical Safety Requirements (TSR), and provides the information necessary to ensure a consistently rigorous approach that meets DOE expectations. The DSA and TSR documents, together with the DOE-issued Safety Evaluation Report (SER), are the basic components of facility safety basis documentation. For HC-2 or 3 nuclear facilities in long-term surveillance and maintenance (S&M), for decommissioning activities, where source term has been eliminated to the point that only low-level, residual fixed contamination is present, or for environmental remediation activities outside of a facility structure, DOE-STD-1120-98, ''Integration of Environment, Safety, and Health into Facility Disposition Activities'' (STD-1120), may serve as the basis for the DSA. HC-2 and 3 environmental remediation sites also are subject to the hazard analysis methodologies of this standard.

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

    SciTech Connect (OSTI)

    Curtis Smith; Cristian Rabiti; Richard Martineau

    2012-11-01

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

  8. Nuclear Safety Information | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Nuclear Safety Information Nuclear Safety Information Idaho National Laboratory's Advanced Test Reactor (ATR) | April 8, 2009 Idaho National Laboratory's Advanced Test Reactor (ATR) | April 8, 2009 Nuclear Facilities List and Map Nuclear Safety Regulatory Framework Summary Pamphlet, Nuclear Safety at the Department of Energy External Nuclear Safety Links Nuclear Regulatory Commission (NRC) Defense Nuclear Facilities Safety Board Contact Tom Staker

  9. Progress toward risk informed regulation

    SciTech Connect (OSTI)

    Rogers, K.C.

    1997-01-01

    For the last several years, the NRC, with encouragement from the industry, has been moving in the direction of risk informed regulation. This is consistent with the regulatory principle of efficiency, formally adopted by the Nuclear Regulatory Commission in 1991, which requires that regulatory activities be consistent with the degree of risk reduction they achieve. Probabilistic risk analysis has become the tool of choice for selecting the best of several alternatives. Closely related to risk informed regulation is the development of performance based rules. Such rules focus on the end result to be achieved. They do not specify the process, but instead establish the goals to be reached and how the achievement of those goals is to be judged. The inspection and enforcement activity is based on whether or not the goals have been met. The author goes on to offer comments on the history of the development of this process and its probable development in the future. He also addresses some issues which must be resolved or at least acknowledged. The success of risk informed regulation ultimately depends on having sufficiently reliable data to allow quantification of regulatory alternatives in terms of relative risk. Perhaps the area of human reliability and organizational performance has the greatest potential for improvement in reactor safety. The ability to model human performance is significantly less developed that the ability to model mechanical or electrical systems. The move toward risk informed, performance based regulation provides an unusual, perhaps unique, opportunity to establish a more rational, more effective basis for regulation.

  10. Risk Informed Safety Margin Characterization Case Study: Selection of Electrical Equipment To Be Subjected to Environmental Qualification

    SciTech Connect (OSTI)

    D. Blanchard; R. Youngblood

    2012-04-01

    In general, the margins-based safety case helps the decision-maker manage plant margins most effectively. It tells the plant decision-maker such things as what margin is present (at the plant level, at the functional level, at the barrier level, at the component level), and where margin is thin or perhaps just degrading. If the plant is safe, it tells the decision-maker why the plant is safe and where margin needs to be maintained, and perhaps where the plant can afford to relax.

  11. Evaluation of residue drum storage safety risks

    SciTech Connect (OSTI)

    Conner, W.V.

    1994-06-17

    A study was conducted to determine if any potential safety problems exist in the residue drum backlog at the Rocky Flats Plant. Plutonium residues stored in 55-gallon drums were packaged for short-term storage until the residues could be processed for plutonium recovery. These residues have now been determined by the Department of Energy to be waste materials, and the residues will remain in storage until plans for disposal of the material can be developed. The packaging configurations which were safe for short-term storage may not be safe for long-term storage. Interviews with Rocky Flats personnel involved with packaging the residues reveal that more than one packaging configuration was used for some of the residues. A tabulation of packaging configurations was developed based on the information obtained from the interviews. A number of potential safety problems were identified during this study, including hydrogen generation from some residues and residue packaging materials, contamination containment loss, metal residue packaging container corrosion, and pyrophoric plutonium compound formation. Risk factors were developed for evaluating the risk potential of the various residue categories, and the residues in storage at Rocky Flats were ranked by risk potential. Preliminary drum head space gas sampling studies have demonstrated the potential for formation of flammable hydrogen-oxygen mixtures in some residue drums.

  12. TWRS safety and technical integration risk management plan

    SciTech Connect (OSTI)

    Fordham, R.A.

    1996-03-12

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

  13. Fire Risk Implications in Safety Analysis Reports

    SciTech Connect (OSTI)

    Blanchard, A.

    1999-03-31

    Fire can be a significant risk for facilities that store and handle radiological material. Such events must be evaluated as part of a comprehensive safety analysis. SRS has been developing methods to evaluate radiological fire risk in such facilities. These methods combined with the analysis techniques proposed by DOE-STD-3009-94 have provided a better understanding of how fire risks in nuclear facilities should be managed. To ensure that these new insights are properly disseminated the DOE Savannah River Office and the Defense Nuclear Facility Safety Board (DNFSB) requested Westinghouse Savannah River Company (WSRC) prepare this paper.

  14. Risk assessment activities at NIOSH: Information resources and needs

    SciTech Connect (OSTI)

    Stayner, L.T.; Meinhardt, T.; Hardin, B.

    1990-12-31

    Under the Occupational Safety and Health, and Mine Safety and Health Acts, the National Institute for Occupational Safety and Health (NIOSH) is charged with development of recommended occupational safety and health standards, and with conducting research to support the development of these standards. Thus, NIOSH has been actively involved in the analysis of risk associated with occupational exposures, and in the development of research information that is critical for the risk assessment process. NIOSH research programs and other information resources relevant to the risk assessment process are described in this paper. Future needs for information resources are also discussed.

  15. Nuclear safety information sharing agreement between NRC and...

    Office of Environmental Management (EM)

    Nuclear safety information sharing agreement between NRC and DOE's Office of Environment, Health, Safety and Security Nuclear safety information sharing agreement between NRC and ...

  16. Reactor operation safety information document

    SciTech Connect (OSTI)

    Not Available

    1990-01-01

    The report contains a reactor facility description which includes K, P, and L reactor sites, structures, operating systems, engineered safety systems, support systems, and process and effluent monitoring systems; an accident analysis section which includes cooling system anomalies, radioactive materials releases, and anticipated transients without scram; a summary of onsite doses from design basis accidents; severe accident analysis (reactor core disruption); a description of operating contractor organization and emergency planning; and a summary of reactor safety evolution. (MB)

  17. September 10th Webinar for the Energy Storage Safety Working Group on Safety Validation and Risk Assessment R&D

    Broader source: Energy.gov [DOE]

    On Thursday, September 10, the Office of Electricity Delivery and Energy Reliability (OE), together with Sandia National Laboratories, will present a kick-off webinar for the Energy Storage Safety Working Group on Safety Validation and Risk Assessment Research and Development. Information on current energy storage safety R&D across government, industry and academia will be shared, as well as activities from the other two OE Energy Storage Safety working groups on Codes, Standards, and Regulations, and Outreach.

  18. Robustness of RISMC Insights under Alternative Aleatory/Epistemic Uncertainty Classifications: Draft Report under the Risk-Informed Safety Margin Characterization (RISMC) Pathway of the DOE Light Water Reactor Sustainability Program

    SciTech Connect (OSTI)

    Unwin, Stephen D.; Eslinger, Paul W.; Johnson, Kenneth I.

    2012-09-20

    The Risk-Informed Safety Margin Characterization (RISMC) pathway is a set of activities defined under the U.S. Department of Energy (DOE) Light Water Reactor Sustainability Program. The overarching objective of RISMC is to support plant life-extension decision-making by providing a state-of-knowledge characterization of safety margins in key systems, structures, and components (SSCs). A technical challenge at the core of this effort is to establish the conceptual and technical feasibility of analyzing safety margin in a risk-informed way, which, unlike conventionally defined deterministic margin analysis, would be founded on probabilistic characterizations of uncertainty in SSC performance. In the context of probabilistic risk assessment (PRA) technology, there has arisen a general consensus about the distinctive roles of two types of uncertainty: aleatory and epistemic, where the former represents irreducible, random variability inherent in a system, whereas the latter represents a state of knowledge uncertainty on the part of the analyst about the system which is, in principle, reducible through further research. While there is often some ambiguity about how any one contributing uncertainty in an analysis should be classified, there has nevertheless emerged a broad consensus on the meanings of these uncertainty types in the PRA setting. However, while RISMC methodology shares some features with conventional PRA, it will nevertheless be a distinctive methodology set. Therefore, the paradigms for classification of uncertainty in the PRA setting may not fully port to the RISMC environment. Yet the notion of risk-informed margin is based on the characterization of uncertainty, and it is therefore critical to establish a common understanding of uncertainty in the RISMC setting.

  19. Integrated risk information system (IRIS)

    SciTech Connect (OSTI)

    Tuxen, L.

    1990-12-31

    The Integrated Risk Information System (IRIS) is an electronic information system developed by the US Environmental Protection Agency (EPA) containing information related to health risk assessment. IRIS is the Agency`s primary vehicle for communication of chronic health hazard information that represents Agency consensus following comprehensive review by intra-Agency work groups. The original purpose for developing IRIS was to provide guidance to EPA personnel in making risk management decisions. This original purpose for developing IRIS was to guidance to EPA personnel in making risk management decisions. This role has expanded and evolved with wider access and use of the system. IRIS contains chemical-specific information in summary format for approximately 500 chemicals. IRIS is available to the general public on the National Library of Medicine`s Toxicology Data Network (TOXNET) and on diskettes through the National Technical Information Service (NTIS).

  20. Information needs for risk assessment

    SciTech Connect (OSTI)

    DeRosa, C.T.; Choudhury, H.; Schoeny, R.S.

    1990-12-31

    Risk assessment can be thought of as a conceptual approach to bridge the gap between the available data and the ultimate goal of characterizing the risk or hazard associated with a particular environmental problem. To lend consistency to and to promote quality in the process, the US Environmental Protection Agency (EPA) published Guidelines for Risk Assessment of Carcinogenicity, Developmental Toxicity, Germ Cell Mutagenicity and Exposure Assessment, and Risk Assessment of Chemical Mixtures. The guidelines provide a framework for organizing the information, evaluating data, and for carrying out the risk assessment in a scientifically plausible manner. In the absence of sufficient scientific information or when abundant data are available, the guidelines provide alternative methodologies that can be employed in the risk assessment. 4 refs., 3 figs., 2 tabs.

  1. The risk assessment information system

    SciTech Connect (OSTI)

    Kerr, S.B.; Bonczek, R.R.; McGinn, C.W.; Land, M.L.; Bloom, L.D.; Sample, B.E.; Dolislager, F.G.

    1998-06-01

    In an effort to provide service-oriented environmental risk assessment expertise, the Department of Energy (DOE) Center for Risk Excellence (CRE) and DOE Oak Ridge Operations Office (ORO) are sponsoring Oak Ridge National Laboratory (ORNL) to develop a web-based system for disseminating risk tools and information to its users. This system, the Risk Assessment Information System (RAIS), was initially developed to support the site-specific needs of the DOE-ORO Environmental Restoration Risk Assessment Program. With support from the CRE, the system is currently being expanded to benefit all DOE risk information users and can be tailored to meet site-specific needs. Taking advantage of searchable and executable databases, menu-driven queries, and data downloads, using the latest World Wide Web technologies, the RAIS offers essential tools that are used in the risk assessment process or anywhere from project scoping to implementation. The RAIS tools can be located directly at http://risk.lsd.ornl.gov/homepage/rap{_}tool.htm or through the CRE`s homepage at http://www.doe.gov/riskcenter/home.html.

  2. Air Risk Information Support Center

    SciTech Connect (OSTI)

    Shoaf, C.R.; Guth, D.J.

    1990-12-31

    The Air Risk Information Support Center (Air RISC) was initiated in early 1988 by the US Environmental Protection Agency`s (EPA) Office of Health and Environmental Assessment (OHEA) and the Office of Air Quality Planning and Standards (OAQPS) as a technology transfer effort that would focus on providing information to state and local environmental agencies and to EPA Regional Offices in the areas of health, risk, and exposure assessment for toxic air pollutants. Technical information is fostered and disseminated by Air RISCs three primary activities: (1) a {open_quotes}hotline{close_quotes}, (2) quick turn-around technical assistance projects, and (3) general technical guidance projects. 1 ref., 2 figs.

  3. Hanford safety analysis and risk assessment handbook (SARAH)

    SciTech Connect (OSTI)

    GARVIN, L.J.

    2003-01-20

    The purpose of the Hanford Safety Analysis and Risk Assessment Handbook (SARAH) is to support the development of safety basis documentation for Hazard Category 1,2, and 3 U.S. Department of Energy (DOE) nuclear facilities. SARAH describes currently acceptable methodology for development of a Documented Safety Analysis (DSA) and derivation of technical safety requirements (TSR) based on 10 CFR 830, ''Nuclear Safety Management,'' Subpart B, ''Safety Basis Requirements,'' and provides data to ensure consistency in approach.

  4. Quickstart Guide, Nuclear Safety Information Dashboard - September 2012 |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Department of Energy Quickstart Guide, Nuclear Safety Information Dashboard - September 2012 Quickstart Guide, Nuclear Safety Information Dashboard - September 2012 September 2012 Quickstart guide on how to use the features of Nuclear Safety Information dashboard tool. Quickstart Guide, Nuclear Safety Information Dashboard - September 2012 (632.92 KB) More Documents & Publications Development of the Nuclear Safety Information Dashboard - September 2012 Enforcement Guidance Supplement

  5. Pilot Project: Nuclear Safety Information Dashboard | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Pilot Project: Nuclear Safety Information Dashboard Pilot Project: Nuclear Safety Information Dashboard The Nuclear Safety Information (NSI) Dashboard provides a new user interface to the Occurrence Reporting and Processing System (ORPS) to easily identify, organize, and analyze nuclear safety-related events reported into ORPS. The NSI Dashboard displays information developed from occurrence information reported into DOE's ORPS database. Events or conditions associated with nuclear safety are

  6. Public Order and Safety | Open Energy Information

    Open Energy Info (EERE)

    Safety Jump to: navigation, search Building Type Public Order and Safety Definition Buildings used for the preservation of law and order or public safety. Sub Categories police...

  7. Public Health and Safety | Open Energy Information

    Open Energy Info (EERE)

    Health and Safety Jump to: navigation, search Retrieved from "http:en.openei.orgwindex.php?titlePublicHealthandSafety&oldid687683" Feedback Contact needs updating Image...

  8. Comparison of a Traditional Probabilistic Risk Assessment Approach with Advanced Safety Analysis

    SciTech Connect (OSTI)

    Smith, Curtis L; Mandelli, Diego; Zhegang Ma

    2014-11-01

    As part of the Light Water Sustainability Program (LWRS) [1], the purpose of the Risk Informed Safety Margin Characterization (RISMC) [2] Pathway research and development (R&D) is to support plant decisions for risk-informed margin management with the aim to improve economics, reliability, and sustain safety of current NPPs. In this paper, we describe the RISMC analysis process illustrating how mechanistic and probabilistic approaches are combined in order to estimate a safety margin. We use the scenario of a “station blackout” (SBO) wherein offsite power and onsite power is lost, thereby causing a challenge to plant safety systems. We describe the RISMC approach, illustrate the station blackout modeling, and contrast this with traditional risk analysis modeling for this type of accident scenario. We also describe our approach we are using to represent advanced flooding analysis.

  9. Executive Order 13045, Protection of Children from Environmental Health Risks and Safety Risks

    Broader source: Energy.gov [DOE]

    Each Federal agency: (a) shall make it a high priority to identify and assess environmental health risks and safety risks that may disproportionately affect children; and (b) shall ensure that its...

  10. Nuclear safety information sharing agreement between NRC and DOE’s Office of Environment, Health, Safety and Security

    Broader source: Energy.gov [DOE]

    Nuclear safety information sharing agreement between NRC and DOE’s Office of Environment, Health, Safety and Security.

  11. Risk-informed inservice test activities at the NRC

    SciTech Connect (OSTI)

    Fischer, D.; Cheok, M.; Hsia, A.

    1996-12-01

    The operational readiness of certain safety-related components is vital to the safe operation of nuclear power plants. Inservice testing (IST) is one of the mechanisms used by licensees to ensure this readiness. In the past, the type and frequency of IST have been based on the collective best judgment of the NRC and industry in an ASME Code consensus process and NRC rulemaking process. Furthermore, IST requirements have not explicitly considered unique component and system designs and contribution to overall plant risk. Because of the general nature of ASME Code test requirements and non-reliance on risk estimates, current IST requirements may not adequately emphasize testing those components that are most important to safety and may overly emphasize testing of less safety significant components. Nuclear power plant licensees are currently interested in optimizing testing by applying resources in more safety significant areas and, where appropriate, reducing measures in less safety-significant areas. They are interested in maintaining system availability and reducing overall maintenance costs in ways that do not adversely affect safety. The NRC has been interested in using probabilistic, as an adjunct to deterministic, techniques to help define the scope, type and frequency of IST. The development of risk-informed IST programs has the potential to optimize the use of NRC and industry resources without adverse affect on safety.

  12. Safety Basis Information System | Department of Energy

    Energy Savers [EERE]

    Click on the above link to log in to the Safety Basis web interface. "RESTRICTED; access ... Click on the above link to access the form to request access to the Safety Basis web ...

  13. Preparing for CAAA risk management plans: The lessons of OSHA PSM process safety management

    SciTech Connect (OSTI)

    Gillespie, D.P. [Control Systems Consultants, Inc., Ashland, KY (United States)

    1994-12-31

    29 CFR 1910.119 OSHA Process Safety Management (PSM) became law in 1992, presenting covered facilities with extraordinarily comprehensive and demanding requirements for information management. This paper reports an approach adopted by petrochemical plants that have pioneered automated, integrated compliance with PSM information requirements. The approach is worthy of consideration by the many additional plants that will be covered by 40 CFR Part 67 Risk Management Programs for Chemical Accidental Release Prevention (RNT), which closely parallels PSM`s information requirements.

  14. Risk and Work Configuration Management as a Function of Integrated Safety Management

    SciTech Connect (OSTI)

    Lana Buehrer, Michele Kelly, Fran Lemieux, Fred Williams

    2007-11-30

    National Security Technologies, LLC (NSTec), has established a work management program and corresponding electronic Facilities and Operations Management Information System (e-FOM) to implement Integrated Safety Management (ISM). The management of work scopes, the identification of hazards, and the establishment of implementing controls are reviewed and approved through electronic signatures. Through the execution of the program and the implementation of the electronic system, NSTec staff work within controls and utilize feedback and improvement process. The Integrated Work Control Manual further implements the five functions of ISM at the Activity level. By adding the Risk and Work Configuration Management program, NSTec establishes risk acceptance (business and physical) for liabilities within the performance direction and work management processes. Requirements, roles, and responsibilities are specifically identified in the program while e-FOM provides the interface and establishes the flowdown from the Safety Chain to work and facilities management processes to company work-related directives, and finally to Subject Matter Expert concurrence. The Program establishes, within the defined management structure, management levels for risk identification, risk mitigation (controls), and risk acceptance (business and physical) within the Safety Chain of Responsibility. The Program also implements Integrated Safeguards and Security Management within the NSTec Safety Chain of Responsibility. Once all information has been entered into e-FOM, approved, and captured as data, the information becomes searchable and sortable by hazard, location, organization, mitigating controls, etc.

  15. PRA and Risk Informed Analysis

    SciTech Connect (OSTI)

    Bernsen, Sidney A.; Simonen, Fredric A.; Balkey, Kenneth R.

    2006-01-01

    The Boiler and Pressure Vessel Code (BPVC) of the American Society of Mechanical Engineers (ASME) has introduced a risk based approach into Section XI that covers Rules for Inservice Inspection of Nuclear Power Plant Components. The risk based approach requires application of the probabilistic risk assessments (PRA). Because no industry consensus standard existed for PRAs, ASME has developed a standard to evaluate the quality level of an available PRA needed to support a given risk based application. The paper describes the PRA standard, Section XI application of PRAs, and plans for broader applications of PRAs to other ASME nuclear codes and standards. The paper addresses several specific topics of interest to Section XI. Important consideration are special methods (surrogate components) used to overcome the lack of PRA treatments of passive components in PRAs. The approach allows calculations of conditional core damage probabilities both for component failures that cause initiating events and failures in standby systems that decrease the availability of these systems. The paper relates the explicit risk based methods of the new Section XI code cases to the implicit consideration of risk used in the development of Section XI. Other topics include the needed interactions of ISI engineers, plant operating staff, PRA specialists, and members of expert panels that review the risk based programs.

  16. Safety Basis Information System | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Request Click on the above link to access the form to request access to the Safety Basis web interface. If you need assistance logging in, please AU UserSupport. Contact Nimi Rao...

  17. Safety and Operational Guidelines | Open Energy Information

    Open Energy Info (EERE)

    Safety and Operational Guidelines Jump to: navigation, search This article is a stub. You can help OpenEI by expanding it. Retrieved from "http:en.openei.orgw...

  18. Risk Informing Environmental Cleanup Priorities

    Broader source: Energy.gov [DOE]

    Presentation from the 2015 Annual Performance and Risk Assessment (P&RA) Community of Practice (CoP) Technical Exchange Meeting held in Richland, Washington on December 15-16, 2015.

  19. Information needs for risk management/communication

    SciTech Connect (OSTI)

    Bennett, D.A.

    1990-12-31

    The hazardous waste cleanup program under the Comprehensive Environmental Response, Compensation, and Liability Act (Superfund) is delegated to the ten Regions of the US Environmental Protection Agency (EPA) and has, to date, identified more than 33,000 sites for consideration. The size and complexity of the program places great demands on those who would provide information to achieve national consistency in application of risk assessment while meeting site-specific needs for risk management and risk communication.

  20. Guidelines for nuclear power plant safety issue prioritization information development. Supplement 4

    SciTech Connect (OSTI)

    Tabatabai, A.S.; Fecht, B.A.; Powers, T.B.; Bickford, W.E.; Andrews, W.B.; Gallucci, R.H.V.; Bian, S.H.; Daling, P.M.; Eschbach, E.J.; Allen, C.H.

    1986-07-01

    This is the fifth in a series of reports to document the use of a methodology developed by the Pacific Northwest Laboratory to calculate, for prioritization purposes, the risk, dose and cost impacts of implementing resolutions to reactor safety issues (NUREG/CR-2800, Andrews et al. 1983). This report contains results of issue-specific analyses for 23 issues. Each issue was considered within the constraints of available information as of winter 1986, and two staff-weeks of labor. The results are referenced, as one consideration in setting priorities for reactor safety issues, in NUREG-0933, ''A Prioritization of Generic Safety Issues.''

  1. Reactor Safety Planning for Prometheus Project, for Naval Reactors Information

    SciTech Connect (OSTI)

    P. Delmolino

    2005-05-06

    The purpose of this letter is to submit to Naval Reactors the initial plan for the Prometheus project Reactor Safety work. The Prometheus project is currently developing plans for cold physics experiments and reactor prototype tests. These tests and facilities may require safety analysis and siting support. In addition to the ground facilities, the flight reactor units will require unique analyses to evaluate the risk to the public from normal operations and credible accident conditions. This letter outlines major safety documents that will be submitted with estimated deliverable dates. Included in this planning is the reactor servicing documentation and shipping analysis that will be submitted to Naval Reactors.

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

    SciTech Connect (OSTI)

    REEP, I.E.

    1999-05-12

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

  3. Transactions of the nineteenth water reactor safety information meeting

    SciTech Connect (OSTI)

    Weiss, A.J.

    1991-10-01

    This report contains summaries of papers on reactor safety research to be presented at the 19th Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel in Bethesda, Maryland, October 28--30, 1991. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, USNRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the Electric Power Research Institute (EPRI), the nuclear industry, and from the governments and industry in Europe and Japan are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting, and are given in the order of their presentation in each session. The individual summaries have been cataloged separately.

  4. Analyses to support development of risk-informed separation distances for hydrogen codes and standards.

    SciTech Connect (OSTI)

    LaChance, Jeffrey L.; Houf, William G.; Fluer, Inc., Paso Robels, CA; Fluer, Larry; Middleton, Bobby

    2009-03-01

    The development of a set of safety codes and standards for hydrogen facilities is necessary to ensure they are designed and operated safely. To help ensure that a hydrogen facility meets an acceptable level of risk, code and standard development organizations are tilizing risk-informed concepts in developing hydrogen codes and standards.

  5. Cyber-Informed Engineering: The Need for a New Risk Informed and Design Methodology

    SciTech Connect (OSTI)

    Price, Joseph Daniel; Anderson, Robert Stephen

    2015-06-01

    Current engineering and risk management methodologies do not contain the foundational assumptions required to address the intelligent adversary’s capabilities in malevolent cyber attacks. Current methodologies focus on equipment failures or human error as initiating events for a hazard, while cyber attacks use the functionality of a trusted system to perform operations outside of the intended design and without the operator’s knowledge. These threats can by-pass or manipulate traditionally engineered safety barriers and present false information, invalidating the fundamental basis of a safety analysis. Cyber threats must be fundamentally analyzed from a completely new perspective where neither equipment nor human operation can be fully trusted. A new risk analysis and design methodology needs to be developed to address this rapidly evolving threatscape.

  6. Guidelines for nuclear power plant safety issue prioritization information development. Supplement 5

    SciTech Connect (OSTI)

    Daling, P.M.; Lavender, J.C.

    1996-07-01

    This is the sixth in a series of reports to document the development and use of a methodology developed by the Pacific Northwest Laboratory (PNL) to calculate, for prioritization purposes, the risk, dose, and cost impacts of implementing potential resolutions to reactor safety issues (see NUREG/CR-2800, Andrews, et al., 1983). This report contains the results of issue-specific analyses for 34 generic issues. Each issue was considered within the constraints of available information at the time the issues were examined and approximately 2 staff-weeks of labor. The results are referenced as one consideration in NUREG-0933, A Prioritization of Generic Safety Issues (Emrit, et al., 1983).

  7. Resources for global risk assessment: The International Toxicity Estimates for Risk (ITER) and Risk Information Exchange (RiskIE) databases

    SciTech Connect (OSTI)

    Wullenweber, Andrea Kroner, Oliver; Kohrman, Melissa; Maier, Andrew; Dourson, Michael; Rak, Andrew; Wexler, Philip; Tomljanovic, Chuck

    2008-11-15

    The rate of chemical synthesis and use has outpaced the development of risk values and the resolution of risk assessment methodology questions. In addition, available risk values derived by different organizations may vary due to scientific judgments, mission of the organization, or use of more recently published data. Further, each organization derives values for a unique chemical list so it can be challenging to locate data on a given chemical. Two Internet resources are available to address these issues. First, the International Toxicity Estimates for Risk (ITER) database ( (www.tera.org/iter)) provides chronic human health risk assessment data from a variety of organizations worldwide in a side-by-side format, explains differences in risk values derived by different organizations, and links directly to each organization's website for more detailed information. It is also the only database that includes risk information from independent parties whose risk values have undergone independent peer review. Second, the Risk Information Exchange (RiskIE) is a database of in progress chemical risk assessment work, and includes non-chemical information related to human health risk assessment, such as training modules, white papers and risk documents. RiskIE is available at (http://www.allianceforrisk.org/RiskIE.htm), and will join ITER on National Library of Medicine's TOXNET ( (http://toxnet.nlm.nih.gov/)). Together, ITER and RiskIE provide risk assessors essential tools for easily identifying and comparing available risk data, for sharing in progress assessments, and for enhancing interaction among risk assessment groups to decrease duplication of effort and to harmonize risk assessment procedures across organizations.

  8. Qualitative Risk Assessment for an LNG Refueling Station and Review of Relevant Safety Issues

    SciTech Connect (OSTI)

    Siu, N.; Herring, J.S.; Cadwallader, L.; Reece, W.; Byers, J.

    1998-02-01

    This report is a qualitative assessment of the public and worker risk involved with the operation of a liquefied natural gas (LNG) vehicle refueling facility. This study includes facility maintenance and operations, tank truck deliveries, and end-use vehicle fueling; it does not treat the risks of LNG vehicles on roadways. Accident initiating events are identified by using a Master Logic Diagram, a Failure Modes and Effects Analysis, and historical operating experiences. The event trees were drawn to depict possible sequences of mitigating events following the initiating events. The phenomenology of LNG and other vehicle fuels is discussed to characterize the hazard posed by LNG usage. Based on the risk modeling and analysis, recommendations are given to improve the safety of LNG refueling stations in the areas of procedures and training, station design, and the dissemination of ``best practice`` information throughout the LNG community.

  9. Interim qualitative risk assessment for an LNG refueling station and review of relevant safety issues

    SciTech Connect (OSTI)

    Siu, N.; Herring, S.; Cadwallader, L.; Reece, W.; Byers, J.

    1997-07-01

    This report is a qualitative assessment of the public and worker risk involved with the operation of a liquefied natural (LNG) vehicle refueling facility. This study includes facility maintenance and operations, tanker truck delivers and end-use vehicle fueling; it does not treat the risks of LNG vehicles on roadways. Accident initiating events are identified by using a Master Logic Diagram, a Failure Modes and Effects analysis and historical operating experiences. The event trees were drawn to depict possible sequences of mitigating events following the initiating events. The phenomenology of LNG and other vehicle fuels is discussed to characterize the hazard posed by LNG usage. Based on the risk modeling and analysis, recommendations are given to improve the safety of LNG refueling stations in the areas of procedures and training, station design, and the dissemination of best practice information throughout the LNG community.

  10. DEVELOPMENT OF RISK-BASED AND TECHNOLOGY-INDEPENDENT SAFETY CRITERIA FOR GENERATION IV SYSTEMS

    SciTech Connect (OSTI)

    William E. Kastenberg; Edward Blandford; Lance Kim

    2009-03-31

    This project has developed quantitative safety goals for Generation IV (Gen IV) nuclear energy systems. These safety goals are risk based and technology independent. The foundations for a new approach to risk analysis has been developed, along with a new operational definition of risk. This project has furthered the current state-of-the-art by developing quantitative safety goals for both Gen IV reactors and for the overall Gen IV nuclear fuel cycle. The risk analysis approach developed will quantify performance measures, characterize uncertainty, and address a more comprehensive view of safety as it relates to the overall system. Appropriate safety criteria are necessary to manage risk in a prudent and cost-effective manner. This study is also important for government agencies responsible for managing, reviewing, and for approving advanced reactor systems because they are charged with assuring the health and safety of the public.

  11. Nuclear Safety Information Agreement Between the U.S. Nuclear Regulatory

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Commission, Office of Nuclear Material Safety and Safeguards, and the U.S. Department of Energy, Office of Environment, Health, Safety and Security | Department of Energy Nuclear Safety Information Agreement Between the U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, and the U.S. Department of Energy, Office of Environment, Health, Safety and Security Nuclear Safety Information Agreement Between the U.S. Nuclear Regulatory Commission, Office of Nuclear

  12. Extracting Information from Narratives: An Application to Aviation Safety Reports

    SciTech Connect (OSTI)

    Posse, Christian; Matzke, Brett D.; Anderson, Catherine M.; Brothers, Alan J.; Matzke, Melissa M.; Ferryman, Thomas A.

    2005-05-12

    Aviation safety reports are the best available source of information about why a flight incident happened. However, stream of consciousness permeates the narratives making difficult the automation of the information extraction task. We propose an approach and infrastructure based on a common pattern specification language to capture relevant information via normalized template expression matching in context. Template expression matching handles variants of multi-word expressions. Normalization improves the likelihood of correct hits by standardizing and cleaning the vocabulary used in narratives. Checking for the presence of negative modifiers in the proximity of a potential hit reduces the chance of false hits. We present the above approach in the context of a specific application, which is the extraction of human performance factors from NASA ASRS reports. While knowledge infusion from experts plays a critical role during the learning phase, early results show that in a production mode, the automated process provides information that is consistent with analyses by human subjects.

  13. Mobius Risk Group LLC | Open Energy Information

    Open Energy Info (EERE)

    Mobius Risk Group LLC Jump to: navigation, search Name: Mobius Risk Group LLC Place: Houston, Texas Zip: TX 77056 Product: A risk advisor to energy-consuming companies, utilities...

  14. Envisory Financial Risk Management | Open Energy Information

    Open Energy Info (EERE)

    Envisory Financial Risk Management Jump to: navigation, search Name: Envisory Financial Risk Management Place: Mnchen, Bavaria, Germany Zip: 80331 Sector: Renewable Energy...

  15. Evaluation of safety assessment methodologies in Rocky Flats Risk Assessment Guide (1985) and Building 707 Final Safety Analysis Report (1987)

    SciTech Connect (OSTI)

    Walsh, B.; Fisher, C.; Zigler, G.; Clark, R.A.

    1990-11-09

    FSARs. Rockwell International, as operating contractor at the Rocky Flats plant, conducted a safety analysis program during the 1980s. That effort resulted in Final Safety Analysis Reports (FSARs) for several buildings, one of them being the Building 707 Final Safety Analysis Report, June 87 (707FSAR) and a Plant Safety Analysis Report. Rocky Flats Risk Assessment Guide, March 1985 (RFRAG85) documents the methodologies that were used for those FSARs. Resources available for preparation of those Rocky Flats FSARs were very limited. After addressing the more pressing safety issues, some of which are described below, the present contractor (EG&G) intends to conduct a program of upgrading the FSARs. This report presents the results of a review of the methodologies described in RFRAG85 and 707FSAR and contains suggestions that might be incorporated into the methodology for the FSAR upgrade effort.

  16. Proceedings of the Twenty-First Water Reactor Safety Information Meeting: Volume 1, Plenary session; Advanced reactor research; advanced control system technology; advanced instrumentation and control hardware; human factors research; probabilistic risk assessment topics; thermal hydraulics; thermal hydraulic research for advanced passive LWRs

    SciTech Connect (OSTI)

    Monteleone, S.

    1994-04-01

    This three-volume report contains 90 papers out of the 102 that were presented at the Twenty-First Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 25--27, 1993. 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, Germany, Japan, Russia, Switzerland, Taiwan, and United Kingdom. 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. Individual papers have been cataloged separately. This document, Volume 1 covers the following topics: Advanced Reactor Research; Advanced Instrumentation and Control Hardware; Advanced Control System Technology; Human Factors Research; Probabilistic Risk Assessment Topics; Thermal Hydraulics; and Thermal Hydraulic Research for Advanced Passive Light Water Reactors.

  17. Nuclear Safety Information Agreement Between the U.S. Nuclear...

    Broader source: Energy.gov (indexed) [DOE]

    Environment, Health, Safety and Security (EHSS DOE), Cathy Haney (Director, Office of Nuclear Materials Safety and Safeguards (NRC)), Marissa Bailey (Director, Division of Fuel...

  18. Nuclear Safety Information Agreement Between the U.S. Nuclear...

    Broader source: Energy.gov (indexed) [DOE]

    DOE), Cathy Haney (Director, Office of Nuclear Materials Safety and Safeguards (NRC)), ... (NRC)) Back Row: Tom Hiltz, Office of Nuclear Safety (EHSS DOE), Roy Zimmerman (Deputy ...

  19. Division of Safety of Dams:About Dam Safety | Open Energy Information

    Open Energy Info (EERE)

    briefly describes activities conducted by the agency to oversee the construction and maintenance of dams for the public safety. Author California Division of Safety of Dams...

  20. Global Framework for Climate Risk Exposure | Open Energy Information

    Open Energy Info (EERE)

    October 2006. Investors require this information in order to analyze a company's business risks and opportunities resulting from climate change, as well as the company's...

  1. Microsoft PowerPoint - Hydropower Meeting Dam Safety Program...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Meeting Dam Safety Program Miles P. Waldron, P.E. Senior Hydropower Program Manager Southwestern Division 16 June 2015 BUILDING STRONG Transition to a Risk Informed Dam Safety ...

  2. Portfolio Risk Modeling | Open Energy Information

    Open Energy Info (EERE)

    (0) NEPA(0) Exploration Technique Information Exploration Group: Data and Modeling Techniques Exploration Sub Group: Modeling Techniques Parent Exploration Technique: Modeling...

  3. Information resource use and need in risk assessment

    SciTech Connect (OSTI)

    Turturro, A.

    1990-12-31

    The manner in which the Food and Drug Administration (FDA) uses information resources comprises an interesting illustration of federal agency information use. A description of the context in which risk assessment occurs within the FDA is followed by a discussion of information access and use, as well as a practical example.

  4. FTCP Site Specific Information – Chief of Nuclear Safety

    Broader source: Energy.gov [DOE]

    Site Specific Information including Contact Information, Annual Workforce Analysis & Staffing Plan Reports, and STSM Self-Assessment.

  5. Preliminary Safety Information Document for the Standard MHTGR. Volume 1, (includes latest Amendments)

    SciTech Connect (OSTI)

    1986-12-01

    With NRC concurrence, the Licensing Plan for the Standard HTGR describes an application program consistent with 10CFR50, Appendix O to support a US Nuclear Regulatory Commission (NRC) review and design certification of an advanced Standard modular High Temperature Gas-Cooled Reactor (MHTGR) design. Consistent with the NRC's Advanced Reactor Policy, the Plan also outlines a series of preapplication activities which have as an objective the early issuance of an NRC Licensability Statement on the Standard MHTGR conceptual design. This Preliminary Safety Information Document (PSID) has been prepared as one of the submittals to the NRC by the US Department of Energy in support of preapplication activities on the Standard MHTGR. Other submittals to be provided include a Probabilistic Risk Assessment, a Regulatory Technology Development Plan, and an Emergency Planning Bases Report.

  6. Energy Department Seeks Information on Geothermal Risk and Uncertainty Management

    Broader source: Energy.gov [DOE]

    The Energy Department's Office of Energy Efficiency and Renewable Energy (EERE) has issued a Request for Information (RFI) to help quantify and manage risk in geothermal exploration, in an effort...

  7. Health Safety & Environmental Protection Committee Site Risks:

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    & Environmental Protection Committee Site Risks:  Radiation - alpha, gamma, beta, neutrons o Plutonium (joint w/ TWC) - IM: Becky, Tom  What is the possibility of criticality?  Sludge samples - is disturbance allowed?  How many tanks are affected?  How is plutonium being monitored? o Plutonium Finishing Plant (PFP) - IM: Tom o RAD Con program - IM: Tom  Chemical o Beryllium - IM: Keith, Mike  continue to monitor o Chemical vapors: IM: Tom  Concern that Industrial

  8. Development of the Nuclear Safety Information Dashboard - September...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    A working group with nuclear safety expertise used paired pairing computer software to ... A computer program was used to combine the results for each "paired pair" in the group and ...

  9. EO 13045: Protection of Children from Environmental Health Risks and Safety Risks (1997) (As Amended by EO 13229 (2001) and EO 13296 (2003))

    Broader source: Energy.gov [DOE]

    Each Federal agency: (a) shall make it a high priority to identify and assess environmental health risks and safety risks that may disproportionately affect children; and (b) shall ensure that its...

  10. Analyses in support of risk-informed natural gas vehicle maintenance facility codes and standards :

    SciTech Connect (OSTI)

    Ekoto, Isaac W.; Blaylock, Myra L.; LaFleur, Angela Christine; LaChance, Jeffrey L.; Horne, Douglas B.

    2014-03-01

    Safety standards development for maintenance facilities of liquid and compressed gas fueled large-scale vehicles is required to ensure proper facility design and operation envelopes. Standard development organizations are utilizing risk-informed concepts to develop natural gas vehicle (NGV) codes and standards so that maintenance facilities meet acceptable risk levels. The present report summarizes Phase I work for existing NGV repair facility code requirements and highlights inconsistencies that need quantitative analysis into their effectiveness. A Hazardous and Operability study was performed to identify key scenarios of interest. Finally, scenario analyses were performed using detailed simulations and modeling to estimate the overpressure hazards from HAZOP defined scenarios. The results from Phase I will be used to identify significant risk contributors at NGV maintenance facilities, and are expected to form the basis for follow-on quantitative risk analysis work to address specific code requirements and identify effective accident prevention and mitigation strategies.

  11. Safety

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    safety Safety All JLF participants must comply fully with all LLNL safety regulations and procedures by becoming a Registered User of the facility. All JLF participants must complete available LLNL safety training: HS5200-W Laser Safety HS4258-W Beryllium Awareness HS4261-W Lead Awareness HS5220-W Electrical Safety Awareness HS6001-W General Employee Radiological HS4240-W Chemical Safety HS4680-W PPE To access these training modules link here [LTRAIN] from inside LLNL, or here from anywhere. All

  12. Development of the Nuclear Safety Information Dashboard- September 2012

    Broader source: Energy.gov [DOE]

    A working group with nuclear safety expertise used paired pairing computer software to develop first, a severity-weighted factor for the 17 Groups of ORPS Reporting Criteria and then, a severity-weighted factor for the sixty-five ORPS reporting criteria.

  13. Safety and Health Regulatory and Policy Response Line- General Information

    Broader source: Energy.gov [DOE]

    The DOE Worker Safety and Health Standards Response Line, established in 1992, is a service that responds to questions DOE, DOE contractor, and DOE subcontractor personnel regarding DOE-adopted and -prescribed standards and directives. These responses may not represent official OSHA policies.

  14. Needs for Risk Informing Environmental Cleanup Decision Making - 13613

    SciTech Connect (OSTI)

    Zhu, Ming; Moorer, Richard

    2013-07-01

    This paper discusses the needs for risk informing decision making by the U.S. Department of Energy (DOE) Office of Environmental Management (EM). The mission of the DOE EM is to complete the safe cleanup of the environmental legacy brought about from the nation's five decades of nuclear weapons development and production and nuclear energy research. This work represents some of the most technically challenging and complex cleanup efforts in the world and is projected to require the investment of billions of dollars and several decades to complete. Quantitative assessments of health and environmental risks play an important role in work prioritization and cleanup decisions of these challenging environmental cleanup and closure projects. The risk assessments often involve evaluation of performance of integrated engineered barriers and natural systems over a period of hundreds to thousands of years, when subject to complex geo-environmental transformation processes resulting from remediation and disposal actions. The requirement of resource investments for the cleanup efforts and the associated technical challenges have subjected the EM program to continuous scrutiny by oversight entities. Recent DOE reviews recommended application of a risk-informed approach throughout the EM complex for improved targeting of resources. The idea behind this recommendation is that by using risk-informed approaches to prioritize work scope, the available resources can be best utilized to reduce environmental and health risks across the EM complex, while maintaining the momentum of the overall EM cleanup program at a sustainable level. In response to these recommendations, EM is re-examining its work portfolio and key decision making with risk insights for the major sites. This paper summarizes the review findings and recommendations from the DOE internal reviews, discusses the needs for risk informing the EM portfolio and makes an attempt to identify topics for R and D in integrated

  15. Informational meeting on new environmental health and safety master's

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Energy Efficiency on Tribal Lands (FOA-0001621) | Department of Energy Informational Webinar: First Steps Toward Developing Renewable Energy and Energy Efficiency on Tribal Lands (FOA-0001621) Informational Webinar: First Steps Toward Developing Renewable Energy and Energy Efficiency on Tribal Lands (FOA-0001621) September 6, 2016 1:00PM to 3:00PM MDT The U.S. Department of Energy Office of Indian Energy is hosting an informational webinar on the funding opportunity, First Steps Toward

  16. Nuclear Safety Risk Management in Refueling Outage of Qinshan Nuclear Power Plant

    SciTech Connect (OSTI)

    Meijing Wu; Guozhang Shen

    2006-07-01

    The NPP is used to planning maintenance, in-service inspection, surveillance test, fuel handling and design modification in the refueling outage; the operator response capability will be reduced plus some of the plant systems out of service or loss of power at this time. Based on 8 times refueling outage experiences of the Qinshan NPP, this article provide some good practice and lesson learned for the nuclear safety risk management focus at four safety function areas of Residual Heat Removal Capability, Inventory Control, Power availability and Reactivity control. (authors)

  17. DOE handbook electrical safety

    SciTech Connect (OSTI)

    1998-01-01

    Electrical Safety Handbook presents the Department of Energy (DOE) safety standards for DOE field offices or facilities involved in the use of electrical energy. It has been prepared to provide a uniform set of electrical safety guidance and information for DOE installations to effect a reduction or elimination of risks associated with the use of electrical energy. The objectives of this handbook are to enhance electrical safety awareness and mitigate electrical hazards to employees, the public, and the environment.

  18. Probabilistic risk analysis toward cost-effective 3S (safety, safeguards, security) implementation

    SciTech Connect (OSTI)

    Suzuki, Mitsutoshi; Mochiji, Toshiro

    2014-09-30

    Probabilistic Risk Analysis (PRA) has been introduced for several decades in safety and nuclear advanced countries have already used this methodology in their own regulatory systems. However, PRA has not been developed in safeguards and security so far because of inherent difficulties in intentional and malicious acts. In this paper, probabilistic proliferation and risk analysis based on random process is applied to hypothetical reprocessing process and physical protection system in nuclear reactor with the Markov model that was originally developed by the Proliferation Resistance and Physical Protection Working Group (PRPPWG) in Generation IV International Framework (GIF). Through the challenge to quantify the security risk with a frequency in this model, integrated risk notion among 3S to pursue the cost-effective installation of those countermeasures is discussed in a heroic manner.

  19. An object-oriented approach to risk and reliability analysis : methodology and aviation safety applications.

    SciTech Connect (OSTI)

    Dandini, Vincent John; Duran, Felicia Angelica; Wyss, Gregory Dane

    2003-09-01

    This article describes how features of event tree analysis and Monte Carlo-based discrete event simulation can be combined with concepts from object-oriented analysis to develop a new risk assessment methodology, with some of the best features of each. The resultant object-based event scenario tree (OBEST) methodology enables an analyst to rapidly construct realistic models for scenarios for which an a priori discovery of event ordering is either cumbersome or impossible. Each scenario produced by OBEST is automatically associated with a likelihood estimate because probabilistic branching is integral to the object model definition. The OBEST methodology is then applied to an aviation safety problem that considers mechanisms by which an aircraft might become involved in a runway incursion incident. The resulting OBEST model demonstrates how a close link between human reliability analysis and probabilistic risk assessment methods can provide important insights into aviation safety phenomenology.

  20. Safety

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering ...

  1. safety

    National Nuclear Security Administration (NNSA)

    contractor at the Nevada National Security Site, has been recognized by the Department of Energy for excellence in occupational safety and health protection. National Nuclear...

  2. Risk-informed assessment of regulatory and design requirements for future nuclear power plants. Annual report

    SciTech Connect (OSTI)

    2000-08-01

    OAK B188 Risk-informed assessment of regulatory and design requirements for future nuclear power plants. Annual report. The overall goal of this research project is to support innovation in new nuclear power plant designs. This project is examining the implications, for future reactors and future safety regulation, of utilizing a new risk-informed regulatory system as a replacement for the current system. This innovation will be made possible through development of a scientific, highly risk-formed approach for the design and regulation of nuclear power plants. This approach will include the development and/or confirmation of corresponding regulatory requirements and industry standards. The major impediment to long term competitiveness of new nuclear plants in the U.S. is the capital cost component--which may need to be reduced on the order of 35% to 40% for Advanced Light Water Reactors (ALWRS) such as System 80+ and Advanced Boiling Water Reactor (ABWR). The required cost reduction for an ALWR such as AP600 or AP1000 would be expected to be less. Such reductions in capital cost will require a fundamental reevaluation of the industry standards and regulatory bases under which nuclear plants are designed and licensed. Fortunately, there is now an increasing awareness that many of the existing regulatory requirements and industry standards are not significantly contributing to safety and reliability and, therefore, are unnecessarily adding to nuclear plant costs. Not only does this degrade the economic competitiveness of nuclear energy, it results in unnecessary costs to the American electricity consumer. While addressing these concerns, this research project will be coordinated with current efforts of industry and NRC to develop risk-informed, performance-based regulations that affect the operation of the existing nuclear plants; however, this project will go further by focusing on the design of new plants.

  3. Final safety analysis report for the Galileo mission: Volume 3 (Book 2), Nuclear risk analysis document: Appendices: Revision 1

    SciTech Connect (OSTI)

    Not Available

    1989-01-25

    It is the purpose of the NRAD to provide an analysis of the range of potential consequences of accidents which have been identified that are associated with the launching and deployment of the Galileo mission spacecraft. The specific consequences analyzed are those associated with the possible release of radioactive material (fuel) of the Radioisotope Thermoelectric Generators (RTGs). They are in terms of radiation doses to people and areas of deposition of radioactive material. These consequence analyses can be used in several ways. One way is to identify the potential range of consequences which might have to be dealt with if there were to be an accident with a release of fuel, so as to assure that, given such an accident, the health and safety of the public will be reasonably protected. Another use of the information, in conjunction with accident and release probabilities, is to estimate the risks associated with the mission. That is, most space launches occur without incident. Given an accident, the most probable result relative to the RTGs is complete containment of the radioactive material. Only a small fraction of accidents might result in a release of fuel and subsequent radiological consequences. The combination of probability with consequence is risk, which can be compared to other human and societal risks to assure that no undue risks are implied by undertaking the mission. Book 2 contains eight appendices.

  4. Transactions of the Twenty-First Water Reactor Safety Information Meeting

    SciTech Connect (OSTI)

    Monteleone, S.

    1993-10-01

    This report contains summaries of papers on reactor safety research to be presented at the 21st Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel, Bethesda, Maryland, October 25--27, 1993. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the Electric Power Research Institute (EPRI), the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting and are given in the order of their presentation in each session.

  5. Transactions of the twenty-fifth water reactor safety information meeting

    SciTech Connect (OSTI)

    Monteleone, S.

    1997-09-01

    This report contains summaries of papers on reactor safety research to be presented at the 25th Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel in Bethesda, Maryland, October 20--22, 1997. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion of information exchanged during the course of the meeting, and are given in order of their presentation in each session.

  6. Process safety management (OSHA) and process risk management (CAA) application. Application to a coke plant

    SciTech Connect (OSTI)

    Graeser, W.C.; Mentzer, W.P.

    1995-12-01

    Risk Management Programs for Chemical Accidental Release Prevention is the name of the proposed rule for the RMP Risk Management Program. The RMP was written in response to several catastrophic releases of hazardous substances. The rule is applicable to facilities that store, process or use greater than threshold quantities of 62 listed flammable chemicals and another 100 listed toxic substances. Additionally, a Risk Management Plan is registered with the EPA, Chemical Safety and Hazardous Investigation Board, state governments and the local emergency planning commission. The Clean Air Act Amendments of 1990 (specifically Section 112r) required the EPA to develop a three phase Risk Management Plan for industry: prevention program; hazard assessment; and emergency response program. The Prevention Program closely follows the OSHA`s Process Safety Management Standard. The Hazard Assessment section requires facilities to develop plans for a worst case scenario. The Emergency Response section defines the steps the facility and each employee will take if a release occurs. This section also needs to be coordinated with the Local Emergency Planning Commission. These regulations are described using Clairton Works as an example of compliance.

  7. Embrittlement Database from the Radiation Safety Information Computational Center

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    The Embrittlement Data Base (EDB) is a comprehensive collection of data from surveillance capsules of U.S. commercial nuclear power reactors and from experiments in material test reactors. The collected data are contained in either the Power Reactor Embrittlement Data Base (PR-EDB) or the Test Reactor Embrittlement Data Base (TR-EDB). The EDB work includes verification of the quality of the EDB, provision for user-friendly software to access and process the data, exploration and/or confirmation of embrittlement prediction models, provision for rapid investigation of regulatory issues, and provision for the technical bases for voluntary consensus standards or regulatory guides. The EDB is designed for use with a personal computer. The data are collected into "raw data files." Traceability of all data is maintained by including complete references along with the page numbers. External data verification of the PR-EDB is the responsibility of the vendors, who were responsible for the insertion and testing of the materials in the surveillance capsules. Internal verification is accomplished by checking against references and checking for inconsistencies. Examples of information contained in the EDBs are: Charpy data, tensile data, reactor type, irradiation environments, fracture toughness data, instrumented Charpy data, pressure-temperature (P-T) data, chemistry data, and material history. The TR-EDB additionally has annealing Charpy data. The current version of the PR-EDB contains the test results from 269 Charpy capsules irradiated in 101 reactors. These results include 320 plate data points, 123 forging data points, 113 standard reference materials (SRMS) or correlation monitor (CM) points, 244 weld material data points, and 220 heat-affected-zone (HAZ) material data points. Similarly, the TR-EDB contains information for 290 SRM or CM points, 342 plate data points, 165 forging data points, 378 welds, and 55 HAZ materials. [copied from http://rsicc.ornl.gov/RelatedLinks.aspx?t=edb

  8. Overview of HyRAM (Hydrogen Risk Assessment Models) Software for Science-Based Safety, Codes, and Standards Webinar

    Broader source: Energy.gov [DOE]

    Access the recording and download the presentation slides from the Fuel Cell Technologies Office webinar "Overview of HyRAM (Hydrogen Risk Assessment Models) Software for Science-Based Safety, Codes, and Standards" held on April 26, 2016.

  9. Defining resilience within a risk-informed assessment framework

    SciTech Connect (OSTI)

    Coles, Garill A.; Unwin, Stephen D.; Holter, Gregory M.; Bass, Robert B.; Dagle, Jeffery E.

    2011-08-01

    The concept of resilience is the subject of considerable discussion in academic, business, and governmental circles. The United States Department of Homeland Security for one has emphasised the need to consider resilience in safeguarding critical infrastructure and key resources. The concept of resilience is complex, multidimensional, and defined differently by different stakeholders. The authors contend that there is a benefit in moving from discussing resilience as an abstraction to defining resilience as a measurable characteristic of a system. This paper proposes defining resilience measures using elements of a traditional risk assessment framework to help clarify the concept of resilience and as a way to provide non-traditional risk information. The authors show various, diverse dimensions of resilience can be quantitatively defined in a common risk assessment framework based on the concept of loss of service. This allows the comparison of options for improving the resilience of infrastructure and presents a means to perform cost-benefit analysis. This paper discusses definitions and key aspects of resilience, presents equations for the risk of loss of infrastructure function that incorporate four key aspects of resilience that could prevent or mitigate that loss, describes proposed resilience factor definitions based on those risk impacts, and provides an example that illustrates how resilience factors would be calculated using a hypothetical scenario.

  10. Guidelines for nuclear-power-plant safety-issue-prioritization information development

    SciTech Connect (OSTI)

    Andrews, W.B.; Gallucci, R.H.V.; Heaberlin, S.W.; Bickford, W.E.; Konzek, G.J.; Strenge, D.L.; Smith, R.I.; Weakley, S.A.

    1983-02-01

    Pacific Northwest Laboratory has developed a methodology, with examples, to calculate - to an approximation serviceable for prioritization purposes - the risk, dose and cost impacts of implementing resolutions to reactor safety issues. This report is an applications guide to issue-specific calculations. A description of the approach, mathematical models, worksheets and step-by-step examples are provided. Analysis using this method is intended to provide comparable results for many issues at a cost of two staff-weeks per issue. Results will be used by the NRC to support decisions related to issue priorities in allocation of resources to complete safety issue resolutions.

  11. Approaches to cancer assessment in EPA's Integrated Risk Information System

    SciTech Connect (OSTI)

    Gehlhaus, Martin W.; Gift, Jeffrey S.; Hogan, Karen A.; Kopylev, Leonid; Schlosser, Paul M.; Kadry, Abdel-Razak

    2011-07-15

    The U.S. Environmental Protection Agency's (EPA) Integrated Risk Information System (IRIS) Program develops assessments of health effects that may result from chronic exposure to chemicals in the environment. The IRIS database contains more than 540 assessments. When supported by available data, IRIS assessments provide quantitative analyses of carcinogenic effects. Since publication of EPA's 2005 Guidelines for Carcinogen Risk Assessment, IRIS cancer assessments have implemented new approaches recommended in these guidelines and expanded the use of complex scientific methods to perform quantitative dose-response assessments. Two case studies of the application of the mode of action framework from the 2005 Cancer Guidelines are presented in this paper. The first is a case study of 1,2,3-trichloropropane, as an example of a chemical with a mutagenic mode of carcinogenic action thus warranting the application of age-dependent adjustment factors for early-life exposure; the second is a case study of ethylene glycol monobutyl ether, as an example of a chemical with a carcinogenic action consistent with a nonlinear extrapolation approach. The use of physiologically based pharmacokinetic (PBPK) modeling to quantify interindividual variability and account for human parameter uncertainty as part of a quantitative cancer assessment is illustrated using a case study involving probabilistic PBPK modeling for dichloromethane. We also discuss statistical issues in assessing trends and model fit for tumor dose-response data, analysis of the combined risk from multiple types of tumors, and application of life-table methods for using human data to derive cancer risk estimates. These issues reflect the complexity and challenges faced in assessing the carcinogenic risks from exposure to environmental chemicals, and provide a view of the current trends in IRIS carcinogenicity risk assessment.

  12. Technical background information for the environmental and safety report, Volume 4: White Oak Lake and Dam

    SciTech Connect (OSTI)

    Oakes, T.W.; Kelly, B.A.; Ohnesorge, W.F.; Eldridge, J.S.; Bird, J.C.; Shank, K.E.; Tsakeres, F.S.

    1982-03-01

    This report has been prepared to provide background information on White Oak Lake for the Oak Ridge National Laboratory Environmental and Safety Report. The paper presents the history of White Oak Dam and Lake and describes the hydrological conditions of the White Oak Creek watershed. Past and present sediment and water data are included; pathway analyses are described in detail.

  13. First Capitol Risk Management LLC | Open Energy Information

    Open Energy Info (EERE)

    Capitol Risk Management LLC Jump to: navigation, search Name: First Capitol Risk Management, LLC Place: Galena, Illinois Zip: 61036 Product: First Capitol Risk Management...

  14. Planning for risk-informed/performance-based fire protection at nuclear power plants. Final report

    SciTech Connect (OSTI)

    Najafi, B.; Parkinson, W.J.; Lee, J.A.

    1997-12-01

    This document presents a framework for discussing issues and building consensus towards use of fire modeling and risk technology in nuclear power plant fire protection program implementation. The plan describes a three-phase approach: development of core technologies, implementation of methods, and finally, case studies and pilot applications to verify viability of such methods. The core technologies are defined as fire modeling, fire and system tests, use of operational data, and system and risk techniques. The implementation phase addresses the programmatic issues involved in implementing a risk-informed/performance-based approach in an integrated approach with risk/performance measures. The programmatic elements include: (1) a relationship with fire codes and standards development as defined by the ongoing effort of NFPA for development of performance-based standards; (2) the ability for NRC to undertake inspection and enforcement; and (3) the benefit to utilities in terms of cost versus safety. The case studies are intended to demonstrate applicability of single issue resolution while pilot applications are intended to check the applicability of the integrated program as a whole.

  15. Evolution of Risk Management at NASA in the Context of Achieving Adequate Safety

    Office of Energy Efficiency and Renewable Energy (EERE)

    Presenter: Homayoon Dezfuli, Ph.D. NASA Technical Fellow for System Safety Office of Safety and Mission Assurance NASA Headquarters

  16. A joint discussion model for assessing safety, health, and environmental risks

    SciTech Connect (OSTI)

    Abbott, R.E.

    1995-12-01

    Industries competing in the global marketplace constantly evaluate potential opportunities for joint ventures and partnerships all over the world. In the petroleum industry, these prospects to explore for and produce oil and gas range geographically from densely populated areas, to offshore, to the remote reaches of a tropical rainforest. There are numerous risks associated with these prospects which must be assessed so that the best investments are selected. The risk categories include: commercial, technical geological, political and safety, health and environmental (SHE). SHE risks are sometimes the most difficult to assess within businesses because they do not allow an easy evaluation of economic impact or other quantification. Additionally, these issues are often not familiar to business development personnel and consequently are not evaluated on an equal basis with other risk criteria. This paper presents a joint discussion model that facilitates the communication between SHE personnel and other members of the multi-disciplinary teams responsible for evaluating and selecting the most attractive prospects. This tool uses a simple approach in contrast to the many quantitative decision-making software products currently available. It provides a set of questions related to relevant SHE issues, establishes a way to approximate the level of uncertainty in the answers, and sums the results so that a comparison among prospects is possible. In the end, a more rigorous, consistent SHE assessment of all prospects is made, and the rationale for each decision is archived so that improvement in the process over time is made easier.

  17. Thermal reactor safety

    SciTech Connect (OSTI)

    Not Available

    1980-06-01

    Information is presented concerning new trends in licensing; seismic considerations and system structural behavior; TMI-2 risk assessment and thermal hydraulics; statistical assessment of potential accidents and verification of computational methods; issues with respect to improved safety; human factors in nuclear power plant operation; diagnostics and activities in support of recovery; LOCA transient analysis; unresolved safety issues and other safety considerations; and fission product transport.

  18. Quantification of margins and uncertainty for risk-informed decision analysis.

    SciTech Connect (OSTI)

    Alvin, Kenneth Fredrick

    2010-09-01

    QMU stands for 'Quantification of Margins and Uncertainties'. QMU is a basic framework for consistency in integrating simulation, data, and/or subject matter expertise to provide input into a risk-informed decision-making process. QMU is being applied to a wide range of NNSA stockpile issues, from performance to safety. The implementation of QMU varies with lab and application focus. The Advanced Simulation and Computing (ASC) Program develops validated computational simulation tools to be applied in the context of QMU. QMU provides input into a risk-informed decision making process. The completeness aspect of QMU can benefit from the structured methodology and discipline of quantitative risk assessment (QRA)/probabilistic risk assessment (PRA). In characterizing uncertainties it is important to pay attention to the distinction between those arising from incomplete knowledge ('epistemic' or systematic), and those arising from device-to-device variation ('aleatory' or random). The national security labs should investigate the utility of a probability of frequency (PoF) approach in presenting uncertainties in the stockpile. A QMU methodology is connected if the interactions between failure modes are included. The design labs should continue to focus attention on quantifying uncertainties that arise from epistemic uncertainties such as poorly-modeled phenomena, numerical errors, coding errors, and systematic uncertainties in experiment. The NNSA and design labs should ensure that the certification plan for any RRW is supported by strong, timely peer review and by an ongoing, transparent QMU-based documentation and analysis in order to permit a confidence level necessary for eventual certification.

  19. Liquid-metal fast-breeder reactors: Preliminary safety and environmental information document. Volume VI

    SciTech Connect (OSTI)

    Not Available

    1980-01-01

    Information is presented concerning LMFBR design characteristics; uranium-plutonium/uranium recycle homogeneous core; uranium-plutonium/uranium spiked recycle heterogeneous core; uranium-plutonium/uranium spiked recycle homogeneous core; uranium-plutonium/thorium spiked recycle heterogeneous core; uranium-plutonium/thorium spiked recycle homogeneous core; thorium-plutonium/thorium spiked recycle homogeneous core; denatured uranium-233/thorium cycle homogeneous core; safety consideration for the LMFBR; and environmental considerations.

  20. Climate Risk and Financial Institutions | Open Energy Information

    Open Energy Info (EERE)

    Corporation Topics: Finance, Co-benefits assessment Website: www.ifc.orgifcextsustainability.nsfAttachmentsByTitlepClimateRisk Climate Risk and Financial Institutions...

  1. Global Climate Change: Risk to Bank Loans | Open Energy Information

    Open Energy Info (EERE)

    Risk to Bank Loans Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Global Climate Change: Risk to Bank Loans AgencyCompany Organization: United Nations...

  2. Risk Level Based Management System: a control banding model for occupational health and safety risk management in a highly regulated environment

    SciTech Connect (OSTI)

    Zalk, D; Kamerzell, R; Paik, S; Kapp, J; Harrington, D; Swuste, P

    2009-05-27

    The Risk Level Based Management System (RLBMS) is an occupational risk management (ORM) model that focuses occupational safety, hygeiene, and health (OSHH) resources on the highest risk procedures at work. This article demonstrates the model's simplicity through an implementation within a heavily regulated research institution. The model utilizes control banding strategies with a stratification of four risk levels (RLs) for many commonly performed maintenance and support activities, characterizing risk consistently for comparable tasks. RLBMS creates an auditable tracking of activities, maximizes OSHH professional field time, and standardizes documentation and control commensurate to a given task's RL. Validation of RLs and their exposure control effectiveness is collected in a traditional quantitative collection regime for regulatory auditing. However, qualitative risk assessment methods are also used within this validation process. Participatory approaches are used throughout the RLBMS process. Workers are involved in all phases of building, maintaining, and improving this model. This work participation also improves the implementation of established controls.

  3. THE RADIATION SAFETY INFORMATION COMPUTATIONAL CENTER (RSICC) - A RESOURCE FOR COMPUTATIONAL TOOLS FOR NUCLEAR APPLICATIONS

    SciTech Connect (OSTI)

    Kirk, Bernadette Lugue

    2009-01-01

    The Radiation Safety Information Computational Center (RSICC), which has been in existence since 1963, is the principal source and repository in the United States for computational tools for nuclear applications. RSICC collects, organizes, evaluates and distributes nuclear software and data involving the transport of neutral and charged particle radiation, and shielding and protection from radiation associated with: nuclear weapons and materials, fission and fusion reactors, outer space, accelerators, medical facilities, and nuclear waste. RSICC serves over 12,000 scientists and engineers from 94 countries. RSICC software provides in-depth coverage of radiation related topics: the physics of the interaction of radiation with matter, radiation production and sources, criticality safety, radiation protection and shielding, radiation detectors and measurements, shielding materials properties, radiation waste management, atmospheric dispersion and environmental dose, medical applications, macro- and micro-dosimetry calculations.

  4. Webinar: Overview of HyRAM (Hydrogen Risk Assessment Models) Software for Science-Based Safety, Codes, and Standards

    Broader source: Energy.gov [DOE]

    The Energy Department will present a live webinar titled "Overview of HyRAM (Hydrogen Risk Assessment Models) Software for Science-Based Safety, Codes, and Standards" on Tuesday, April 26, from 12:00 to 1:00 p.m. Eastern Daylight Time (EDT).

  5. Criticality Safety | Department of Energy

    Office of Environmental Management (EM)

    Contact Garrett Smith 301-903-7440 DOE Employee Concerns Program Environment Worker Health & Safety Facility Safety Nuclear Safety Criticality Safety Quality Assurance Risk ...

  6. WM2014 Conference- Building the Community of Practice for Performance and Risk Assessment in Support of Risk-Informed Environmental Management Decisions

    Broader source: Energy.gov [DOE]

    WM2014 Conference - Building the Community of Practice for Performance and Risk Assessment in Support of Risk-Informed Environmental Management Decisions - 14575

  7. Health, safety, and environmental risks from energy production: A year-long reality check

    SciTech Connect (OSTI)

    Oldenburg, C.M.

    2011-04-01

    Large-scale carbon dioxide capture and storage (CCS) offers the benefit of reducing CO{sub 2} emissions and thereby mitigating climate change risk, but it will also bring its own health, safety, and environmental risks. Curtis M. Oldenburg, Editor-in-Chief, considers these risks in the context of the broader picture of energy production. Over the last year, there have been major acute health, safety, and environmental (HSE) consequences related to accidents involving energy production from every major primary energy source. These are, in chronological order: (i) the Upper Big Branch (coal) Mine disaster, (ii) the Gulf of Mexico Macondo (oil) well blowout, (iii) the San Bruno (natural gas) pipeline leak and explosion, and (iv) the Fukushima (nuclear) reactor radioactivity releases. Briefly, the Upper Big Branch Mine disaster occurred in West Virginia on April 5, 2010, when natural methane in the mine ignited, causing the deaths of 29 miners, the worst coal mine disaster in the USA since 1970. Fifteen days later, the Macondo oil well in the Gulf of Mexico suffered a blowout, with a gas explosion and fire on the floating drilling platform that killed 11 people. The oil and gas continued to flow out of the well at the seafloor until July 15, 2010, spilling a total of approximately 5 million barrels of oil into the sea. On September 9, 2010, a 30-inch (76-cm) buried, steel, natural gas pipeline in San Bruno, California, leaked gas and exploded in a residential neighborhood, killing 8 people in their homes and burning a total of 38 homes. Flames were up to 1000 ft (300 m) high, and the initial explosion itself reportedly measured 1.1 on the Richter scale. Finally, on March 11, 2011, a magnitude 9.0 earthquake off the coast of Japan's main island, Honshu, caused a tsunami that crippled the backup power and associated cooling systems for six reactor cores and their spent fuel storage tanks at the Fukushima nuclear power plant. At time of writing, workers trying to bring

  8. Hazardous Waste/Mixed Waste Treatment Building Safety Information Document (SID)

    SciTech Connect (OSTI)

    Fatell, L.B.; Woolsey, G.B.

    1993-04-15

    This Safety Information Document (SID) provides a description and analysis of operations for the Hazardous Waste/Mixed Waste Disposal Facility Treatment Building (the Treatment Building). The Treatment Building has been classified as a moderate hazard facility, and the level of analysis performed and the methodology used are based on that classification. Preliminary design of the Treatment Building has identified the need for two separate buildings for waste treatment processes. The term Treatment Building applies to all these facilities. The evaluation of safety for the Treatment Building is accomplished in part by the identification of hazards associated with the facility and the analysis of the facility`s response to postulated events involving those hazards. The events are analyzed in terms of the facility features that minimize the causes of such events, the quantitative determination of the consequences, and the ability of the facility to cope with each event should it occur. The SID presents the methodology, assumptions, and results of the systematic evaluation of hazards associated with operation of the Treatment Building. The SID also addresses the spectrum of postulated credible events, involving those hazards, that could occur. Facility features important to safety are identified and discussed in the SID. The SID identifies hazards and reports the analysis of the spectrum of credible postulated events that can result in the following consequences: Personnel exposure to radiation; Radioactive material release to the environment; Personnel exposure to hazardous chemicals; Hazardous chemical release to the environment; Events leading to an onsite/offsite fatality; and Significant damage to government property. The SID addresses the consequences to the onsite and offsite populations resulting from postulated credible events and the safety features in place to control and mitigate the consequences.

  9. Preliminary characterization of risks in the nuclear waste management system based on information in the literature

    SciTech Connect (OSTI)

    Daling, P.M.; Rhoads, R.E.; Van Luick, A.E.; Fecht, B.A.; Nilson, S.A.; Sevigny, N.L.; Armstrong, G.R.; Hill, D.H.; Rowe, M.; Stern, E.

    1992-01-01

    This document presents preliminary information on the radiological and nonradiological risks in the nuclear waste management system. The objective of the study was to (1) review the literature containing information on risks in the nuclear waste management system and (2) use this information to develop preliminary estimates of the potential magnitude of these risks. Information was collected on a broad range of risk categories to assist the US Department of Energy (DOE) in communicating information about the risks in the waste management systems. The study examined all of the portions of the nuclear waste management system currently expected to be developed by the DOE. The scope of this document includes the potential repository, the integral MRS facility, and the transportation system that supports the potential repository and the MRS facility. Relevant literature was reviewed for several potential repository sites and geologic media. A wide range of ``risk categories`` are addressed in this report: (1) public and occupational risks from accidents that could release radiological materials, (2) public and occupational radiation exposure resulting from routine operations, (3) public and occupational risks from accidents involving hazards other than radioactive materials, and (4) public and occupational risks from exposure to nonradioactive hazardous materials during routine operations. The report is intended to provide a broad spectrum of risk-related information about the waste management system. This information is intended to be helpful for planning future studies.

  10. Waste isolation safety assessment program. Task 4. Third contractor information meeting

    SciTech Connect (OSTI)

    Not Available

    1980-06-01

    The Contractor Information Meeting (October 14 to 17, 1979) was part of the FY-1979 effort of Task 4 of the Waste Isolation Safety Assessment Program (WISAP): Sorption/Desorption Analysis. The objectives of this task are to: evaluate sorption/desorption measurement methods and develop a standardized measurement procedure; produce a generic data bank of nuclide-geologic interactions using a wide variety of geologic media and groundwaters; perform statistical analysis and synthesis of these data; perform validation studies to compare short-term laboratory studies to long-term in situ behavior; develop a fundamental understanding of sorption/desorption processes; produce x-ray and gamma-emitting isotopes suitable for the study of actinides at tracer concentrations; disseminate resulting information to the international technical community; and provide input data support for repository safety assessment. Conference participants included those subcontracted to WISAP Task 4, representatives and independent subcontractors to the Office of Nuclear Waste Isolation, representatives from other waste disposal programs, and experts in the area of waste/geologic media interaction. Since the meeting, WISAP has been divided into two programs: Assessment of Effectiveness of Geologic Isolation Systems (AEGIS) (modeling efforts) and Waste/Rock Interactions Technology (WRIT) (experimental work). The WRIT program encompasses the work conducted under Task 4. This report contains the information presented at the Task 4, Third Contractor Information Meeting. Technical Reports from the subcontractors, as well as Pacific Northwest Laboratory (PNL), are provided along with transcripts of the question-and-answer sessions. The agenda and abstracts of the presentations are also included. Appendix A is a list of the participants. Appendix B gives an overview of the WRIT program and details the WRIT work breakdown structure for 1980.

  11. Reactor safety study. An assessment of accident risks in U. S...

    Office of Scientific and Technical Information (OSTI)

    An assessment of accident risks in U. S. commercial nuclear power plants. Executive ... An assessment of accident risks in U. S. commercial nuclear power plants. Executive ...

  12. Guidance on risk analysis and safety implications of a large liquefied natural gas (LNG) spill over water.

    SciTech Connect (OSTI)

    Wellman, Gerald William; Melof, Brian Matthew; Luketa-Hanlin, Anay Josephine; Hightower, Marion Michael; Covan, John Morgan; Gritzo, Louis Alan; Irwin, Michael James; Kaneshige, Michael Jiro; Morrow, Charles W.

    2004-12-01

    While recognized standards exist for the systematic safety analysis of potential spills or releases from LNG (Liquefied Natural Gas) storage terminals and facilities on land, no equivalent set of standards or guidance exists for the evaluation of the safety or consequences from LNG spills over water. Heightened security awareness and energy surety issues have increased industry's and the public's attention to these activities. The report reviews several existing studies of LNG spills with respect to their assumptions, inputs, models, and experimental data. Based on this review and further analysis, the report provides guidance on the appropriateness of models, assumptions, and risk management to address public safety and property relative to a potential LNG spill over water.

  13. Light Water Reactor Sustainability Program Technical Basis Guide Describing How to Perform Safety Margin Configuration Risk Management

    SciTech Connect (OSTI)

    Curtis Smith; James Knudsen; Bentley Harwood

    2013-08-01

    The INL has carried out a demonstration of the RISMC approach for the purpose of configuration risk management. We have shown how improved accuracy and realism can be achieved by simulating changes in risk as a function of different configurations in order to determine safety margins as the plant is modified. We described the various technical issues that play a role in these configuration-based calculations with the intent that future applications can take advantage of the analysis benefits while avoiding some of the technical pitfalls that are found for these types of calculations. Specific recommendations have been provided on a variety of topics aimed at improving the safety margin analysis and strengthening the technical basis behind the analysis process.

  14. Summary of tank information relating salt well pumping to flammable gas safety issues

    SciTech Connect (OSTI)

    Caley, S.M.; Mahoney, L.A.; Gauglitz, P.A.

    1996-09-01

    The Hanford Site has 149 single-shell tanks (SSTs) containing radioactive wastes that are complex mixes of radioactive and chemical products. Active use of these SSTs was phased out completely by November 1980, and the first step toward final disposal of the waste in the SSTs is interim stabilization, which involves removing essentially all of the drainable liquid from the tank. Stabilization can be achieved administratively, by jet pumping to remove drainable interstitial liquid, or by supernatant pumping. To date, 116 tanks have been declared interim stabilized; 44 SSTs have had drainable liquid removed by salt well jet pumping. Of the 149 SSTs, 19 are on the Flammable Gas Watch List (FGWL) because the waste in these tanks is known or suspected, in all but one case, to generate and retain mixtures of flammable gases, including; hydrogen, nitrous oxide, and ammonia. Salt well pumping to remove the drainable interstitial liquid from these SSTs is expected to cause the release of much of the retained gas, posing a number of safety concerns. The scope of this work is to collect and summarize information, primarily tank data and observations, that relate salt well pumping to flammable gas safety issues. While the waste within FGWL SSTs is suspected offering flammable gases, the effect of salt well pumping on the waste behavior is not well understood. This study is being conducted for the Westinghouse Hanford Company as part of the Flammable Gas Project at the Pacific Northwest National Laboratory (PNNL). Understanding the historical tank behavior during and following salt well pumping will help to resolve the associated safety issues.

  15. Nuclear Energy Research Initiative. Risk Informed Assessment of Regulatory and Design Requirements for Future Nuclear Power Plants. Annual Report

    SciTech Connect (OSTI)

    Ritterbusch, S.E.

    2000-08-01

    The overall goal of this research project is to support innovation in new nuclear power plant designs. This project is examining the implications, for future reactors and future safety regulation, of utilizing a new risk-informed regulatory system as a replacement for the current system. This innovation will be made possible through development of a scientific, highly risk-informed approach for the design and regulation of nuclear power plants. This approach will include the development and.lor confirmation of corresponding regulatory requirements and industry standards. The major impediment to long term competitiveness of new nuclear plants in the U.S. is the capital cost component--which may need to be reduced on the order of 35% to 40% for Advanced Light Water Reactors (ALWRs) such as System 80+ and Advanced Boiling Water Reactor (ABWR). The required cost reduction for an ALWR such as AP600 or AP1000 would be expected to be less. Such reductions in capital cost will require a fundamental reevaluation of the industry standards and regulatory bases under which nuclear plants are designed and licensed. Fortunately, there is now an increasing awareness that many of the existing regulatory requirements and industry standards are not significantly contributing to safety and reliability and, therefore, are unnecessarily adding to nuclear plant costs. Not only does this degrade the economic competitiveness of nuclear energy, it results in unnecessary costs to the American electricity consumer. While addressing these concerns, this research project will be coordinated with current efforts of industry and NRC to develop risk-informed, performance-based regulations that affect the operation of the existing nuclear plants; however, this project will go farther by focusing on the design of new plants.

  16. REVIEW OF PROPOSED METHODOLOGY FOR A RISK- INFORMED RELAXATION TO ASME SECTION XI APPENDIX G

    SciTech Connect (OSTI)

    Dickson, Terry L; Kirk, Mark

    2010-01-01

    The current regulations, as set forth by the United States Nuclear Regulatory Commission (NRC), to insure that light-water nuclear reactor pressure vessels (RPVs) maintain their structural integrity when subjected to planned normal reactor startup (heat-up) and shut-down (cool-down) transients are specified in Appendix G to 10 CFR Part 50, which incorporates by reference Appendix G to Section XI of the American Society of Mechanical Engineers (ASME) Code. The technical basis for these regulations are now recognized by the technical community as being conservative and some plants are finding it increasingly difficult to comply with the current regulations. Consequently, the nuclear industry has developed, and submitted to the ASME Code for approval, an alternative risk-informed methodology that reduces the conservatism and is consistent with the methods previously used to develop a risk-informed revision to the regulations for accidental transients such as pressurized thermal shock (PTS). The objective of the alternative methodology is to provide a relaxation to the current regulations which will provide more operational flexibility, particularly for reactor pressure vessels with relatively high irradiation levels and radiation sensitive materials, while continuing to provide reasonable assurance of adequate protection to public health and safety. The NRC and its contractor at Oak Ridge National Laboratory (ORNL) have recently performed an independent review of the industry proposed methodology. The NRC / ORNL review consisted of performing probabilistic fracture mechanics (PFM) analyses for a matrix of cool-down and heat-up rates, permutated over various reactor geometries and characteristics, each at multiple levels of embrittlement, including 60 effective full power years (EFPY) and beyond, for various postulated flaw characterizations. The objective of this review is to quantify the risk of a reactor vessel experiencing non-ductile fracture, and possible

  17. Assessing the Changes In Safety Risk Arising From the Use of Natural Gas Infrastructure For Mixtures of Hydrogen and Natural Gas

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    6/02/2005 Assessing the changes in safety risk arising from the use of natural gas infrastructures for mixtures of hydrogen and natural gas NATURALHY G. Hankinson Loughborough University, UK 2 16/02/2005 Naturalhy project safety work package NATURALHY 3 16/02/2005 Outline NATURALHY To identify and quantify the major factors influencing safety in the transportation, distribution, and delivery of hydrogen/natural gas mixtures by means of existing natural gas infrastructures. 4 16/02/2005 Purpose

  18. Risk Informed Design and Analysis Criteria for Nuclear Structures

    SciTech Connect (OSTI)

    Salmon, Michael W.

    2015-06-17

    Target performance can be achieved by defining design basis ground motion from results of a probabilistic seismic hazards assessment, and introducing known levels of conservatism in the design above the DBE. ASCE 4, 43, DOE-STD-1020 defined the DBE at 4x10-4 and introduce only slight levels of conservatism in response. ASCE 4, 43, DOE-STD-1020 assume code capacities shoot for about 98% NEP. There is a need to have a uniform target (98% NEP) for code developers (ACI, AISC, etc.) to aim for. In considering strengthening options, one must also consider cost/risk reduction achieved.

  19. Proposed Risk-Informed Seismic Hazard Periodic Reevaluation Methodology for Complying with DOE Order 420.1C

    SciTech Connect (OSTI)

    Kammerer, Annie

    2015-10-01

    Department of Energy (DOE) nuclear facilities must comply with DOE Order 420.1C Facility Safety, which requires that all such facilities review their natural phenomena hazards (NPH) assessments no less frequently than every ten years. The Order points the reader to Standard DOE-STD-1020-2012. In addition to providing a discussion of the applicable evaluation criteria, the Standard references other documents, including ANSI/ANS-2.29-2008 and NUREG-2117. These documents provide supporting criteria and approaches for evaluating the need to update an existing probabilistic seismic hazard analysis (PSHA). All of the documents are consistent at a high level regarding the general conceptual criteria that should be considered. However, none of the documents provides step-by-step detailed guidance on the required or recommended approach for evaluating the significance of new information and determining whether or not an existing PSHA should be updated. Further, all of the conceptual approaches and criteria given in these documents deal with changes that may have occurred in the knowledge base that might impact the inputs to the PSHA, the calculated hazard itself, or the technical basis for the hazard inputs. Given that the DOE Order is aimed at achieving and assuring the safety of nuclear facilities—which is a function not only of the level of the seismic hazard but also the capacity of the facility to withstand vibratory ground motions—the inclusion of risk information in the evaluation process would appear to be both prudent and in line with the objectives of the Order. The purpose of this white paper is to describe a risk-informed methodology for evaluating the need for an update of an existing PSHA consistent with the DOE Order. While the development of the proposed methodology was undertaken as a result of assessments for specific SDC-3 facilities at Idaho National Laboratory (INL), and it is expected that the application at INL will provide a demonstration of the

  20. Risk Informed Assessment of Regulatory and Design Requirements for Future Nuclear Power Plants - Final Technical Report

    SciTech Connect (OSTI)

    Ritterbusch, Stanley; Golay, Michael; Duran, Felicia; Galyean, William; Gupta, Abhinav; Dimitrijevic, Vesna; Malsch, Marty

    2003-01-29

    OAK B188 Summary of methods proposed for risk informing the design and regulation of future nuclear power plants. All elements of the historical design and regulation process are preserved, but the methods proposed for new plants use probabilistic risk assessment methods as the primary decision making tool.

  1. Risk-Informed LNG/CNG Maintenance Facility Codes and Standards

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    NO. 2011-XXXXP Risk-Informed LNG/CNG Maintenance Facility Codes and Standards Project sponsored by the Clean Vehicle Education Foundation Chris LaFleur, Myra Blaylock, Rad Bozinoski, Amanda Dodd, Ethan Hecht, Doug Horne, Alice Muña Sandia National Laboratories SAND NO. 2015-7361PE Project Motivation  Improve codes and standards for gaseous fuel vehicle maintenance facility design and operation to reflect technology advancements  Develop Risk-Informed guidelines for modification and

  2. Qualitative Risk Assessment For An LNG Refueling Station And Review Of Relevant Safety Issues, Revision 2

    SciTech Connect (OSTI)

    Siu, Nathan; Herring, J Stephen; Cadwallader, Lee; Reece, Wendy; Byers, James

    2014-06-25

    This report is a qualitative assessment of the public and worker risk involved with the operation of liquefied natural gas vehicle refueling facility.

  3. Report on the handling of safety information concerning flammable gases and ferrocyanide at the Hanford waste tanks

    SciTech Connect (OSTI)

    Not Available

    1990-07-01

    This report discusses concerns safety issues, and management at Hanford Tank Farm. Concerns center on the issue of flammable gas generation which could ignite, and on possible exothermic reactions of ferrocyanide compounds which were added to single shell tanks in the 1950's. It is believed that information concerning these issues has been mis-handled and the problems poorly managed. (CBS)

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

    SciTech Connect (OSTI)

    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.

  5. GIZ Sourcebook Module 5b: Urban Road Safety | Open Energy Information

    Open Energy Info (EERE)

    with the consequential social, economic, and health burdens imposing heavy constraints on sustainable development. This module focuses on addressing local road safety, creating a...

  6. FTCP Site Specific Information – Office of Environment, Health, Safety & Security

    Broader source: Energy.gov [DOE]

    Site Specific Information including Contact Information, and Annual Workforce Analysis & Staffing Plan Reports.

  7. Use of information resources by the state of Tennessee in risk assessment applications

    SciTech Connect (OSTI)

    Bashor, B.S.

    1990-12-31

    The major resources used by the Bureau of Environment, and Environmental Epidemiology (EEP) for risk assessment are: the Integrated Risk Information System (IRIS), Health and Environmental Effects Summary Table (HEAST), Agency for Toxic Substances and disease Registry (ATSDR) Toxicological Profiles, databases at the National Library of Medicine (NLM), World Health Organization (WHO) ENvironmental Criteria, and documents that the Environmental Protection Agency (EPA) has published on Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) risk assessment activities. The Risk Assessment Review has been helpful in providing information about availability of new documents or information. No systematic method has been made available to us to locate information resources. IRIS User`s Support has been helpful in making appropriate and timely referrals. Most other EPA resources were located by serendipity and persistence. The CERCLA methodology for risk assessments is being used in environmental programs, and at present, one person is responsible for all risk assessment activities in the department, but plans are underway to train one or two people from each program area. 2 figs.

  8. DOE Standard on Development and Use of Probabilistic Risk Assessment in DOE

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Nuclear Safety Applications (draft), December 2010 | Department of Energy Standard on Development and Use of Probabilistic Risk Assessment in DOE Nuclear Safety Applications (draft), December 2010 DOE Standard on Development and Use of Probabilistic Risk Assessment in DOE Nuclear Safety Applications (draft), December 2010 There have been significant developments with regard to the risk assessment and risk informed decision making, as it applies to nuclear and other safety areas, since the

  9. Access and use of information resources in assessing health risks from chemical exposure: Proceedings

    SciTech Connect (OSTI)

    Not Available

    1990-12-31

    Health risk assessment is based on access to comprehensive information about potentially hazardous agents in question. Relevant information is scattered throughout the literature, and often is not readily accessible. To be useful in assessment efforts, emerging scientific findings, risk assess parameters, and associated data must be compiled and evaluated systemically. The US Environmental Protection Agency (EPA) and Oak Ridge National Laboratory (ORNL) are among the federal agencies heavily involved in this effort. This symposium was a direct response by EPA and ORNL to the expressed needs of individuals involved in assessing risks from chemical exposure. In an effort to examine the state of the risk assessment process, the availability of toxicological information, and the future development and transfer of this information, the symposium provided an excellent cadre of speakers and participants from state and federal agencies, academia and research laboratories to address these topics. This stimulating and productive gathering discussed concerns associated with (1) environmental contamination by chemicals; (2) laws regulating chemicals; (3) information needs and resources; (4) applications; (5) challenges and priorities; and (6)future issues. Individual reports are processed separately for the data bases.

  10. Request for Investigation or Inspection of Safety or Classified Information Security Violations

    Broader source: Energy.gov [DOE]

    Form allows for any DOE contractor employee or employee representative to submit a request to the Department of Energy’s Office of Enforcement, within the Office of Health, Safety, and Security, to initiate an enforcement investigation or inspection into a potential violation of DOE regulatory requirements.

  11. Strategic Safety Goals | Department of Energy

    Broader source: Energy.gov (indexed) [DOE]

    Safety Goals More Documents & Publications Strategic Safety Goals Occupational Safety Performance Trends Development of the Nuclear Safety Information Dashboard - September 2012

  12. Hydrogen Safety Panel

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    or otherwise restricted information. Project ID: scs07weiner PNNL-SA-65397 2 IEA HIA Task 19 Working Group Hydrogen Safety Training Props Hydrogen Safety Panel Incident...

  13. Nuclear criticality safety guide

    SciTech Connect (OSTI)

    Pruvost, N.L.; Paxton, H.C.

    1996-09-01

    This technical reference document cites information related to nuclear criticality safety principles, experience, and practice. The document also provides general guidance for criticality safety personnel and regulators.

  14. Material Safety Data Sheets

    Broader source: Energy.gov [DOE]

    Material Safety Data Sheets (MSDSs) provide workers and emergency personnel with ways for handling and working with a hazardous substance and other health and safety information.

  15. The Radiation Safety Information Computational Center - A Resource for Training the Next Generation Engineer

    SciTech Connect (OSTI)

    Kirk, Bernadette Lugue

    2009-01-01

    RSICC came into existence in 1962 largely as a result of the report made by Alvin Weinbergand others to the Executive Office of the President of the United States on the 'information explosion' and the role of the technical community and government in its preservation and use. This report became known as the Weinberg Report. Its theme was 'Information is an integral part of science; without proper handling of information, science cannot function.' The report recommended the establishment of specialized information centers -'to digest and evaluate -to make condensations and reviews -thus saving the time of the individual research scientist and engineer.'

  16. How information resources are used by federal agencies in risk assessment application: Rapporteur summary

    SciTech Connect (OSTI)

    Fenner-Crisp, P.

    1990-12-31

    The application of information available for risk assessment from the federal perspective is described. Different federal agencies conduct varying degrees of hazard evaluation, and some also generate empirical data. The role of the Agency for Toxic Substances and Disease Registry in hazard assessments of potential public health impacts of Superfund sites includes identification of the 275 most significant substances. ATSDR is responsible for preparing toxicological profiles. ATSDR also identifies data gaps and needs critical to adequately assessing human health impacts.

  17. Fuel-cycle facilities: preliminary safety and environmental information document. Volume VII

    SciTech Connect (OSTI)

    Not Available

    1980-01-01

    Information is presented concerning the mining and milling of uranium and thorium; uranium hexafluoride conversion; enrichment; fuel fabrication; reprocessing; storage options; waste disposal options; transportation; heavy-water-production facilities; and international fuel service centers.

  18. Topographical Risk Assessment

    Energy Science and Technology Software Center (OSTI)

    2002-09-24

    TRA was developed as a computer tool for the DOE Office of River Protection (ORP) that will provides the capability to visualize and rapidly understand information about the risks associated with the River protection Project (RPP). Previously, technical and programmatic risk management within ORP had relied heavily on risk lists and other techniques that presented risk information but did not place it in perspective of the overall project. This made it difficult for ORP seniormore » management to understand the risk information presented, prioritize their activities, and provide direction to ORP staff and contractors about how to manage specific risk events. The TRA visualization tool, provides the appropriate context and perspective that allows senior management to effectively manage risks. Basically, the TRA overlays information about risks associated with specific activities and their magnitudes on top of the project baseline schedule. this provides senior management with information about the magnitudes of specific risk events as well as their timing, and allows them to focus their attention and resources on the risks that merit attention and possible further action. The TRA tool can also be used to display other types of information associated with scheduled activities, such as cost to date, technical performance, schedule performance, etc. Additionally, the base of the 3-dimensional representation can be changed to other types of graphics, such as maps, process flow diagrams, etc., which allows the display of other types of informatio, such as hazards, health and safety risks, and system availability.« less

  19. AUDIT REPORT Follow-up on Nuclear Safety: Safety Basis and Quality...

    Broader source: Energy.gov (indexed) [DOE]

    Nuclear Safety: Safety Basis and Quality Assurance at the Los Alamos National Laboratory ... INFORMATION: Audit Report: "Follow-up on Nuclear Safety: Safety Basis and Quality ...

  20. High-temperature gas-cooled reactors: preliminary safety and environmental information document. Volume IV

    SciTech Connect (OSTI)

    Not Available

    1980-01-01

    Information is presented concerning medium-enriched uranium/thorium once-through fuel cycle; medium-enrichment uranium-233/thorium recycle fuel; high-enrichment uranium-235/thorium recycle (spiked) fuel cycle; high-enrichment uranium-233/thorium recycle (spiked) fuel cycle; and gas-turbine high-temperature gas-cooled reactor.

  1. Update to Risk-Informed Pressurized Water Reactor Vessel 10 to 20 Year Inspection Interval Extension

    SciTech Connect (OSTI)

    Palm, Nathan A.; Bishop, Bruce A.; Boggess, Cheryl L.

    2006-07-01

    The Pressurized Water Reactor Owners Group (formerly the Westinghouse Owners Group (WOG)) methodology for extending the inservice inspection interval for welds in pressurized water reactor (PWR) reactor pressure vessel (RPV) was introduced as ICONE12-49429. The paper presented a risk informed basis for extending the interval between inspections from the current interval of 10 years to 20 years. In the paper presented at ICONE-12, results of pilot studies on typical Westinghouse and Combustion Engineering Nuclear Steam Supply System (NSSS) designs of PWR vessels showed that the change in risk associated with the proposed inspection interval extension was within the guidelines specified in the United States Nuclear Regulatory Commission (NRC) Regulatory Guide 1.174 for an acceptably small change in risk. Since the methodology was originally presented, the evaluation has been updated to incorporate the latest changes in the NRC Pressurized Thermal Shock (PTS) Risk Reevaluation Program and expanded to include the Babcock and Wilcox NSSS RPV design. The results of these evaluations demonstrate that the proposed RPV inspection interval extension remains a viable option for the industry. The updates to the methodology and input, pilot plant evaluations, results, process for demonstrating applicability of the pilot plant analysis to non-pilot lead plants and lessons learned from the evaluations performed are summarized in this paper. (authors)

  2. PAT-1 safety analysis report addendum author responses to request for additional information.

    SciTech Connect (OSTI)

    Weiner, Ruth F.; Schmale, David T.; Kalan, Robert J.; Akin, Lili A.; Miller, David Russell; Knorovsky, Gerald Albert; Yoshimura, Richard Hiroyuki; Lopez, Carlos; Harding, David Cameron; Jones, Perry L.; Morrow, Charles W.

    2010-09-01

    The Plutonium Air Transportable Package, Model PAT-1, is certified under Title 10, Code of Federal Regulations Part 71 by the U.S. Nuclear Regulatory Commission (NRC) per Certificate of Compliance (CoC) USA/0361B(U)F-96 (currently Revision 9). The National Nuclear Security Administration (NNSA) submitted SAND Report SAND2009-5822 to NRC that documented the incorporation of plutonium (Pu) metal as a new payload for the PAT-1 package. NRC responded with a Request for Additional Information (RAI), identifying information needed in connection with its review of the application. The purpose of this SAND report is to provide the authors responses to each RAI. SAND Report SAND2010-6106 containing the proposed changes to the Addendum is provided separately.

  3. Light-water reactors: preliminary safety and environmental information document. Volume I

    SciTech Connect (OSTI)

    Not Available

    1980-01-01

    Information is presented concerning the reference PWR reactor system; once-through, low-enrichment uranium-235 fuel, 30 MWD per kilogram (PWR LEU(5)-OT); once-through, low-enrichment, high-burnup uranium fuel (PWR LEU(5)-Mod OT); self-generated plutonium spiked recycle (PWR LEU(5)-Pu-Spiked Recycle); denatured uranium-233/thorium cycle (PWR DU(3)-Th Recycle DU(3)); and plutonium/thorium cycle (Pu/ThO/sub 2/ Burner).

  4. Transactions of the twenty-third water reactor safety information meeting to be held at Bethesda Marriott Hotel, Bethesda, Maryland, October 23--25, 1995

    SciTech Connect (OSTI)

    Monteleone, S.

    1995-09-01

    This report contains summaries of papers on reactor safety research to be presented at the 23rd Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23--25, 1995. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory, Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting and are given in the order of their presentation in each session.

  5. Overview of HyRAM (Hydrogen Risk Assessment Models) Software for Science-Based Safety, Codes, and Standards

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    HyRAM Software for Science-Based Safety, Codes, and Standards U.S. Department of Energy Fuel Cell Technologies Office April 26, 2016 Presenter: Katrina M. Groth - Sandia National Laboratories DOE Host: Will James - Program Manager: Hydrogen Safety, Codes, and Standards, Fuel Cell Technologies Office 2 | Fuel Cell Technologies Office eere.energy.gov Question and Answer * Please type your questions into the question box 2 Overview of HyRAM Software for Science- Based Safety, Codes, and Standards

  6. How information resources are used by state agencies in risk assessment applications - Illinois

    SciTech Connect (OSTI)

    Olson, C.S.

    1990-12-31

    The Environmental Protection Agency of the State of Illinois (Illinois EPA) has programs in water, air, and land pollution and water supplies paralleling those of the US Environmental Protection Agency (EPA). The organization is part of a tripartite arrangement in which the Pollution Control Board is the judicial arm, the Department of Energy and Natural Resources is the research arm, and the Illinois EPA is the enforcement arm. Other state agencies are also concerned with various aspects of the environment and may do risk assessments for chemicals. Although there are various risk assessment activities, both formal and informal, in our agency and in others, this paper will discuss only recent initiatives in water quality criteria.

  7. Webinar April 26: Overview of HyRAM (Hydrogen Risk Assessment Models) Software for Science-Based Safety, Codes, and Standards

    Broader source: Energy.gov [DOE]

    The Energy Department will present a live webinar titled "Overview of HyRAM (Hydrogen Risk Assessment Models) Software for Science-Based Safety, Codes, and Standards" on Tuesday, April 26, from 12 to 1 p.m. Eastern Daylight Time. This webinar provides an introduction to the new HyRAM research software developed by Sandia National Laboratories and supported by the Fuel Cell Technologies Office.

  8. 2016 Strategic Plan Chief of Nuclear Safety

    Office of Energy Efficiency and Renewable Energy (EERE)

    The purpose of this strategic plan is to communicate our commitment to the safety of the Office of Environmental Management (EM) nuclear facilities. It provides an integrated framework for the mission, functions, vision, and strategic direction for the Chief of Nuclear Safety (CNS) and Central Technical Authority (CTA). It was developed, in part, using the outcome of a risk-informed analysis that helps identify the facilities and activities where CNS will focus its attention during the upcoming year.

  9. CRAD, Facility Safety - Unreviewed Safety Question Requirements |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Department of Energy Facility Safety - Unreviewed Safety Question Requirements CRAD, Facility Safety - Unreviewed Safety Question Requirements A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) that can be used for assessment of a contractor's Unreviewed Safety Question (USQ) process.. CRADs provide a recommended approach and the types of information to

  10. Risk-Informed Monitoring, Verification and Accounting (RI-MVA). An NRAP White Paper Documenting Methods and a Demonstration Model for Risk-Informed MVA System Design and Operations in Geologic Carbon Sequestration

    SciTech Connect (OSTI)

    Unwin, Stephen D.; Sadovsky, Artyom; Sullivan, E. C.; Anderson, Richard M.

    2011-09-30

    This white paper accompanies a demonstration model that implements methods for the risk-informed design of monitoring, verification and accounting (RI-MVA) systems in geologic carbon sequestration projects. The intent is that this model will ultimately be integrated with, or interfaced with, the National Risk Assessment Partnership (NRAP) integrated assessment model (IAM). The RI-MVA methods described here apply optimization techniques in the analytical environment of NRAP risk profiles to allow systematic identification and comparison of the risk and cost attributes of MVA design options.

  11. Comparison of Integrated Safety Analysis (ISA) and Probabilistic Risk Assessment (PRA) for Fuel Cycle Facilities, 2/17/11

    Broader source: Energy.gov [DOE]

    During the 580th meeting of the Advisory Committee on Reactor Safeguards (ACRS), February10-12, 2011, we reviewed the staff’s white paper, “A Comparison of Integrated Safety Analysisand...

  12. Health and Safety Laws | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Health and Safety Laws Health and Safety Laws Health and safety laws require working conditions that do not pose a risk of serious harm: Occupational Safety and Health Act of 1970 ...

  13. Investing in International Information Exchange Activities to Improve the Safety, Cost Effectiveness and Schedule of Cleanup - 13281

    SciTech Connect (OSTI)

    Seed, Ian; James, Paula; Mathieson, John; Judd, Laurie; Elmetti-Ramirez, Rosa; Han, Ana

    2013-07-01

    With decreasing budgets and increasing pressure on completing cleanup missions as quickly, safely and cost-effectively as possible, there is significant benefit to be gained from collaboration and joint efforts between organizations facing similar issues. With this in mind, the US Department of Energy (DOE) and the UK Nuclear Decommissioning Authority (NDA) have formally agreed to share information on lessons learned on the development and application of new technologies and approaches to improve the safety, cost effectiveness and schedule of the cleanup legacy wastes. To facilitate information exchange a range of tools and methodologies were established. These included tacit knowledge exchange through facilitated meetings, conference calls and Site visits as well as explicit knowledge exchange through document sharing and newsletters. A DOE web-based portal has been established to capture these exchanges and add to them via discussion boards. The information exchange is operating at the Government-to-Government strategic level as well as at the Site Contractor level to address both technical and managerial topic areas. This effort has resulted in opening a dialogue and building working relationships. In some areas joint programs of work have been initiated thus saving resource and enabling the parties to leverage off one another activities. The potential benefits of high quality information exchange are significant, ranging from cost avoidance through identification of an approach to a problem that has been proven elsewhere to cost sharing and joint development of a new technology to address a common problem. The benefits in outcomes significantly outweigh the costs of the process. The applicability of the tools and methods along with the lessons learned regarding some key issues is of use to any organization that wants to improve value for money. In the waste management marketplace, there are a multitude of challenges being addressed by multiple organizations and

  14. Modular High Temperature Gas-Cooled Reactor Safety Basis and Approach

    SciTech Connect (OSTI)

    David Petti; Jim Kinsey; Dave Alberstein

    2014-01-01

    Various international efforts are underway to assess the safety of advanced nuclear reactor designs. For example, the International Atomic Energy Agency has recently held its first Consultancy Meeting on a new cooperative research program on high temperature gas-cooled reactor (HTGR) safety. Furthermore, the Generation IV International Forum Reactor Safety Working Group has recently developed a methodology, called the Integrated Safety Assessment Methodology, for use in Generation IV advanced reactor technology development, design, and design review. A risk and safety assessment white paper is under development with respect to the Very High Temperature Reactor to pilot the Integrated Safety Assessment Methodology and to demonstrate its validity and feasibility. To support such efforts, this information paper on the modular HTGR safety basis and approach has been prepared. The paper provides a summary level introduction to HTGR history, public safety objectives, inherent and passive safety features, radionuclide release barriers, functional safety approach, and risk-informed safety approach. The information in this paper is intended to further the understanding of the modular HTGR safety approach. The paper gives those involved in the assessment of advanced reactor designs an opportunity to assess an advanced design that has already received extensive review by regulatory authorities and to judge the utility of recently proposed new methods for advanced reactor safety assessment such as the Integrated Safety Assessment Methodology.

  15. Ladder Safety Information Sheet

    Broader source: Energy.gov [DOE]

    Falls are the number one cause of workplace fatalities in the construction industry. Ladder fall injury facts state that 43 percent of all fatal falls in the last decade have involved ladders. Ladder fall prevention measures is necessary in order to prevent further falls.

  16. Winter Safety Information & Tips

    Broader source: Energy.gov (indexed) [DOE]

    ... are in proper working order. - Keep spare window washer fluid in the car and make ... person indoors and warm the frostbitten parts of their body quickly in warm (not hot) ...

  17. Safety Staff Contact Information

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    spambots. You need JavaScript enabled to view it (Radiation Physicist) 6212 5597 75-103 80A-102 Ergo Advocates This e-mail address is being protected from spambots. You need...

  18. Twenty-second water reactor safety information meeting. Volume 2: Severe accident research, thermal hydraulic research for advanced passive LWRs, high-burnup fuel behavior

    SciTech Connect (OSTI)

    Monteleone, S.

    1995-04-01

    This three-volume report contains papers presented at the Twenty-Second Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 24-26, 1994. 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 Finland, France, Italy, Japan, Russia, and United Kingdom. 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.

  19. Proceedings of the US Nuclear Regulatory Commission fifteenth water reactor safety information meeting: Volume 6, Decontamination and decommissioning, accident management, TMI-2

    SciTech Connect (OSTI)

    Weiss, A. J.

    1988-02-01

    This six-volume report contains 140 papers out of the 164 that were presented at the Fifteenth Water Reactor Safety Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, during the week of October 26-29, 1987. 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. This report, Volume 6, discusses decontamination and decommissioning, accident management, and the Three Mile Island-2 reactor accident. Thirteen reports have been cataloged separately.

  20. Health and Safety Research Division progress report for the period October 1, 1991--March 31, 1993

    SciTech Connect (OSTI)

    Berven, B.A.

    1993-09-01

    This is a progress report from the Health and Safety Research Division of Oak Ridge National Laboratory. Information is presented in the following sections: Assessment Technology, Biological and Radiation Physics, Chemical Physics, Biomedical and Environmental Information Analysis, Risk Analysis, Center for Risk Management, Associate Laboratories for Excellence in Radiation Technology (ALERT), and Contributions to National and Lead Laboratory Programs and Assignments--Environmental Restoration.

  1. Access and use of information resources in assessing health risks from chemicals in food

    SciTech Connect (OSTI)

    Johnson, W.A.

    1990-12-31

    The Food Safety and Inspection Service (FSIS) is responsible for the wholesomeness, safety, and adulteration-free status of meat and poultry. The agency developed the National Residue Program (NRP) to monitor these products for residue of drugs, pesticides, and environmental contaminants. Today, few chemical residues are detected in meat and poultry because of the success of the NRP. 3 figs.

  2. Electrical safety guidelines

    SciTech Connect (OSTI)

    Not Available

    1993-09-01

    The Electrical Safety Guidelines prescribes the DOE safety standards for DOE field offices or facilities involved in the use of electrical energy. It has been prepared to provide a uniform set of electrical safety standards and guidance for DOE installations in order to affect a reduction or elimination of risks associated with the use of electrical energy. The objectives of these guidelines are to enhance electrical safety awareness and mitigate electrical hazards to employees, the public, and the environment.

  3. Facility Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1996-10-24

    Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation.

  4. Facility Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1995-11-16

    Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation.

  5. DOE's Safety Bulletin No. 2011-01, Events Beyond Design Safety...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    This Safety Alert provides information on a safety concern related to the identification and mitigation of events that may fall outside those analyzed in the documented safety ...

  6. Electrical Safety Occurrences | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    by the Electrical Safety Community for information exchange and continual learning. ... by the Electrical Safety Community for information exchange and continual learning. ...

  7. Framework for Modeling High-Impact, Low-Frequency Power Grid Events to Support Risk-Informed Decisions

    SciTech Connect (OSTI)

    Veeramany, Arun; Unwin, Stephen D.; Coles, Garill A.; Dagle, Jeffery E.; Millard, W. David; Yao, Juan; Glantz, Clifford S.; Gourisetti, Sri Nikhil Gup

    2015-12-03

    Natural and man-made hazardous events resulting in loss of grid infrastructure assets challenge the electric power grid’s security and resilience. However, the planning and allocation of appropriate contingency resources for such events requires an understanding of their likelihood and the extent of their potential impact. Where these events are of low likelihood, a risk-informed perspective on planning can be problematic as there exists an insufficient statistical basis to directly estimate the probabilities and consequences of their occurrence. Since risk-informed decisions rely on such knowledge, a basis for modeling the risk associated with high-impact low frequency events (HILFs) is essential. Insights from such a model can inform where resources are most rationally and effectively expended. The present effort is focused on development of a HILF risk assessment framework. Such a framework is intended to provide the conceptual and overarching technical basis for the development of HILF risk models that can inform decision makers across numerous stakeholder sectors. The North American Electric Reliability Corporation (NERC) 2014 Standard TPL-001-4 considers severe events for transmission reliability planning, but does not address events of such severity that they have the potential to fail a substantial fraction of grid assets over a region, such as geomagnetic disturbances (GMD), extreme seismic events, and coordinated cyber-physical attacks. These are beyond current planning guidelines. As noted, the risks associated with such events cannot be statistically estimated based on historic experience; however, there does exist a stable of risk modeling techniques for rare events that have proven of value across a wide range of engineering application domains. There is an active and growing interest in evaluating the value of risk management techniques in the State transmission planning and emergency response communities, some of this interest in the context of

  8. Reference computations of public dose and cancer risk from airborne releases of plutonium. Nuclear safety technical report

    SciTech Connect (OSTI)

    Peterson, V.L.

    1993-12-23

    This report presents results of computations of doses and the associated health risks of postulated accidental atmospheric releases from the Rocky Flats Plant (RFP) of one gram of weapons-grade plutonium in a form that is respirable. These computations are intended to be reference computations that can be used to evaluate a variety of accident scenarios by scaling the dose and health risk results presented here according to the amount of plutonium postulated to be released, instead of repeating the computations for each scenario. The MACCS2 code has been used as the basis of these computations. The basis and capabilities of MACCS2 are summarized, the parameters used in the evaluations are discussed, and results are presented for the doses and health risks to the public, both the Maximum Offsite Individual (a maximally exposed individual at or beyond the plant boundaries) and the population within 50 miles of RFP. A number of different weather scenarios are evaluated, including constant weather conditions and observed weather for 1990, 1991, and 1992. The isotopic mix of weapons-grade plutonium will change as it ages, the {sup 241}Pu decaying into {sup 241}Am. The {sup 241}Am reaches a peak concentration after about 72 years. The doses to the bone surface, liver, and whole body will increase slightly but the dose to the lungs will decrease slightly. The overall cancer risk will show almost no change over this period. This change in cancer risk is much smaller than the year-to-year variations in cancer risk due to weather. Finally, x/Q values are also presented for other applications, such as for hazardous chemical releases. These include the x/Q values for the MOI, for a collocated worker at 100 meters downwind of an accident site, and the x/Q value integrated over the population out to 50 miles.

  9. Highlights from a Workshop Series: Best Practices for Risk-Informed Remedy Selection, Closure, and Post-Closure Control of Contaminated Sites

    Broader source: Energy.gov [DOE]

    Highlights from a Workshop Series: Best Practices for Risk-Informed Remedy Selection, Closure, and Post-Closure Control of Contaminated Sites

  10. Events Beyond Design Safety Basis Analysis

    Broader source: Energy.gov [DOE]

    This Safety Alert provides information on a safety concern related to the identification and mitigation of events that may fall outside those analyzed in the documented safety analysis. [Safety Bulletin 2011-01

  11. Radiation Safety

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Safety Home MSDS Search MSDS Help Safety Training and Tests Contact Links LSU Campus Safety Glossary Radiation Safety Manual Radiation Safety Test NOTE: All Training and Testing Material is for LSU CAMD Users ONLY! **Please allow two weeks for your badge to be processed.** Regulations and Hierarchy The CAMD Safety Officer reports to two separate individuals regarding safety. These are the Radiation Safety Officer for the University, and the Campus Safety Officer in all other matters. Thus safety

  12. CRAD, Safety Functions Assessment Plan

    Broader source: Energy.gov [DOE]

    Management should be proactive in addressing safety-related issues. Management should have an established system to provide a ranking of safety considerations founded upon risk-based priorities.

  13. Modular HTGR Safety Basis and Approach

    SciTech Connect (OSTI)

    Thomas Hicks

    2011-08-01

    The Next Generation Nuclear Plant (NGNP) will be a licensed commercial high temperature gas-cooled reactor (HTGR) capable of producing electricity and/or high temperature process heat for industrial markets supporting a range of end-user applications. The NGNP Project has adopted the 10 CFR 52 Combined License (COL) process, as recommended in the NGNP Licensing Strategy - A Report to Congress, dated August 2008, as the foundation for the NGNP licensing strategy [DOE/NRC 2008]. Nuclear Regulatory Commission (NRC) licensing of the NGNP plant utilizing this process will demonstrate the efficacy for licensing future HTGRs for commercial industrial applications. This information paper is one in a series of submittals that address key generic issues of the priority licensing topics as part of the process for establishing HTGR regulatory requirements. This information paper provides a summary level introduction to HTGR history, public safety objectives, inherent and passive safety features, radionuclide release barriers, functional safety approach, and risk-informed safety approach. The information in this paper is intended to further the understanding of the modular HTGR safety approach with the NRC staff and public stakeholders. The NGNP project does not expect to receive comments on this information paper because other white papers are addressing key generic issues of the priority licensing topics in greater detail.

  14. Information resources used in health risk assessment by the New Jersey Department of Environmental Protection

    SciTech Connect (OSTI)

    Post, G.B.; Baratta, M.; Wolfson, S.; McGeorge, L.

    1990-12-31

    The New Jersey Department of Environmental Protection`s responsibilities related to health-based risk assessment are described, including its research projects and its development of health based compound specific standards and guidance levels. The resources used by the agency to support health risk assessment work are outlined.

  15. Twenty-First Water Reactor Safety Information Meeting. Volume 3, Primary system integrity; Aging research, products and applications; Structural and seismic engineering; Seismology and geology: Proceedings

    SciTech Connect (OSTI)

    Monteleone, S.

    1994-04-01

    This three-volume report contains 90 papers out of the 102 that were presented at the Twenty-First Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 25-27, 1993. 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, Germany, Japan, Russia, Switzerland, Taiwan, and United Kingdom. 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. Selected papers were indexed separately for inclusion in the Energy Science and Technology Database.

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

    SciTech Connect (OSTI)

    Baxter, D.E.

    1994-10-01

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

  17. Improving the safety of LWR power plants. Final report

    SciTech Connect (OSTI)

    Not Available

    1980-04-01

    This report documents the results of the Study to identify current, potential research issues and efforts for improving the safety of Light Water Reactor (LWR) power plants. This final report describes the work accomplished, the results obtained, the problem areas, and the recommended solutions. Specifically, for each of the issues identified in this report for improving the safety of LWR power plants, a description is provided in detail of the safety significance, the current status (including information sources, status of technical knowledge, problem solution and current activities), and the suggestions for further research and development. Further, the issues are ranked for action into high, medium, and low priority with respect to primarily (a) improved safety (e.g. potential reduction in public risk and occupational exposure), and secondly (b) reduction in safety-related costs (improving or maintaining level of safety with simpler systems or in a more cost-effective manner).

  18. Job Safety

    Office of Environmental Management (EM)

    Job Safety and Health It's the law EMPLOYEES: Must have access to: DOE safety and health publications; The worker safety and health program for their location; This ...

  19. Hydrogen Technologies Safety Guide

    SciTech Connect (OSTI)

    Rivkin, C.; Burgess, R.; Buttner, W.

    2015-01-01

    The purpose of this guide is to provide basic background information on hydrogen technologies. It is intended to provide project developers, code officials, and other interested parties the background information to be able to put hydrogen safety in context. For example, code officials reviewing permit applications for hydrogen projects will get an understanding of the industrial history of hydrogen, basic safety concerns, and safety requirements.

  20. AMERIND Risk Annual Conference and Trade Fair

    Broader source: Energy.gov [DOE]

    Hosted by the AMERIND Risk, this three-day conference includes risk management training, workers' safety, human resources, and more.

  1. Risk Assessment Technical Expert Working Group (RWG)Conference Call Minutes, May 6, 2010

    Broader source: Energy.gov [DOE]

    Risk Assessment Information Notice (IN): HSS provided the draft IN to safety basis experts fromSNL, Y-12 and PNNL for their review and comment. Their comments were addressed and the IN isback into...

  2. September 10th Webinar for the Energy Storage Safety Working...

    Energy Savers [EERE]

    0th Webinar for the Energy Storage Safety Working Group on Safety Validation and Risk Assessment R&D September 10th Webinar for the Energy Storage Safety Working Group on Safety ...

  3. Building America Case Study: Combustion Safety Simplified Test...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Combustion Safety Simplified Test Protocol Chicago, Illinois, and Minneapolis, Minnesota PROJECT INFORMATION Project Name: Combustion Safety Simplified Test Protocol Location: ...

  4. Summary of the contractor information exchange meeting for improving the safety of Soviet-Designed Nuclear Power Plants, February 19, 1997

    SciTech Connect (OSTI)

    1997-04-01

    This report summarizes a meeting held on February 19, 1997, in Washington, D.C. The meeting was held primarily to exchange information among the contractors involved in the U.S. Department of Energy`s efforts to improve the safety of Soviet-designed nuclear power plants. Previous meetings have been held on December 5-6, 1995, and May 22, 1996. The meetings are sponsored by the U.S. Department of Energy and coordinated by the Pacific Northwest National Laboratory. The U.S. Department of Energy works with countries to increase the level of safety at 63 Soviet-designed nuclear reactors operating in Armenia, Bulgaria, the Czech Republic, Hungary, Lithuania, Russia, Slovakia, and Ukraine. The work is implemented largely by commercial companies and individuals who provide technologies and services to the countries with Soviet-designed nuclear power plants. Attending the meeting were 71 representatives of commercial contractors, the U.S. Department of Energy, the U.S. Department of State, national laboratories, and other federal agencies. The presentations and discussions that occurred during the exchange are summarized in this report. While this report captures the general presentation and discussion points covered at the meeting, it is not a verbatim, inclusive record. To make the report useful, information presented at the meeting has been expanded to clarify issues, respond to attendees` requests, or place discussion points in a broader programmatic context. Appendixes A through F contain the meeting agenda, list of attendees, copies of presentation visuals and handouts, the Strategy Document discussed at the meeting, and a summary of attendees` post-meeting evaluation comments. As with past information exchanges, the participants found this meeting valuable and useful. In response to the participant`s requests, a fourth information exchange will be held later in 1997.

  5. Organized for safety

    SciTech Connect (OSTI)

    McCleary, M.D.; Schuberth, P.C.; Hining, D.E.

    1996-11-01

    The Exxon Company, International Drilling Organization (ECIDO) is committed to an injury-free workplace through continuous efforts by identifying and eliminating or managing safety risks associated with drilling activities. The newly developed and recently completed ECIDO Safety Management Program (SMP) strengthens this commitment by defining a comprehensive, management approved, organized framework for drill teams from which operations safety is managed both effectively and consistently worldwide. The SMP is proactive, focuses on positive recognition, promotes greater individual involvement, and gives part ownership of the safety program at the rig level to the crews.

  6. Electrical Safety Occurrences | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    requested by the Electrical Safety Community for information exchange and continual learning. August 16, 2011 Monthly Analysis of Electrical Safety Occurrences - July 2011 An...

  7. Electrical Safety Occurrences | Department of Energy

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    requested by the Electrical Safety Community for information exchange and continual learning. October 29, 2013 Monthly Analysis of Electrical Safety Occurrences - September 2013...

  8. Produced water discharges to the Gulf of Mexico: Background information for ecological risk assessments

    SciTech Connect (OSTI)

    Meinhold, A.F.; Holtzman, S.; DePhillips, M.P.

    1996-06-01

    This report reviews ecological risk assessment concepts and methods; describes important biological resources in the Gulf of Mexico of potential concern for produced water impacts; and summarizes data available to estimate exposure and effects of produced water discharges. The emphasis is on data relating to produced water discharges in the central and western Gulf of Mexico, especially in Louisiana. Much of the summarized data and cited literature are relevant to assessments of impacts in other regions. Data describing effects on marine and estuarine fishes, mollusks, crustaceans and benthic invertebrates are emphasized. This review is part of a series of studies of the health and ecological risks from discharges of produced water to the Gulf of Mexico. These assessments will provide input to regulators in the development of guidelines and permits, and to industry in the use of appropriate discharge practices.

  9. National Safety Month- June 2013

    Broader source: Energy.gov [DOE]

    National Safety Month is recognized by employers, employees, and safety and health professionals throughout the country. During the month of June, HSS provided information, activities, and events pertaining to weekly themes.

  10. TWRS safety management plan

    SciTech Connect (OSTI)

    Popielarczyk, R.S., Westinghouse Hanford

    1996-08-01

    The Tank Waste Remediation System (TWRS) Safety Management Program Plan for development, implementation and maintenance of the tank farm authorization basis is described. The plan includes activities and procedures for: (a) Updating the current Interim Safety Basis, (b) Development,implementation and maintenance of a Basis for Interim Operations, (c) Development, implementation and maintenance of the Final Safety Analyses Report, (d) Development and implementation of a TWRS information Management System for monitoring the authorization basis.

  11. Compliance & Risk Assessment | Department of Energy

    Broader source: Energy.gov (indexed) [DOE]

    environmental hazards and risks to protect human health and safety and the environment. ... Plans. Risk evaluation tools such as the Human Health and Ecological Risk Methods ...

  12. Model-based safety assessments

    SciTech Connect (OSTI)

    Carlson, D.D.; Jones, T.R.

    1998-04-01

    Sandia National Laboratories performs systems analysis of high risk, high consequence systems. In particular, Sandia is responsible for the engineering of nuclear weapons, exclusive of the explosive physics package. In meeting this responsibility, Sandia has developed fundamental approaches to safety and a process for evaluating safety based on modeling and simulation. These approaches provide confidence in the safety of our nuclear weapons. Similar concepts may be applied to improve the safety of other high consequence systems.

  13. Health & Safety

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Health & Safety Health & Safety1354608000000Health & SafetySome of these resources are LANL-only and will require Remote Access.NoQuestions? 667-5809library@lanl.gov Health &...

  14. Safety, Security

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Safety, Security Safety, Security The Lab's mission is to develop and apply science and technology to ensure the safety, security, and reliability of the U.S. nuclear deterrent; reduce global threats; and solve other emerging national security and energy challenges. Contact Operator Los Alamos National Laboratory (505) 667-5061 We do not compromise safety for personal, programmatic, or operational reasons. Safety: we integrate safety, security, and environmental concerns into every step of our

  15. LANL closes road, trails for safety reasons; flooding and erosion...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    closed for safety reasons LANL closes road, trails for safety reasons; flooding and erosion control work under way Closure is in response to the increased fire risk and...

  16. Safety & Occupational Health Manager

    Broader source: Energy.gov [DOE]

    (See Frequently Asked Questions for more information). Where would I be working? Western Area Power Administration, Upper Great Plains Region, Safety Office (B0700). One vacancy exists that may be...

  17. Complete Safety Training

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    how to use the hutches and working with cryogens ALS 1007 User Chemistry Lab Chemical hygiene and safety course EHS 0348 Nano Materials More detailed information on working with...

  18. Safety and Security Officer

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2007-07-20

    Designated as the DOE official responsible for enforcement of 10 CFR 824 pertaining to the assessment of civil penalties for classified information security violations, and the management and administration of agency occupational safety and health program pursuant to EO 12196

  19. Lift truck safety review

    SciTech Connect (OSTI)

    Cadwallader, L.C.

    1997-03-01

    This report presents safety information about powered industrial trucks. The basic lift truck, the counterbalanced sit down rider truck, is the primary focus of the report. Lift truck engineering is briefly described, then a hazard analysis is performed on the lift truck. Case histories and accident statistics are also given. Rules and regulations about lift trucks, such as the US Occupational Safety an Health Administration laws and the Underwriter`s Laboratories standards, are discussed. Safety issues with lift trucks are reviewed, and lift truck safety and reliability are discussed. Some quantitative reliability values are given.

  20. WASTE PROCESSING ANNUAL NUCLEAR SAFETY RELATED R AND D REPORT FOR CY2008

    SciTech Connect (OSTI)

    Fellinger, A.

    2009-10-15

    The Engineering and Technology Office of Waste Processing identifies and reduces engineering and technical risks associated with key waste processing project decisions. The risks, and actions taken to mitigate those risks, are determined through technology readiness assessments, program reviews, technology information exchanges, external technical reviews, technical assistance, and targeted technology development and deployment (TDD). The Office of Waste Processing TDD program prioritizes and approves research and development scopes of work that address nuclear safety related to processing of highly radioactive nuclear wastes. Thirteen of the thirty-five R&D approved work scopes in FY2009 relate directly to nuclear safety, and are presented in this report.

  1. Safety and Occupational Health Manager

    Broader source: Energy.gov [DOE]

    (See Frequently Asked Questions for more information). Where would I be working? Western Area Power Administration, Corporate Services Office, Office of the Chief Operating Officer, Safety an...

  2. Health & Safety Exposition - Hanford Site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Events Exhibitor Information What is EXPO Electronic Registration Form Contact Us Health & Safety Exposition Email Email Page | Print Print Page |Text Increase Font Size...

  3. Facility Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2000-11-20

    The objective of this Order is to establish facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation. The Order has Change 1 dated 11-16-95, Change 2 dated 10-24-96, and the latest Change 3 dated 11-22-00 incorporated. The latest change satisfies a commitment made to the Defense Nuclear Facilities Safety Board (DNFSB) in response to DNFSB recommendation 97-2, Criticality Safety.

  4. Implementation of Information Management System for Radiation Safety of Personnel at the Russian Northwest Center for Radioactive Waste Management 'SevRAO' - 13131

    SciTech Connect (OSTI)

    Chizhov, K.; Simakov, A.; Seregin, V.; Kudrin, I.; Shandala, N.; Tsovyanov, A.; Kryuchkov, V. [Burnasyan Federal Medical Biophysical Center of Federal Medical Biological Agency, RF Ministry of Health and Social Development. 46, Zhivopisnaya St., Moscow, 123182 (Russian Federation)] [Burnasyan Federal Medical Biophysical Center of Federal Medical Biological Agency, RF Ministry of Health and Social Development. 46, Zhivopisnaya St., Moscow, 123182 (Russian Federation); Krasnoschekov, A.; Kosnikov, A. [Northwest Center for Radioactive Waste Management 'SevRAO' - a branch of the Federal State Unitary Enterprise 'Enterprise for Radioactive Waste Management' 'RosRAO' 183017, Murmansk, Lobova st., 100 (Russian Federation)] [Northwest Center for Radioactive Waste Management 'SevRAO' - a branch of the Federal State Unitary Enterprise 'Enterprise for Radioactive Waste Management' 'RosRAO' 183017, Murmansk, Lobova st., 100 (Russian Federation); Kemsky, I. [Regional management - 120 of the Federal Medical-Biological Agency, 184682, Snezhnogorsk, Valentina Biryukova St., 5/1 (Russian Federation)] [Regional management - 120 of the Federal Medical-Biological Agency, 184682, Snezhnogorsk, Valentina Biryukova St., 5/1 (Russian Federation); Sneve, M. [Norwegian Radiation Protection Authority, Postboks 55, 1332 Oesteraas (Norway)] [Norwegian Radiation Protection Authority, Postboks 55, 1332 Oesteraas (Norway)

    2013-07-01

    The report is an overview of the information-analytical system designed to assure radiation safety of workers. The system was implemented in the Northwest Radioactive Waste Management Center 'SevRAO' (which is a branch of the Federal State Unitary Enterprise 'Radioactive Waste Management Enterprise RosRAO'). The center is located in the Northwest Russia. In respect to 'SevRAO', the Federal Medical-Biological Agency is the regulatory body, which deals with issues of radiation control. The main document to regulate radiation control is 'Reference levels of radiation factors in radioactive wastes management center'. This document contains about 250 parameters. We have developed a software tool to simplify control of these parameters. The software includes: input interface, the database, dose calculating module and analytical block. Input interface is used to enter radiation environment data. Dose calculating module calculates the dose on the route. Analytical block optimizes and analyzes radiation situation maps. Much attention is paid to the GUI and graphical representation of results. The operator can enter the route at the industrial site or watch the fluctuations of the dose rate field on the map. Most of the results are presented in a visual form. Here we present some analytical tasks, such as comparison of the dose rate in some point with control levels at this point, to be solved for the purpose of radiation safety control. The program helps to identify points making the largest contribution to the collective dose of the personnel. The tool can automatically calculate the route with the lowest dose, compare and choose the best route. The program uses several options to visualize the radiation environment at the industrial site. This system will be useful for radiation monitoring services during the operation, planning of works and development of scenarios. The paper presents some applications of this system on real data over three years - from March 2009 to

  5. DOE's Safety Bulletin No. 2011-01, Events Beyond Design Safety Basis Analysis, March 2011

    Broader source: Energy.gov [DOE]

    PURPOSE This Safety Alert provides information on a safety concern related to the identification and mitigation of events that may fall outside those analyzed in the documented safety analysis.

  6. Safety, Codes and Standards Technical Publications

    Broader source: Energy.gov [DOE]

    Technical information about safety, codes and standards published in technical reports, conference proceedings, journal articles, and websites is provided here.

  7. Facility Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2012-12-04

    The Order establishes facility and programmatic safety requirements for DOE and NNSA for nuclear safety design criteria, fire protection, criticality safety, natural phenomena hazards (NPH) mitigation, and System Engineer Program. This Page Change is limited in scope to changes necessary to invoke DOE-STD-1104, Review and Approval of Nuclear Facility Safety Basis and Safety Design Basis Document, and revised DOE-STD-3009-2014, Preparation of Nonreactor Nuclear Facility Documented Safety Analysis as required methods. DOE O 420.1C Chg 1, dated 2-27-15, supersedes DOE O 420.1C.

  8. User Information

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    User Information User Information Print ALSHub User Portal User Guide A step-by-step guide for users about how to apply and prepare for beam time at the ALS. Experiment Safety Upon receiving beam time, complete an Experiment Safety Sheet Prospective Users Users from Industry Contacts for Users User Policy Data Management Users' Executive Committee (UEC) User Meeting

  9. DOE's Safety Bulletin No. 2011-01, Events Beyond Design Safety Basis

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Analysis, March 2011 | Department of Energy DOE's Safety Bulletin No. 2011-01, Events Beyond Design Safety Basis Analysis, March 2011 DOE's Safety Bulletin No. 2011-01, Events Beyond Design Safety Basis Analysis, March 2011 PURPOSE This Safety Alert provides information on a safety concern related to the identification and mitigation of events that may fall outside those analyzed in the documented safety analysis. BACKGROUND On March 11, 2011, the Fukushima Daiichi nuclear power station in

  10. Monthly Analysis of Electrical Safety Occurrences - February...

    Broader source: Energy.gov (indexed) [DOE]

    information for information exchange and continual learning. Monthly Analysis of Electrical Safety Occurrences - February 2011 More Documents & Publications Monthly Analysis of...

  11. Facility Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2005-12-22

    The order establishes facility and programmatic safety requirements for nuclear and explosives safety design criteria, fire protection, criticality safety, natural phenomena hazards (NPH) mitigation, and the System Engineer Program.Chg 1 incorporates the use of DOE-STD-1189-2008, Integration of Safety into the Design Process, mandatory for Hazard Category 1, 2 and 3 nuclear facilities. Cancels DOE O 420.1A.

  12. Biological Safety

    Office of Energy Efficiency and Renewable Energy (EERE)

    The DOE's Biological Safety Program provides a forum for the exchange of best practices, lessons learned, and guidance in the area of biological safety. This content is supported by the Biosurety Executive Team. The Biosurety Executive Team is a DOE-chartered group. The DOE Office of Worker Safety and Health Policy provides administrative support for this group. The group identifies biological safety-related issues of concern to the DOE and pursues solutions to issues identified.

  13. Facility Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2005-12-22

    This Order establishes facility and programmatic safety requirements for Department of Energy facilities, which includes nuclear and explosives safety design criteria, fire protection, criticality safety, natural phenomena hazards mitigation, and the System Engineer Program. Cancels DOE O 420.1A. DOE O 420.1B Chg 1 issued 4-19-10.

  14. Facility Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2012-12-04

    The Order establishes facility and programmatic safety requirements for DOE and NNSA for nuclear safety design criteria, fire protection, criticality safety, natural phenomena hazards (NPH) mitigation, and System Engineer Program. Cancels DOE O 420.1B, DOE G 420.1-2 and DOE G 420.1-3.

  15. Facility Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1995-10-13

    Establishes facility safety requirements related to: nuclear safety design, criticality safety, fire protection and natural phenomena hazards mitigation. Cancels DOE 5480.7A, DOE 5480.24, DOE 5480.28 and Division 13 of DOE 6430.1A. Canceled by DOE O 420.1A.

  16. Safety study application guide. Safety Analysis Report Update Program

    SciTech Connect (OSTI)

    Not Available

    1993-07-01

    Martin Marietta Energy Systems, Inc., (Energy Systems) is committed to performing and documenting safety analyses for facilities it manages for the Department of Energy (DOE). Included are analyses of existing facilities done under the aegis of the Safety Analysis Report Upgrade Program, and analyses of new and modified facilities. A graded approach is used wherein the level of analysis and documentation for each facility is commensurate with the magnitude of the hazard(s), the complexity of the facility and the stage of the facility life cycle. Safety analysis reports (SARs) for hazard Category 1 and 2 facilities are usually detailed and extensive because these categories are associated with public health and safety risk. SARs for Category 3 are normally much less extensive because the risk to public health and safety is slight. At Energy Systems, safety studies are the name given to SARs for Category 3 (formerly {open_quotes}low{close_quotes}) facilities. Safety studies are the appropriate instrument when on-site risks are limited to irreversible consequences to a few people, and off-site consequences are limited to reversible consequences to a few people. This application guide provides detailed instructions for performing safety studies that meet the requirements of DOE Orders 5480.22, {open_quotes}Technical Safety Requirements,{close_quotes} and 5480.23, {open_quotes}Nuclear Safety Analysis Reports.{close_quotes} A seven-chapter format has been adopted for safety studies. This format allows for discussion of all the items required by DOE Order 5480.23 and for the discussions to be readily traceable to the listing in the order. The chapter titles are: (1) Introduction and Summary, (2) Site, (3) Facility Description, (4) Safety Basis, (5) Hazardous Material Management, (6) Management, Organization, and Institutional Safety Provisions, and (7) Accident Analysis.

  17. Safety Analysis: Evaluation of Accident Risks in the Transporation of Hazardous Materials by Truck and Rail at the Savannah River Plant

    SciTech Connect (OSTI)

    Blanchard, A.

    1999-04-15

    This report presents an analysis of the consequences and risks of accidents resulting from hazardous material transportation at the Savannah River Plant.

  18. 2012 Nuclear Safety Workshop Presentations

    Broader source: Energy.gov [DOE]

    Lists workshop presentations from: Wednesday, September 19 - Plenary Session Wednesday, September 19 - Beyond Design Basis Events Analysis and Response Breakout Session Wednesday, September 19 - Safety Culture Breakout Session Wednesday, September 19 - Risk Assessment and Management Breakout Session Thursday, September 20 - Beyond Design Basis Events Analysis and Response Breakout Session Thursday, September 20 - Safety Culture Breakout Session Thursday, September 20 - Risk Assessment and Management Breakout Session Thursday, September 20 - Plenary Session

  19. New Methods and Tools to Perform Safety Analysis within RISMC

    SciTech Connect (OSTI)

    Diego Mandelli; Curtis Smith; Cristian Rabiti; Andrea Alfonsi; Robert Kinoshita; Joshua Cogliati

    2013-11-01

    The Risk Informed Safety Margins Characterization (RISMC) Pathway uses a systematic approach developed to characterize and quantify safety margins of nuclear power plant structures, systems and components. What differentiates the RISMC approach from traditional probabilistic risk assessment (PRA) is the concept of safety margin. In PRA, a safety metric such as core damage frequency (CDF) is generally estimated using static fault-tree and event-tree models. However, it is not possible to estimate how close we are to physical safety limits (say peak clad temperature) for most accident sequences described in the PRA. In the RISMC approach, what we want to understand is not just the frequency of an event like core damage, but how close we are (or not) to this event and how we might increase our safety margin through margin management strategies in a Dynamic PRA (DPRA) fashion. This paper gives an overview of methods that are currently under development at the Idaho National Laboratory (INL) with the scope of advance the current state of the art of dynamic PRA.

  20. Risk Informed Assessment of Regulatory and Design Requirements for Future Nuclear Power Plants (Cooperative Agreement DE-FC03-99SF21902, Am. M004) Final Technical Report

    SciTech Connect (OSTI)

    Stanley E. Ritterbusch, et. al.

    2003-01-29

    OAK-B135 Research under this project addresses the barriers to long term use of nuclear-generated electricity in the United States. It was agreed that a very basic and significant change to the current method of design and regulation was needed. That is, it was believed that the cost reduction goal could not be met by fixing the current system (i.e., an evolutionary approach) and a new, more advanced approach for this project would be needed. It is believed that a completely new design and regulatory process would have to be developed--a ''clean sheet of paper'' approach. This new approach would start with risk-based methods, would establish probabilistic design criteria, and would implement defense-in-depth only when necessary (1) to meet public policy issues (e.g., use of a containment building no matter how low the probability of a large release is) and (2) to address uncertainties in probabilistic methods and equipment performance. This new approach is significantly different from the Nuclear Regulatory Commission's (NRC) current risk-informed program for operating plants. For our new approach, risk-based methods are the primary means for assuring plant safety, whereas in the NRC's current approach, defense-in-depth remains the primary means of assuring safety. The primary accomplishments in the first year--Phase 1 were (1) the establishment of a new, highly risk-informed design and regulatory framework, (2) the establishment of the preliminary version of the new, highly risk-informed design process, (3) core damage frequency predictions showing that, based on new, lower pipe rupture probabilities, the design of the emergency core cooling system equipment can be simplified without reducing plant safety, and (4) the initial development of methods for including uncertainties in a new integrated structures-systems design model. Under the new regulatory framework, options for the use of ''design basis accidents'' were evaluated. It is expected that design basis

  1. Overview of DOE-NE Proliferation and Terrorism Risk Assessment

    SciTech Connect (OSTI)

    Sadasivan, Pratap

    2012-08-24

    Research objectives are: (1) Develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of current reactors; (2) Develop improvements in the affordability of new reactors to enable nuclear energy; (3) Develop Sustainable Nuclear Fuel Cycles; and (4) Understand and minimize the risks of nuclear proliferation and terrorism. The goal is to enable the use of risk information to inform NE R&D program planning. The PTRA program supports DOE-NE's goal of using risk information to inform R&D program planning. The FY12 PTRA program is focused on terrorism risk. The program includes a mix of innovative methods that support the general practice of risk assessments, and selected applications.

  2. Task Group report to the Assistant Secretary for Environment, Safety and Health on oversight of chemical safety at the Department of Energy. Volume 2, Appendices

    SciTech Connect (OSTI)

    Not Available

    1992-11-01

    This report presents the results of a preliminary review of chemical safety within the Department of Energy (DOE). The review was conducted by Chemical Safety Oversight Review (CSOR) Teams composed of Office of Environment, Safety and Health (EH) staff members and contractors. The primary objective of the CSOR was to assess, the safety status of DOE chemical operations and identify any significant deficiencies associated with such operations. Significant was defined as any situation posing unacceptable risk, that is, imminent danger or threat to workers, co-located workers, the general public, or the environment, that requires prompt action by EH or the line organizations. A secondary objective of the CSOR was to gather and analyze technical and programmatic information related to chemical safety to be used in conjunction with the longer-range EH Workplace Chemical Accident Risk Review (WCARR) Program. The WCARR Program is part of the ongoing EH oversight of nonnuclear safety at all DOE facilities. `` The program objective is to analyze DOE and industry chemical safety programs and performance and determine the need for additional or improved safety guidance for DOE. During the period June 6, 1992, through July 31, 1992, EH conducted CSORs at five DOE sites. The sites visited were Los Alamos National Laboratory (LANL), Savannah River Site (SRS), the Y-12 Plant (Y-12), Oak Ridge National Laboratory (ORNL), and Lawrence Livermore National Laboratory (LLNL).

  3. Next Generation Nuclear Plant Structures, Systems, and Components Safety Classification White Paper

    SciTech Connect (OSTI)

    Pete Jordan

    2010-09-01

    This white paper outlines the relevant regulatory policy and guidance for a risk-informed approach for establishing the safety classification of Structures, Systems, and Components (SSCs) for the Next Generation Nuclear Plant and sets forth certain facts for review and discussion in order facilitate an effective submittal leading to an NGNP Combined Operating License application under 10 CFR 52.

  4. Tank farm health and safety plan. Revision 2

    SciTech Connect (OSTI)

    Mickle, G.D.

    1995-03-29

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

  5. EO 13045: Protection of Children from Environmental Health Risks...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Environmental Health Risks and Safety Risks (1997) (As Amended by EO 13229 (2001) and EO 13296 (2003)) EO 13045: Protection of Children from Environmental Health Risks and ...

  6. Risk Management Guide - DOE Directives, Delegations, and Requirements

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    7A, Risk Management Guide by John Makepeace Functional areas: Risk Management, Safety and Security This Guide provides non-mandatory risk management approaches for implementing the...

  7. Safety Issues

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Site Safety Orientation April, 2015 Atmospheric Radiation Measurement Climate Research Facility/ North Slope of Alaska/Adjacent Arctic Ocean (ACRF/NSA/AAO) Site Safety Orientation Purpose This document provides an overview and summary of safety issues and safe work practices associated with operations at the Atmospheric Radiation Measurement Climate Research Facility/North Slope of Alaska/Adjacent Arctic Ocean (ACRF/NSA/AAO) Sites. It is intended for site visitors as well as routine site

  8. Risk Assessment Technical Experts Working Group

    Broader source: Energy.gov [DOE]

    The Risk Assessment Technical Experts Working Group (RWG) was established to assist DOE in the appropriate and effective use of quantitative risk assessment in nuclear safety related activities.

  9. AMERIND Risk Annual Conference and Trade Fair

    Broader source: Energy.gov [DOE]

    Hosted by the AMERIND Risk, this three-day conference includes trainings in risk management, workers' safety, human resources, and more.

  10. Explosives Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2012-06-27

    The Standard provides the basic technical requirements for an explosives safety program necessary for operations involving explosives, explosives assemblies, pyrotechnics and propellants, and assemblies containing these materials.

  11. Safety Engineer

    Broader source: Energy.gov [DOE]

    A successful candidate in this position will ensure DOE Federal personnel and contractors develop effective safety programs and continuously evaluates those activities to ensure compliance with DOE...

  12. Explosives Safety

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    ... Schnetzer, Kimball O. Merewether, and Roy E. Jorgenson; May 1993 (current version 06 August 2002) Life Safety Code: NFPA 101, National Fire Protection Association (current version) ...

  13. Station Blackout: A case study in the interaction of mechanistic and probabilistic safety analysis

    SciTech Connect (OSTI)

    Curtis Smith; Diego Mandelli; Cristian Rabiti

    2013-11-01

    The ability to better characterize and quantify safety margins is important to improved decision making about nuclear power plant design, operation, and plant life extension. As research and development (R&D) in the light-water reactor (LWR) Sustainability (LWRS) Program and other collaborative efforts yield new data, sensors, and improved scientific understanding of physical processes that govern the aging and degradation of plant SSCs needs and opportunities to better optimize plant safety and performance will become known. The purpose of the Risk Informed Safety Margin Characterization (RISMC) Pathway R&D is to support plant decisions for risk-informed margin management with the aim to improve economics, reliability, and sustain safety of current NPPs. In this paper, we describe the RISMC analysis process illustrating how mechanistic and probabilistic approaches are combined in order to estimate a safety margin. We use the scenario of a “station blackout” wherein offsite power and onsite power is lost, thereby causing a challenge to plant safety systems. We describe the RISMC approach, illustrate the station blackout modeling, and contrast this with traditional risk analysis modeling for this type of accident scenario.

  14. Seismic Safety Guide

    SciTech Connect (OSTI)

    Eagling, D.G.

    1983-09-01

    This guide provides managers with practical guidelines for administering a comprehensive earthquake safety program. The Guide is comprehensive with respect to earthquakes in that it covers the most important aspects of natural hazards, site planning, evaluation and rehabilitation of existing buildings, design of new facilities, operational safety, emergency planning, special considerations related to shielding blocks, non-structural elements, lifelines, fire protection and emergency facilities. Management of risk and liabilities is also covered. Nuclear facilities per se are not dealt with specifically. The principles covered also apply generally to nuclear facilities but the design and construction of such structures are subject to special regulations and legal controls.

  15. Institute for Business and Home Safety (IBHS) | Open Energy Informatio...

    Open Energy Info (EERE)

    Business and Home Safety (IBHS) Jump to: navigation, search Name: Institute for Business and Home Safety (IBHS) Place: Tampa, FL Information About Partnership with NREL Partnership...

  16. Assessing Risk and Driving Risk Mitigation for First-of-a-Kind Advanced Reactors

    SciTech Connect (OSTI)

    John W. Collins

    2011-09-01

    Planning and decision making amidst programmatic and technological risks represent significant challenges for projects. This presentation addresses the four step risk-assessment process needed to determine clear path forward to mature needed technology and design, license, and construct advanced nuclear power plants, which have never been built before, including Small Modular Reactors. This four step process has been carefully applied to the Next Generation Nuclear Plant. STEP 1 - Risk Identification Risks are identified, collected, and categorized as technical risks, programmatic risks, and project risks, each of which result in cost and schedule impacts if realized. These include risks arising from the use of technologies not previously demonstrated in a relevant application. These risks include normal and accident scenarios which the SMR could experience including events that cause the disablement of engineered safety features (typically documented in Phenomena Identification Ranking Tables (PIRT) as produced with the Nuclear Regulatory Commission) and design needs which must be addressed to further detail the design. Product - Project Risk Register contained in a database with sorting, presentation, rollup, risk work off functionality similar to the NGNP Risk Management System . STEP 2 - Risk Quantification The risks contained in the risk register are then scored for probability of occurrence and severity of consequence, if realized. Here the scoring methodology is established and the basis for the scoring is well documented. Product - Quantified project risk register with documented basis for scoring. STEP 3 - Risk Handling Strategy Risks are mitigated by applying a systematic approach to maturing the technology through Research and Development, modeling, test, and design. A Technology Readiness Assessment is performed to determine baseline Technology Readiness Levels (TRL). Tasks needed to mature the technology are developed and documented in a roadmap

  17. Thermal Reactor Safety

    SciTech Connect (OSTI)

    Not Available

    1980-06-01

    Information is presented concerning fire risk and protection; transient thermal-hydraulic analysis and experiments; class 9 accidents and containment; diagnostics and in-service inspection; risk and cost comparison of alternative electric energy sources; fuel behavior and experiments on core cooling in LOCAs; reactor event reporting analysis; equipment qualification; post facts analysis of the TMI-2 accident; and computational methods.

  18. Slideshow, National Safety Month- June 2013

    Broader source: Energy.gov [DOE]

    National Safety Month is recognized by employers, employees, and safety and health professionals throughout the country. During the month of June, HSS provided information, activities, and events pertaining to weekly themes.

  19. Environment, Safety, and Health Reporting Manual

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1996-11-07

    This Manual provides detailed requirements to supplement DOE O 231.1, ENVIRONMENT, SAFETY AND HEALTH REPORTING, which establishes management objectives and requirements for reporting environment, safety and health information. Chg 1, 11-7-96.

  20. Environment Safety and Health Reporting Manual

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1995-09-30

    This Manual provides detailed requirements to supplement DOE O 231.1, Environment, Safety and Health Reporting, which establishes management objectives and requirements for reporting environment, safety and health information. Does not cancel other directives.

  1. Safety is the First Priority

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    is the First Priority The project team completed a number of overlapping safety methods to assure the safety of individuals operating and in proximity to the hydrogen fuel cell including: ● Failure Mode Effects Analysis (FMEA) which identifies potential failure points and devises ways to mitigate them (engineered and administrative/operational controls). ● Independent review and approval of the design by the Hydrogen Safety Panel and the US Coast Guard, and informational review by the

  2. Safety and Health | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Health Safety and Health Office of Industrial Hygiene and Safety Information for Department of Energy Headquarters Personnel Our mission is to promote and coordinate safety and health for DOE Headquarters property (facilities) in addition to oversight of building operations, lease/project/space management, and support services for DOE Headquarters buildings. The Office of Industrial Hygiene and Safety provides information, guidelines, documentation, training, and materials pertaining to many

  3. Radiation Safety System

    SciTech Connect (OSTI)

    Vylet, Vaclav; Liu, James C.; Walker, Lawrence S.; /Los Alamos

    2012-04-04

    The goal of this work is to provide an overview of a Radiation safety system (RSS) designed for protection from prompt radiation hazard at accelerator facilities. RSS design parameters, functional requirements and constraints are derived from hazard analysis and risk assessment undertaken in the design phase of the facility. The two main subsystems of a RSS are access control system (ACS) and radiation control system (RCS). In this text, a common approach to risk assessment, typical components of ACS and RCS, desirable features and general design principles applied to RSS are described.

  4. Review and Approval of Nuclear Facility Safety Basis Documents (Documented Safety Analyses and Technical Safety Requirements)

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    DOE-STD-1104-96 November 2005 CHANGE NOTICE NO. 3 Date December 2005 DOE STANDARD REVIEW AND APPROVAL OF NUCLEAR FACILITY SAFETY BASIS DOCUMENTS (DOCUMENTED SAFETY ANALYSES AND TECHNICAL SAFETY REQUIREMENTS) U.S. Department of Energy AREA SAFT Washington, DC 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information

  5. Alerting device and method for reminding a person of a risk

    SciTech Connect (OSTI)

    Runyon, Larry; Gunter, Wayne M; Pratt, Richard M

    2001-11-27

    An alerting device and method to remind personnel of a risk is disclosed. The device has at least two sensors, a logic controller, a power source, and an annunciator that delivers a visual message, with or without an audible alarm, about a risk to a person when the sensors detect the person exiting a predetermined space. In particular, the present invention reminds a person of a security, safety, or health risk upon exiting a predetermined space. More particularly, the present invention reminds a person of an information security risk relating to sensitive, proprietary, confidential, trade secret, classified, or intellectual property information.

  6. Facility Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2002-05-20

    To establish facility safety requirements for the Department of Energy, including National Nuclear Security Administration. Cancels DOE O 420.1. Canceled by DOE O 420.1B.

  7. Transportation Safety

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Safety - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Energy Defense Waste Management Programs Advanced Nuclear Energy

  8. Forrestal Security and Safety Procedures

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1983-02-02

    To establish uniform procedures for the security and safety of the Forrestal Building and to inform all personnel of precautionary measures. This directive does not cancel another directive. Canceled by DOE N 251.11.

  9. DOE-NE Proliferation and Terrorism Risk Assessment: FY12 Plans Update

    SciTech Connect (OSTI)

    Sadasivan, Pratap

    2012-06-21

    This presentation provides background information on FY12 plans for the DOE Office of Nuclear Energy Proliferation and Terrorism Risk Assessment program. Program plans, organization, and individual project elements are described. Research objectives are: (1) Develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of current reactors; (2) Develop improvements in the affordability of new reactors to enable nuclear energy; (3) Develop Sustainable Nuclear Fuel Cycles; and (4) Understand and minimize the risks of nuclear proliferation and terrorism - Goal is to enable the use of risk information to inform NE R&D program planning.

  10. Safety System Oversight Staffing Analysis (Instructions, Blank...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Safety System Oversight Staffing Analysis (Instructions, Blank Sheet and Example Sheet) This Staffing Analysis calculation is completed using an Excel worksheet. Information ...

  11. Chemical Safety Program | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    For Additional Information Contact: Bill R. McArthur Chemical Management Tools Chemical Compatibility Material Safety Data Sheets Protective Action Criteria (PAC) with AEGLs, ...

  12. Nuclear Safety Research and Development Status Workshop Summary

    Office of Environmental Management (EM)

    NSR&D STATUS WORKSHOP SUMMARIES Caroline Garzon Chief of Nuclear Safety Staff NUCLEAR SAFETY R&D Perform a peer review of Risk Assessment Corporation WTP analysis by a team and ...

  13. An overview of safety assessment, regulation, and control of hazardous material use at NREL

    SciTech Connect (OSTI)

    Nelson, B.P.; Crandall, R.S. ); Moskowitz, P.D.; Fthenakis, V.M. )

    1992-12-01

    This paper summarizes the methodology we use to ensure the safe use of hazardous materials at the National Renewable Energy Laboratory (NREL). First, we analyze the processes and the materials used in those processes to identify the hazards presented. Then we study federal, state, and local regulations and apply the relevant requirements to our operations. When necessary, we generate internal safety documents to consolidate this information. We design research operations and support systems to conform to these requirements. Before we construct the systems, we perform a semiquantitative risk analysis on likely accident scenarios. All scenarios presenting an unacceptable risk require system or procedural modifications to reduce the risk. Following these modifications, we repeat the risk analysis to ensure that the respective accident scenarios present an acceptable risk. Once all risks are acceptable, we conduct an operational readiness review (ORR). A management-appointed panel performs the ORR ensuring compliance with all relevant requirements. After successful completion of the ORR, operations can begin.

  14. An overview of safety assessment, regulation, and control of hazardous material use at NREL

    SciTech Connect (OSTI)

    Nelson, B.P.; Crandall, R.S.; Moskowitz, P.D.; Fthenakis, V.M.

    1992-07-01

    This paper summarizes the methodology we use to ensure the safe use of hazardous materials at the National Renewable Energy Laboratory (NREL). First, we analyze the processes and the materials used in those processes to identify the hazards presented. Then we study federal, state, and local regulations and apply the relevant requirements to our operations. When necessary, we generate internal safety documents to consolidate this information. We design research operations and support systems to conform to these requirements. Before we construct the systems, we perform a semiquantitative risk analysis on likely accident scenarios. All scenarios presenting in unacceptable risk require system or procedural modifications to reduce the risk. Following these modifications, we repeat the risk analysis to ensure that the respective accident scenarios present acceptable risk. Once all risks are acceptable, we conduct an operational readiness review (ORR). A management appointed panel performs the ORR ensuring compliance with all relevant requirements. After successful completion of the ORR, operations can begin.

  15. New risk metrics and mathematical tools for risk analysis: Current and future challenges

    SciTech Connect (OSTI)

    Skandamis, Panagiotis N. Andritsos, Nikolaos Psomas, Antonios Paramythiotis, Spyridon

    2015-01-22

    The current status of the food safety supply world wide, has led Food and Agriculture Organization (FAO) and World Health Organization (WHO) to establishing Risk Analysis as the single framework for building food safety control programs. A series of guidelines and reports that detail out the various steps in Risk Analysis, namely Risk Management, Risk Assessment and Risk Communication is available. The Risk Analysis approach enables integration between operational food management systems, such as Hazard Analysis Critical Control Points, public health and governmental decisions. To do that, a series of new Risk Metrics has been established as follows: i) the Appropriate Level of Protection (ALOP), which indicates the maximum numbers of illnesses in a population per annum, defined by quantitative risk assessments, and used to establish; ii) Food Safety Objective (FSO), which sets the maximum frequency and/or concentration of a hazard in a food at the time of consumption that provides or contributes to the ALOP. Given that ALOP is rather a metric of the public health tolerable burden (it addresses the total ‘failure’ that may be handled at a national level), it is difficult to be interpreted into control measures applied at the manufacturing level. Thus, a series of specific objectives and criteria for performance of individual processes and products have been established, all of them assisting in the achievement of FSO and hence, ALOP. In order to achieve FSO, tools quantifying the effect of processes and intrinsic properties of foods on survival and growth of pathogens are essential. In this context, predictive microbiology and risk assessment have offered an important assistance to Food Safety Management. Predictive modelling is the basis of exposure assessment and the development of stochastic and kinetic models, which are also available in the form of Web-based applications, e.g., COMBASE and Microbial Responses Viewer), or introduced into user

  16. Impact of Passive Safety on FHR Instrumentation Systems Design and Classification

    SciTech Connect (OSTI)

    Holcomb, David Eugene

    2015-01-01

    Fluoride salt-cooled high-temperature reactors (FHRs) will rely more extensively on passive safety than earlier reactor classes. 10CFR50 Appendix A, General Design Criteria for Nuclear Power Plants, establishes minimum design requirements to provide reasonable assurance of adequate safety. 10CFR50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, provides guidance on how the safety significance of systems, structures, and components (SSCs) should be reflected in their regulatory treatment. The Nuclear Energy Institute (NEI) has provided 10 CFR 50.69 SSC Categorization Guideline (NEI-00-04) that factors in probabilistic risk assessment (PRA) model insights, as well as deterministic insights, through an integrated decision-making panel. Employing the PRA to inform deterministic requirements enables an appropriately balanced, technically sound categorization to be established. No FHR currently has an adequate PRA or set of design basis accidents to enable establishing the safety classification of its SSCs. While all SSCs used to comply with the general design criteria (GDCs) will be safety related, the intent is to limit the instrumentation risk significance through effective design and reliance on inherent passive safety characteristics. For example, FHRs have no safety-significant temperature threshold phenomena, thus, enabling the primary and reserve reactivity control systems required by GDC 26 to be passively, thermally triggered at temperatures well below those for which core or primary coolant boundary damage would occur. Moreover, the passive thermal triggering of the primary and reserve shutdown systems may relegate the control rod drive motors to the control system, substantially decreasing the amount of safety-significant wiring needed. Similarly, FHR decay heat removal systems are intended to be running continuously to minimize the amount of safety-significant instrumentation needed to initiate

  17. Impact of Passive Safety on FHR Instrumentation Systems Design and Classification

    SciTech Connect (OSTI)

    Holcomb, David Eugene

    2015-01-01

    Fluoride salt-cooled high-temperature reactors (FHRs) will rely more extensively on passive safety than earlier reactor classes. 10CFR50 Appendix A, General Design Criteria for Nuclear Power Plants, establishes minimum design requirements to provide reasonable assurance of adequate safety. 10CFR50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, provides guidance on how the safety significance of systems, structures, and components (SSCs) should be reflected in their regulatory treatment. The Nuclear Energy Institute (NEI) has provided 10 CFR 50.69 SSC Categorization Guideline (NEI-00-04) that factors in probabilistic risk assessment (PRA) model insights, as well as deterministic insights, through an integrated decision-making panel. Employing the PRA to inform deterministic requirements enables an appropriately balanced, technically sound categorization to be established. No FHR currently has an adequate PRA or set of design basis accidents to enable establishing the safety classification of its SSCs. While all SSCs used to comply with the general design criteria (GDCs) will be safety related, the intent is to limit the instrumentation risk significance through effective design and reliance on inherent passive safety characteristics. For example, FHRs have no safety-significant temperature threshold phenomena, thus enabling the primary and reserve reactivity control systems required by GDC 26 to be passively, thermally triggered at temperatures well below those for which core or primary coolant boundary damage would occur. Moreover, the passive thermal triggering of the primary and reserve shutdown systems may relegate the control rod drive motors to the control system, substantially decreasing the amount of safety-significant wiring needed. Similarly, FHR decay heat removal systems are intended to be running continuously to minimize the amount of safety-significant instrumentation needed to initiate

  18. DOE standard: Firearms safety

    SciTech Connect (OSTI)

    1996-02-01

    Information in this document is applicable to all DOE facilities, elements, and contractors engaged in work that requires the use of firearms as provided by law or contract. The standard in this document provides principles and practices for implementing a safe and effective firearms safety program for protective forces and for non-security use of firearms. This document describes acceptable interpretations and methods for meeting Order requirements.

  19. Identification and Resolution of Safety Issues for the Advanced Integral Type PWR

    SciTech Connect (OSTI)

    Kim, Woong Sik; Jo, Jong Chull; Yune, Young Gill; Kim, Hho Jung

    2004-07-01

    This paper presents the interim results of a study on the identification and resolution of safety issues for the AIPWR licensing. The safety issues discussed in this paper include (1) policy issues for which decision-makings are needed for the procedural requirements of licensing system in the regulatory policy point of view, (2) technical issues for which either development of new requirements or amendment of some existing requirements is needed, or (3) other technical issues for which safety verifications are required. The study covers (a) the assessment of applicability of the issues identified from the previous studies to the case of the AIPWR, (b) identification of safety issues through analysis of the international experiences in the design and licensing of advanced reactors, and technical review of the AIPWR design, and (c) development of the resolutions of safety issues, and application of the resolutions to the amendment of regulatory requirements and the licensing review of the AIPWR. As the results of this study, a total of twenty eight safety issues was identified: fourteen issues from the previous studies, including the establishment of design safety goals; four issues from the foreign practices and experiences, including the risk-informed licensing; and ten issues by the AIPWR design review, including reliability of passive safety systems. Ten issues of them have been already resolved and the succeeding study is under way to resolve the remaining ones. (authors)

  20. Lessons Learned from Safety Events

    SciTech Connect (OSTI)

    Weiner, Steven C.; Fassbender, Linda L.

    2012-11-01

    The Hydrogen Incident Reporting and Lessons Learned website (www.h2incidents.org) was launched in 2006 as a database-driven resource for sharing lessons learned from hydrogen-related safety events to raise safety awareness and encourage knowledge-sharing. The development of this database, its first uses and subsequent enhancements have been described at the Second and Third International Conferences on Hydrogen Safety. [1,2] Since 2009, continuing work has not only highlighted the value of safety lessons learned, but enhanced how the database provides access to another safety knowledge tool, Hydrogen Safety Best Practices (http://h2bestpractices.org). Collaborations with the International Energy Agency (IEA) Hydrogen Implementing Agreement (HIA) Task 19 Hydrogen Safety and others have enabled the database to capture safety event learnings from around the world. This paper updates recent progress, highlights the new Lessons Learned Corner as one means for knowledge-sharing and examines the broader potential for collecting, analyzing and using safety event information.

  1. SOME CHEMICAL SAFETY ASPECTS AT LANL

    SciTech Connect (OSTI)

    J. LAUL

    2001-05-01

    Recently, the Department of Energy (DOE) and its contractors have begun activities to improve the quality and consistency of chemical safety programs throughout the DOE Complex. Several working groups have been formed to assemble a framework for systematically identifying and quantifying chemical hazards and managing chemical risks. At LANL, chemical safety program is implemented through Laboratory Implementation Requirements (LIRs), which are part of the Integrated Safety Management (ISM) plan that includes Safe Work Practices, emphasizing five core functions; define work, identify and analyze hazards, develop and implement controls, perform work safely, and ensure performance. Work is authorized in medium, low and minimal risk areas and not in high risk. Some chemical safety aspects are discussed in terms of chemical hazards and identification, screening, facility hazard categorization--Category A (high), Category B (moderate), and Category C (low), and their requirements in format and content in Authorization Safety Basis documents.

  2. Monthly Analysis of Electrical Safety Occurrences - January 2011...

    Broader source: Energy.gov (indexed) [DOE]

    information for information exchange and continual learning. Monthly Analysis of Electrical Safety Occurrences - January 2011 More Documents & Publications Monthly Analysis of...

  3. Monthly Analysis of Electrical Safety Occurrences - May 2011...

    Broader source: Energy.gov (indexed) [DOE]

    information for information exchange and continual learning. Monthly Analysis of Electrical Safety Occurrences - May 2011 More Documents & Publications Monthly Analysis of...

  4. Monthly Analysis of Electrical Safety Occurrences - April 2011...

    Broader source: Energy.gov (indexed) [DOE]

    information for information exchange and continual learning. Monthly Analysis of Electrical Safety Occurrences - April 2011 More Documents & Publications Monthly Analysis of...

  5. Monthly Analysis of Electrical Safety Occurrences - March 2011...

    Energy Savers [EERE]

    analysis of March 2011 and past information for information exchange and continual learning. PDF icon Monthly Analysis of Electrical Safety Occurrences - March 2011 More...

  6. Safety harness

    DOE Patents [OSTI]

    Gunter, Larry W.

    1993-01-01

    A safety harness to be worn by a worker, especially a worker wearing a plastic suit thereunder for protection in a radioactive or chemically hostile environment, which safety harness comprises a torso surrounding portion with at least one horizontal strap for adjustably securing the harness about the torso, two vertical shoulder straps with rings just forward of the of the peak of the shoulders for attaching a life-line and a pair of adjustable leg supporting straps releasibly attachable to the torso surrounding portion. In the event of a fall, the weight of the worker, when his fall is broken and he is suspended from the rings with his body angled slightly back and chest up, will be borne by the portion of the leg straps behind his buttocks rather than between his legs. Furthermore, the supporting straps do not restrict the air supplied through hoses into his suit when so suspended.

  7. Department of Energy Cites Bechtel Jacobs for Classified Information...

    Energy Savers [EERE]

    Jacobs for Classified Information Security and Worker Safety and Health Violations Department of Energy Cites Bechtel Jacobs for Classified Information Security and Worker Safety ...

  8. Safety valve

    DOE Patents [OSTI]

    Bergman, Ulf C.

    1984-01-01

    The safety valve contains a resilient gland to be held between a valve seat and a valve member and is secured to the valve member by a sleeve surrounding the end of the valve member adjacent to the valve seat. The sleeve is movable relative to the valve member through a limited axial distance and a gap exists between said valve member and said sleeve.

  9. Facility Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2013-06-21

    DOE-STD-1104 contains the Department's method and criteria for reviewing and approving nuclear facility's documented safety analysis (DSA). This review and approval formally document the basis for DOE, concluding that a facility can be operated safely in a manner that adequately protects workers, the public, and the environment. Therefore, it is appropriate to formally require implementation of the review methodology and criteria contained in DOE-STD-1104.

  10. Nuclear Safety Regulatory Framework

    Energy Savers [EERE]

    Authority and responsibility to regulate nuclear safety at DOE facilities 10 CFR 830 10 CFR 835 10 CFR 820 Regulatory Implementation Nuclear Safety Radiological Safety Procedural ...

  11. Safety Management System Policy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    SAFETY MANAGEMENT POLICY PURPOSE AND SCOPE To establish the Department of Energy's (DOE) expectation for safety, 1 including integrated safety management that will enable ...

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

    SciTech Connect (OSTI)

    Szilard, Ronaldo H; Smith, Curtis L

    2014-09-01

    In this report, the Advanced Safety Analysis Program (ASAP) objectives and value proposition is described. ASAP focuses on modernization of nuclear power safety analysis (tools, methods and data); implementing state-of-the-art modeling techniques (which include, for example, enabling incorporation of more detailed physics as they become available); taking advantage of modern computing hardware; and combining probabilistic and mechanistic analyses to enable a risk informed safety analysis process. The modernized tools will maintain the current high level of safety in our nuclear power plant fleet, while providing an improved understanding of safety margins and the critical parameters that affect them. Thus, the set of tools will provide information to inform decisions on plant modifications, refurbishments, and surveillance programs, while improving economics. The set of tools will also benefit the design of new reactors, enhancing safety per unit cost of a nuclear plant. As part of the discussion, we have identified three sets of stakeholders, the nuclear industry, the Department of Energy (DOE), and associated oversight organizations. These three groups would benefit from ASAP in different ways. For example, within the DOE complex, the possible applications that are seen include the safety of experimental reactors, facility life extension, safety-by-design in future generation advanced reactors, and managing security for the storage of nuclear material. This report provides information in five areas: (1) A value proposition (“why is this important?”) that will make the case for stakeholder’s use of the ASAP research and development (R&D) products; (2) An identification of likely end users and pathway to adoption of enhanced tools by the end-users; (3) A proposed set of practical and achievable “use case” demonstrations; (4) A proposed plan to address ASAP verification and validation (V&V) needs; and (5) A proposed schedule for the multi-year ASAP.

  13. Risk of Hippocampal Metastases in Small Cell Lung Cancer Patients at Presentation and After Cranial Irradiation: A Safety Profile Study for Hippocampal Sparing During Prophylactic or Therapeutic Cranial Irradiation

    SciTech Connect (OSTI)

    Kundapur, Vijayananda; Ellchuk, Tasha; Ahmed, Shahid; Gondi, Vinai

    2015-03-15

    Purpose: Neurocognitive impairment (NI) in patients with small cell lung cancer (SCLC) after whole brain radiation treatment (WBRT) is a significant cause of morbidity. Hippocampal avoidance (HA) during WBRT may mitigate or prevent NI in such patients. However, this has not been tested in SCLC patients. The estimated risk of metastases in the HA region (HM) in patients with SCLC at diagnosis or after WBRT is unknown. Our study aimed to determine the risk of HM in patients with SCLC and to assess correlated clinical factors. Methods and Materials: Patients with SCLC who experienced brain metastases (BM) at presentation (de novo) or after WBRT treated at the Saskatoon Cancer Centre between 2005 and 2012 were studied. Relevant neuroimaging was independently reviewed by a neuroradiologist. HM was defined as metastases within 5 mm of the hippocampus. Logistic regression analysis was performed to assess correlation between various clinical variables and HM. Results: Seventy eligible patients were identified. Of 59 patients presenting with de novo BM, 3 patients (5%, 95% confidence interval [CI]: 0%-10.7%) had HM. Collectively there were 359 (range, 1-33) de novo BM with 3 (0.8%, 95% CI: 0%-1.7%) HM deposits. Twenty patients experienced progression of metastatic disease in the brain after WBRT. Of the 20 patients, only 1 patient (5%, 95% CI: 0%-14.5%) experienced HM. On logistic regression, no factors significantly correlated with HM. Conclusion: The overall incidence of HM before or after WBRT in SCLC patients is low, providing preliminary support for the safety of HA during planned clinical trials of HA-WBRT for SCLC.

  14. Overview of HyRAM (Hydrogen Risk Assessment Models) Software...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    HyRAM (Hydrogen Risk Assessment Models) Software for Science-Based Safety, Codes, and Standards Webinar Overview of HyRAM (Hydrogen Risk Assessment Models) Software for ...

  15. Proposed framework for the Western Area Power Administration Environmental Risk Management Program

    SciTech Connect (OSTI)

    Glantz, C.S.; DiMassa, F.V.; Pelto, P.J.; Brothers, A.J.; Roybal, A.L.

    1994-12-01

    The Western Area Power Administration (Western) views environmental protection and compliance as a top priority as it manages the construction, operation, and maintenance of its vast network of transmission lines, substations, and other facilities. A recent Department of Energy audit of Western`s environmental management activities recommends that Western adopt a formal environmental risk program. To accomplish this goal, Western, in conjunction with Pacific Northwest Laboratory, is in the process of developing a centrally coordinated environmental risk program. This report presents the results of this design effort, and indicates the direction in which Western`s environmental risk program is heading. Western`s environmental risk program will consist of three main components: risk communication, risk assessment, and risk management/decision making. Risk communication is defined as an exchange of information on the potential for threats to human health, public safety, or the environment. This information exchange provides a mechanism for public involvement, and also for the participation in the risk assessment and management process by diverse groups or offices within Western. The objective of risk assessment is to evaluate and rank the relative magnitude of risks associated with specific environmental issues that are facing Western. The evaluation and ranking is based on the best available scientific information and judgment and serves as input to the risk management process. Risk management takes risk information and combines it with relevant non-risk factors (e.g., legal mandates, public opinion, costs) to generate risk management options. A risk management tool, such as decision analysis, can be used to help make risk management choices.

  16. Transportation safety training

    SciTech Connect (OSTI)

    Jones, E.

    1990-01-01

    Over the past 25 years extensive federal legislation involving the handling and transport of hazardous materials/waste has been passed that has resulted in numerous overlapping regulations administered and enforced by different federal agencies. The handling and transport of hazardous materials/waste involves a significant number of workers who are subject to a varying degree of risk should an accident occur during handling or transport. Effective transportation training can help workers address these risks and mitigate them, and at the same time enable ORNL to comply with the federal regulations concerning the transport of hazardous materials/waste. This presentation will outline how the Environmental and Health Protection Division's Technical Resources and Training Section at the Oak Ridge National Laboratory, working with transportation and waste disposal personnel, have developed and implemented a comprehensive transportation safety training program to meet the needs of our workers while satisfying appropriate federal regulations. 8 refs., 3 tabs.

  17. PRELIMINARY ENVIRONMENTAL, HEALTH AND SAFETY RISK ASSESSMENT ON THE INTEGRATION OF A PROCESS UTILIZING LOW-ENERGY SOLVENTS FOR CARBON DIOXIDE CAPTURE ENABLED BY A COMBINATION OF ENZYMES AND VACUUM REGENERATION WITH A SUBCRITICAL PC POWER PLANT

    SciTech Connect (OSTI)

    Fitzgerald, David; Vidal, Rafael; Russell, Tania; Babcock, Doosan; Freeman, Charles; Bearden, Mark; Whyatt, Greg; Liu, Kun; Frimpong, Reynolds; Lu, Kunlei; Salmon, Sonja; House, Alan; Yarborough, Erin

    2014-12-31

    The results of the preliminary environmental, health and safety (EH&S) risk assessment for an enzyme-activated potassium carbonate (K2CO3) solution post-combustion CO2 capture (PCC) plant, integrated with a subcritical pulverized coal (PC) power plant, are presented. The expected emissions during normal steady-state operation have been estimated utilizing models of the PCC plant developed in AspenTech’s AspenPlus® software, bench scale test results from the University of Kentucky, and industrial experience of emission results from a slipstream PCC plant utilizing amine based solvents. A review of all potential emission species and their sources was undertaken that identified two credible emission sources, the absorber off-gas that is vented to atmosphere via a stack and the waste removed from the PCC plant in the centrifuge used to reclaim enzyme and solvent. The conditions and compositions of the emissions were calculated and the potential EH&S effects were considered as well as legislative compliance requirements. Potential mitigation methods for emissions during normal operation have been proposed and solutions to mitigate uncontrolled releases of species have been considered. The potential emissions were found to pose no significant EH&S concerns and were compliant with the Federal legislation reviewed. The limitations in predicting full scale plant performance from bench scale tests have been noted and further work on a larger scale test unit is recommended to reduce the level of uncertainty.

  18. Conduct and results of the Interagency Nuclear Safety Review Panel's evaluation of the Ulysses space mission

    SciTech Connect (OSTI)

    Sholtis, J.A. Jr. ); Gray, L.B. ); Huff, D.A. ); Klug, N.P. ); Winchester, R.O. )

    1991-01-01

    The recent 6 October 1990 launch and deployment of the nuclear-powered Ulysses spacecraft from the Space Shuttle {ital Discovery} culminated an extensive safety review and evaluation effort by the Interagency Nuclear Safety Review Panel (INSRP). After more than a year of detailed independent review, study, and analysis, the INSRP prepared a Safety Evaluation Report (SER) on the Ulysses mission, in accordance with Presidential Directive-National Security Council memorandum 25. The SER, which included a review of the Ulysses Final Safety Analysis Report (FSAR) and an independent characterization of the mission risks, was used by the National Aeronautics and Space Administration (NASA) in its decision to request launch approval as well as by the Executive Office of the President in arriving at a launch decision based on risk-benefit considerations. This paper provides an overview of the Ulysses mission and the conduct as well as the results of the INSRP evaluation. While the mission risk determined by the INSRP in the SER was higher than that characterized by the Ulysses project in the FSAR, both reports indicated that the radiological risks were relatively small. In the final analysis, the SER proved to be supportive of a positive launch decision. The INSRP evaluation process has demonstrated its effectiveness numerous times since the 1960s. In every case, it has provided the essential ingredients and perspective to permit an informed launch decision at the highest level of our Government.

  19. Delivering safety

    SciTech Connect (OSTI)

    Baldwin, N.D.; Spooner, K.G.; Walkden, P.

    2007-07-01

    In the United Kingdom there have been significant recent changes to the management of civil nuclear liabilities. With the formation in April 2005 of the Nuclear Decommissioning Authority (NDA), ownership of the civil nuclear licensed sites in the UK, including the Magnox Reactor Stations, passed to this new organisation. The NDAs mission is to seek acceleration of the nuclear clean up programme and deliver increased value for money and, consequently, are driving their contractors to seek more innovative ways of performing work. British Nuclear Group manages the UK Magnox stations under contract to the NDA. This paper summarises the approach being taken within its Reactor Sites business to work with suppliers to enhance working arrangements at sites, improve the delivery of decommissioning programmes and deliver improvements in safety and environmental performance. The UK Magnox stations are 1. generation gas-graphite reactors, constructed in the 1950's and 1960's. Two stations are currently still operating, three are shut-down undergoing defueling and the other five are being decommissioned. Despite the distractions of industry restructuring, an uncompromising policy of demanding improved performance in conjunction with improved safety and environmental standards has been adopted. Over the past 5 years, this policy has resulted in step-changes in performance at Reactor Sites, with increased electrical output and accelerated defueling and decommissioning. The improvements in performance have been mirrored by improvements in safety (DACR of 0 at 5 sites); environmental standards (reductions in energy and water consumption, increased waste recycling) and the overall health of the workforce (20% reduction in sickness absence). These achievements have, in turn, been recognised by external bodies, resulting in several awards, including: the world's first ISRS and IERS level 10 awards (Sizewell, 2006), the NUMEX plant maintenance award (Bradwell, 2006), numerous Ro

  20. H2 Safety Snapshot - Vol. 2, Issue 2, July 2011

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    2, July 2011 How Do I Perform A Hazard Analysis? Perform the hazard analysis at the project's earliest stages using any of the established industry methods described on page 2. A hazard analysis typically consists of the fve major steps shown in the graphic to the right (see Safety Planning Guidance for Hydrogen and Fuel Cell Projects in the list of Helpful Resources on page 2 for more information). Once the hazards are identifed, their risks should be categorized in terms of potential impact

  1. Health and Safety Research Division progress report for the period April 1, 1990--September 30, 1991

    SciTech Connect (OSTI)

    Kaye, S.V.

    1992-03-01

    This is a brief progress report from the Health and Safety Research Division of Oak Ridge National Laboratory. Information is presented in the following sections: Assessment Technology including Measurement Applications and Development, Pollutant Assessments, Measurement Systems Research, Dosimetry Applications Research, Metabolism and Dosimetry Research and Nuclear Medicine. Biological and Radiation Physics including Atomic, Molecular, and High Voltage Physics, Physics of Solids and Macromolecules, Liquid and Submicron Physics, Analytic Dosimetry and Surface Physics and Health Effects. Chemical Physics including Molecular Physics, Photophysics and Advanced Monitoring Development. Biomedical and Environmental Information Analysis including Human Genome and Toxicology, Chemical Hazard Evaluation and Communication, Environmental Regulations and Remediation and Information Management Technology. Risk Analysis including Hazardous Waste.

  2. Environment, Safety and Health Reporting

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2012-01-01

    To ensure timely collection, reporting, analysis, and dissemination of information on environment, safety, and health issues as required by law or regulations or as needed to ensure that the Department of Energy (DOE) and National Nuclear Security Administration are kept fully informed on a timely basis about events that could adversely affect the health and safety of the public or the workers, the environment, the intended purpose of DOE facilities, or the credibility of the Department. Cancels DOE O 210.1, DOE O 231.1, DOE O 232.1A. Canceled by DOE O 231.1B. DOE O 231.1B cancels all portions pertaining to environment, safety, and health reporting. Occurrence reporting and processing of operations information provisions remain in effect until January 1, 2012.

  3. Safety Share from National Safety Council

    Broader source: Energy.gov [DOE]

    Slide Presentation by Joe Yanek, Fluor Government Group. National Safety Council Safety Share. The Campbell Institute is the “Environmental, Health and Safety (EHS) Center of Excellence” at the National Safety Council and provides a Forum for Leaders in EHS to exchange ideas and collaborate across industry sectors and organizational types.

  4. CRITICALITY SAFETY TRAINING AT FLUOR HANFORD (FH)

    SciTech Connect (OSTI)

    TOFFER, H.

    2005-05-02

    The Fluor Hanford Criticality Safety engineers are extensively trained. The objectives and requirements for training are derived from Department of Energy (DOE) and American National Standards Institute/American Nuclear Society Standards (ANSI/ANS), and are captured in the Hanford Criticality Safety Program manual, HNF-7098. Qualification cards have been established for the general Criticality Safety Engineer (CSE) analyst, CSEs who support specific facilities, and for the facility Criticality Safety Representatives (CSRs). Refresher training and continuous education in the discipline are emphasized. Weekly Brown Bag Sessions keep the criticality safety engineers informed of the latest developments and historic perspectives.

  5. Environment, Safety, and Health Reporting

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2003-08-19

    To ensure timely collection, reporting, analysis, and dissemination of information on environment, safety, and health issues as required by law or regulations or as needed to ensure that the Department of Energy (DOE) and National Nuclear Security Administration (NNSA) are kept fully informed on a timely basis about events that could adversely affect the health and safety of the public or the workers, the environment, the intended purpose of DOE facilities, or the credibility of the Department. Cancels DOE O 210.1, DOE O 231.1, and DOE O 232.1A. Canceled by DOE O 232.2.

  6. Office of Information Management

    Broader source: Energy.gov [DOE]

    The Office of Information Management provides a broad range of information technology services in support of the Associate Under Secretary for the Office of Environment, Health, Safety and Security (AU).

  7. Microsoft PowerPoint - Fire Safety workshop NQA-1 CGD 4 29 15...

    Office of Environmental Management (EM)

    v Nuclear and Facility Safety Programs Workshop Fire Safety Track May 5th, 2015 Overview ... of Replacement Items in Nuclear Power Plants" * EPRI 1016157, "Information for ...

  8. Supplemental information related to risk assessment for the off-site transportation of low-level mixed waste for the U.S. Department of Energy waste management programmatic environmental impact statement

    SciTech Connect (OSTI)

    Monette, F.A.; Biwer, B.M.; LePoire, D.J.; Lazaro, M.A.; Antonopoulos, A.A.; Hartmann, H.M.; Policastro, A.J.; Chen, S.Y.

    1996-12-01

    This report provides supplemental information to support the human health risk assessment conducted for the transportation of low-level mixed waste (LLMW) in support of the US Department of Energy Waste Management Programmatic Environmental Impact Statement (WM PEIS). The assessment considers both the radioactive and chemical hazards associated with LLMW transportation. Detailed descriptions of the transportation health risk assessment methods and results of the assessment are presented in Appendix E of the WM PEIS. This report presents additional information that is not included in Appendix E but that was needed to conduct the transportation risk assessment for Waste Management (WM) LLMW. Included are definitions of the LLMW alternatives considered in the WM PEIS; data related to the inventory and to the physical, chemical, and radiological characteristics of WM LLMW; an overview of the risk assessment methods; and detailed results of the assessment for each WM LLMW case considered.

  9. Supplemental information related to risk assessment for the off-site transportation of low-level waste for the U.S. Department of Energy waste management programmatic environmental impact statement

    SciTech Connect (OSTI)

    Monette, F.A.; Biwer, B.M.; LePoire, D.J.; Chen, S.Y. [Argonne National Lab., IL (United States). Environmental Assessment Div.

    1996-12-01

    This report presents supplemental information to support the human health risk assessment conducted for the transportation of low-level waste (LLW) in support of the US Department of Energy Waste Management Programmatic Environmental Impact Statement (WM PEIS). Detailed descriptions of the transportation health risk assessment method and results of the assessment are presented in Appendix E of the WM PEIS and are not repeated in this report. This report presents additional information that is not presented in Appendix E but that was needed to conduct the transportation risk assessment for Waste Management (WM) LLW. Included are definition of the LLW alternatives considered in the WM PEIS, data related to the inventory and to the physical and radiological characteristics of WM LLW, an overview of the risk assessment method, and detailed results of the assessment for each WM LLW alternative considered.

  10. Material Safety Data Sheet

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Material Safety Data Sheet MSDS of LITHIUM POLYMER battery (total 3pages) 1. Product and Company Identification Product 1.1 Product Name: LITHIUM- POLYMER Battery 1.2 System: Rechargeable Lithium-ion Polymer Battery Comapny 1.4 Company Name: YUNTONG POWER CO.,LTD 1.5 Company Address: LINGGANG INDUSTRIAL ZONE JIANGLING Road, Zhongshan, G.D.China 1.6 Emergency Telephone Number: 86-760-8299193 2. Composition Information on Components Components Approximate Percent of Total Weight Aluminum 2-10%

  11. Enterprise Risk Management Specialist

    Broader source: Energy.gov [DOE]

    (See Frequently Asked Questions for more information). Where would I be working? Western Area Power Administration, Corporate Services Office, Office of the Chief Operating Officer, Risk and...

  12. Hydrogen Safety, Codes and Standards Challenges | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Current Approaches to Safety, Codes & Standards » Hydrogen Safety, Codes and Standards Challenges Hydrogen Safety, Codes and Standards Challenges From a safety, codes and standards perspective, the fundamental challenges to the commercialization of hydrogen technologies are the lack of safety information on hydrogen components and systems used in a hydrogen fuel infrastructure, and the limited availability of appropriate codes and standards to ensure uniformity and facilitate deployment.

  13. Job Safety and Health Poster | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Job Safety and Health Poster Job Safety and Health Poster Department of Energy (DOE) Job Safety and Health poster. DOE Order 440.1B Worker Protection Program for DOE (Including the National Nuclear Security Administration) Federal Employees and title 10, Code of Federal Regulations (CFR), part 851, Worker Safety and Health Program, both require that a worker safety and health poster be posted in a prominent location to inform employees of their rights and responsibilities. In the past, DOE has

  14. Criticality safety basics, a study guide

    SciTech Connect (OSTI)

    V. L. Putman

    1999-09-01

    This document is a self-study and classroom guide, for criticality safety of activities with fissile materials outside nuclear reactors. This guide provides a basic overview of criticality safety and criticality accident prevention methods divided into three parts: theory, application, and history. Except for topic emphasis, theory and history information is general, while application information is specific to the Idaho National Engineering and Environmental Laboratory (INEEL). Information presented here should be useful to personnel who must know criticality safety basics to perform their assignments safely or to design critically safe equipment or operations. However, the guide's primary target audience is fissile material handler candidates.

  15. Introduction to LNG vehicle safety. Topical report

    SciTech Connect (OSTI)

    Bratvold, D.; Friedman, D.; Chernoff, H.; Farkhondehpay, D.; Comay, C.

    1994-03-01

    Basic information on the characteristics of liquefied natural gas (LNG) is assembled in this report to provide an overview of safety issues and practices for the use of LNG vehicles. This document is intended for those planning or considering the use of LNG vehicles, including vehicle fleet owners and operators, public transit officials and boards, local fire and safety officials, manufacturers and distributors, and gas industry officials. Safety issues and mitigation measures that should be considered for candidate LNG vehicle projects are addressed.

  16. Office of Worker Safety and Health Assessments | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Worker Safety and Health Assessments Office of Worker Safety and Health Assessments MISSION The Office of Worker Safety and Health Assessments conducts assessments to provide critical feedback and objective information on occupational safety and health programs and performance. This information provides assurance to our stakeholders and identifies areas for improvement to our leadership to support the safe performance of the Department's mission. FUNCTIONS Conducts analyses of occupational

  17. Safety Alerts

    Office of Energy Efficiency and Renewable Energy (EERE)

    Documents downloaded from the password-protected areas of this web site may be made available to the DOE Federal and contractor community and to the military. These documents are not permitted to be made available to the general public via an Internet web site. All parties with access to the password-protected areas of the EHSS web site are to exercise due diligence to maintain control of information.

  18. CRAD, Nuclear Safety Delegations for Documented Safety Analysis...

    Office of Environmental Management (EM)

    Nuclear Safety Delegations for Documented Safety Analysis Approval - January 8, 2015 (EA CRAD 31-09, Rev. 0) CRAD, Nuclear Safety Delegations for Documented Safety Analysis ...

  19. Environment, Safety and Health Reporting

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2011-06-27

    The order addresses DOE/NNSA receiving timely, accurate information about events that have affected or could adversely affect the health, safety and security of the public or workers, the environment, the operations of DOE facilities, or the credibility of the Department. Admin Chg 1, dated 11-28-12, Supersedes DOE O 231.1B.

  20. Commercial Vehicle Safety Alliance Commercial Vehicle Safety...

    Office of Environmental Management (EM)

    of Radioactive Material Carlisle Smith Director, Hazardous Materials Programs ... Safety Alliance QUESTIONS? Carlisle Smith Director, Hazardous Materials Programs ...

  1. Dam Safety 2015

    Broader source: Energy.gov [DOE]

    Make your plans now to attend Dam Safety 2015, in New Orleans! Dam Safety 2015 is one of the leading conferences in the United States dedicated to dam and levee safety engineering and technology...

  2. Setting clear expectations for safety basis development

    SciTech Connect (OSTI)

    MORENO, M.R.

    2003-05-03

    DOE-RL has set clear expectations for a cost-effective approach for achieving compliance with the Nuclear Safety Management requirements (10 CFR 830, Nuclear Safety Rule) which will ensure long-term benefit to Hanford. To facilitate implementation of these expectations, tools were developed to streamline and standardize safety analysis and safety document development resulting in a shorter and more predictable DOE approval cycle. A Hanford Safety Analysis and Risk Assessment Handbook (SARAH) was issued to standardized methodologies for development of safety analyses. A Microsoft Excel spreadsheet (RADIDOSE) was issued for the evaluation of radiological consequences for accident scenarios often postulated for Hanford. A standard Site Documented Safety Analysis (DSA) detailing the safety management programs was issued for use as a means of compliance with a majority of 3009 Standard chapters. An in-process review was developed between DOE and the Contractor to facilitate DOE approval and provide early course correction. As a result of setting expectations and providing safety analysis tools, the four Hanford Site waste management nuclear facilities were able to integrate into one Master Waste Management Documented Safety Analysis (WM-DSA).

  3. Facility Disposition Safety Strategy RM

    Office of Environmental Management (EM)

    ... facility and nuclear safety requirements defined in 10 CFR 830, Nuclear Safety Management, and worker safety requirements defined in 10 CFR 851, Worker Safety and Health Program. ...

  4. DRAFT Bear Safety Plan

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Bear Safety Plan June 2010 NSAbspRev9.doc 1 Atmospheric Radiation Measurement Climate Research Facility North Slope of AlaskaAdjacent Arctic Ocean (ACRFNSAAAO) Bear Safety ...

  5. Safety | Department of Energy

    Energy Savers [EERE]

    On February 7, 2014, Deputy Assistant Secretary, Safety, Security, and Quality Programs Environmental Management, ... Serves as liaison to the Defense Nuclear Facilities Safety Board ...

  6. Advanced reactor safety research. Quarterly report, April-June 1982. Volume 22

    SciTech Connect (OSTI)

    None

    1983-10-01

    Overall objective of this work is to provide NRC a comprehensive data base essential to (1) defining key safety issues, (2) understanding risk-significant accident sequences, (3) developing and verifying models used in safety assessments, and (4) assuring the public that power reactor systems will not be licensed and placed in commercial service in the United States without appropriate consideration being given to their effects on health and safety. This report describes progress in a number of activities dealing with current safety issues relevant to both light water and breeder reactors. The work includes a broad range of experiments to simulate accidental conditions to provide the required data base to understand important accident sequences and to serve as a basis for development and verification of the complex computer simulation models and codes used in accident analysis and licensing reviews. Such a program must include the development of analytical models, verified by experiment, which can be used to predict reactor and safety system performance under a broad variety of abnormal conditions. Current major emphasis is focused on providing information to NRC relevant to (1) its deliberations and decisions dealing with severe LWR accidents, and (2) its safety evaluation of the proposed Clinch River Breeder Reactor.

  7. Operating Experience Level 3, Ladder Safety

    Office of Energy Efficiency and Renewable Energy (EERE)

    OE-3 2016-04: This Operating Experience Level 3 (OE-3) document provides information about a safety concern related to workers who use ladders during work at Department of Energy (DOE) facilities.

  8. Operating Experience Level 3, Electrical Safety: Shocks

    Broader source: Energy.gov [DOE]

    OE-3: 2015-03 This Operating Experience Level 3 (OE-3) document provides information about a safety concern related to electrical shocks workers have received while performing work at Department of Energy (DOE) facilities.

  9. Reactor Safety Research: Semiannual report, January-June 1986: Reactor Safety Research Program

    SciTech Connect (OSTI)

    Not Available

    1987-05-01

    Sandia National Laboratories is conducting, under USNRC sponsorship, phenomenological research related to the safety of commercial nuclear power reactors. The research includes experiments to simulate the phenomenology of accident conditions and the development of analytical models, verified by experiment, which can be used to predict reactor and safety systems performance behavior under abnormal conditions. The objective of this work is to provide NRC requisite data bases and analytical methods to (1) identify and define safety issues, (2) understand the progression of risk-significant accident sequences, and (3) conduct safety assessments. The collective NRC-sponsored effort at Sandia National Laboratories is directed at enhancing the technology base supporting licensing decisions.

  10. Risk-based technical specifications program: Site interview results

    SciTech Connect (OSTI)

    Andre, G.R.; Baker, A.J. ); Johnson, R.L. )

    1991-08-01

    The Electric Power Research Institute and Pacific Gas and Electric Company are sponsoring a program directed at improving Technical Specifications using risk-based methods. The major objectives of the program are to develop risk-based approaches to improve Technical Specifications and to develop an Interactive Risk Advisor (IRA) prototype. The IRA is envisioned as an interactive system that is available to plant personnel to assist in controlling plant operation. Use of an IRA is viewed as a method to improve plant availability while maintaining or improving plant safety. In support of the program, interviews were conducted at several PWR and BWR plant sites, to elicit opinions and information concerning risk-based approaches to Technical Specifications and IRA requirements. This report presents the results of these interviews, including the functional requirements of an IRA. 2 refs., 6 figs., 2 tabs.

  11. Monthly Analysis of Electrical Safety Occurrences - February 2013 |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Department of Energy 3 Monthly Analysis of Electrical Safety Occurrences - February 2013 February 2013 An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning. The report discusses the quantitative analysis of February 2013 and past information for information exchange and continual learning. Monthly Analysis of Electrical Safety Occurrences - February 2013 (2.74 MB)

  12. Monthly Analysis of Electrical Safety Occurrences - July 2012 |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Department of Energy 2 Monthly Analysis of Electrical Safety Occurrences - July 2012 July 2012 An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning. The report discusses the quantitative analysis of July 2012 and past information for information exchange and continual learning. Monthly Analysis of Electrical Safety Occurrences - July 2012 (1.71 MB) More Documents

  13. Monthly Analysis of Electrical Safety Occurrences - July 2013 |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Department of Energy 3 Monthly Analysis of Electrical Safety Occurrences - July 2013 July 2013 An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning. The report discusses the quantitative analysis of July 2013 and past information for information exchange and continual learning. Monthly Analysis of Electrical Safety Occurrences - July 2013 (2.69 MB) More Documents

  14. Monthly Analysis of Electrical Safety Occurrences - March 2013 |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Department of Energy 3 Monthly Analysis of Electrical Safety Occurrences - March 2013 March 2013 An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning. The report discusses the quantitative analysis of March 2013 and past information for information exchange and continual learning. Monthly Analysis of Electrical Safety Occurrences - March 2013 (2.61 MB) More Documents

  15. Monthly Analysis of Electrical Safety Occurrences - November 2012 |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Department of Energy 2 Monthly Analysis of Electrical Safety Occurrences - November 2012 November 2012 An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning. The report discusses the quantitative analysis of November 2012 and past information for information exchange and continual learning. Monthly Analysis of Electrical Safety Occurrences - November 2012 (2.17 MB)

  16. Monthly Analysis of Electrical Safety Occurrences - October 2012 |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Department of Energy 2 Monthly Analysis of Electrical Safety Occurrences - October 2012 October 2012 An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning. The report discusses the quantitative analysis of October 2012 and past information for information exchange and continual learning. Monthly Analysis of Electrical Safety Occurrences - October 2012 (1.52 MB) More

  17. Monthly Analysis of Electrical Safety Occurrences - September 2011 |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Department of Energy 1 Monthly Analysis of Electrical Safety Occurrences - September 2011 September 2011 An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning. The report discusses the quantitative analysis of September 2011 and past information for information exchange and continual learning. Monthly Analysis of Electrical Safety Occurrences - September 2011 (679.94

  18. Monthly Analysis of Electrical Safety Occurrences - September 2013 |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Department of Energy 3 Monthly Analysis of Electrical Safety Occurrences - September 2013 September 2013 An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning. The report discusses the quantitative analysis of September 2013 and past information for information exchange and continual learning. Monthly Analysis of Electrical Safety Occurrences - September 2013 (3.6 MB)

  19. CRITICALITY SAFETY CONTROLS AND THE SAFETY BASIS AT PFP

    SciTech Connect (OSTI)

    Kessler, S

    2009-04-21

    reviewing documents used in classifying controls for Nuclear Safety, it was noted that DOE-HDBK-1188, 'Glossary of Environment, Health, and Safety Terms', defines an Administrative Control (AC) in terms that are different than typically used in Criticality Safety. As part of this CCR, a new term, Criticality Administrative Control (CAC) was defined to clarify the difference between an AC used for criticality safety and an AC used for nuclear safety. In Nuclear Safety terms, an AC is a provision relating to organization and management, procedures, recordkeeping, assessment, and reporting necessary to ensure safe operation of a facility. A CAC was defined as an administrative control derived in a criticality safety analysis that is implemented to ensure double contingency. According to criterion 2 of Section IV, 'Linkage to the Documented Safety Analysis', of DOESTD-3007-2007, the consequence of a criticality should be examined for the purposes of classifying the significance of a control or component. HNF-PRO-700, 'Safety Basis Development', provides control selection criteria based on consequence and risk that may be used in the development of a Criticality Safety Evaluation (CSE) to establish the classification of a component as a design feature, as safety class or safety significant, i.e., an Engineered Safety Feature (ESF), or as equipment important to safety; or merely provides defense-in-depth. Similar logic is applied to the CACs. Criterion 8C of DOE-STD-3007-2007, as written, added to the confusion of using the basic CCR from HNF-7098. The PFP CCR attempts to clarify this criterion by revising it to say 'Programmatic commitments or general references to control philosophy (e.g., mass control or spacing control or concentration control as an overall control strategy for the process without specific quantification of individual limits) is included in the PFP DSA'. Table 1 shows the PFP methodology for evaluating CACs. This evaluation process has been in use since

  20. Hot Cell Facility (HCF) Safety Analysis Report

    SciTech Connect (OSTI)

    MITCHELL,GERRY W.; LONGLEY,SUSAN W.; PHILBIN,JEFFREY S.; MAHN,JEFFREY A.; BERRY,DONALD T.; SCHWERS,NORMAN F.; VANDERBEEK,THOMAS E.; NAEGELI,ROBERT E.

    2000-11-01

    This Safety Analysis Report (SAR) is prepared in compliance with the requirements of DOE Order 5480.23, Nuclear Safety Analysis Reports, and has been written to the format and content guide of DOE-STD-3009-94 Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Safety Analysis Reports. The Hot Cell Facility is a Hazard Category 2 nonreactor nuclear facility, and is operated by Sandia National Laboratories for the Department of Energy. This SAR provides a description of the HCF and its operations, an assessment of the hazards and potential accidents which may occur in the facility. The potential consequences and likelihood of these accidents are analyzed and described. Using the process and criteria described in DOE-STD-3009-94, safety-related structures, systems and components are identified, and the important safety functions of each SSC are described. Additionally, information which describes the safety management programs at SNL are described in ancillary chapters of the SAR.

  1. DEPARTMENT OF ENERGY CITES STANFORD UNIVERSITY FOR WORKER SAFETY...

    Energy Savers [EERE]

    851, Worker Safety and Health Program, in the areas of hazard identification and assessment; hazard prevention and abatement; training and information; and occupational medicine. ...

  2. Department of Energy Cites Stanford University for Worker Safety...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    851, Worker Safety and Health Program, in the areas of hazard identification and assessment; hazard prevention and abatement; training and information; and occupational medicine. ...

  3. Safety Planning Guidance for Hydrogen and Fuel Cell Projects

    SciTech Connect (OSTI)

    none,

    2010-04-01

    This guidance document provides information on safety requirements for hydrogen and fuel cell projects funded by the U.S. Department of Energy Fuel Cell Technologies Program.

  4. Monthly Analysis of Electrical Safety Occurrences – April 2013

    Broader source: Energy.gov [DOE]

    An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

  5. Safety Planning Guidance for Hydrogen and Fuel Cell Projects

    Fuel Cell Technologies Publication and Product Library (EERE)

    This guidance document provides information on safety requirements for hydrogen and fuel cell projects funded by the U.S. Department of Energy Fuel Cell Technologies Program.

  6. Safety System Oversight Staffing Analysis - Blank Sheet | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Safety System Oversight Staffing Analysis - Blank Sheet This Staffing Analysis calculation is completed using an Excel worksheet. Information locations are identified by titles in ...

  7. Monthly Analysis of Electrical Safety Occurrences – December 2011

    Broader source: Energy.gov [DOE]

    An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

  8. Monthly Analysis of Electrical Safety Occurrences – March 2012

    Broader source: Energy.gov [DOE]

    An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

  9. Monthly Analysis of Electrical Safety Occurrences – September 2012

    Broader source: Energy.gov [DOE]

    An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

  10. Monthly Analysis of Electrical Safety Occurrences – July 2011

    Broader source: Energy.gov [DOE]

    An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

  11. Monthly Analysis of Electrical Safety Occurrences – June 2012

    Broader source: Energy.gov [DOE]

    An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

  12. Monthly Analysis of Electrical Safety Occurrences – June 2013

    Broader source: Energy.gov [DOE]

    An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

  13. Monthly Analysis of Electrical Safety Occurrences – February 2012

    Broader source: Energy.gov [DOE]

    An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

  14. Monthly Analysis of Electrical Safety Occurrences – October 2011

    Broader source: Energy.gov [DOE]

    An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

  15. Monthly Analysis of Electrical Safety Occurrences – May 2012

    Broader source: Energy.gov [DOE]

    An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

  16. Monthly Analysis of Electrical Safety Occurrences – August 2012

    Broader source: Energy.gov [DOE]

    An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

  17. Monthly Analysis of Electrical Safety Occurrences – June 2011

    Broader source: Energy.gov [DOE]

    An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

  18. Monthly Analysis of Electrical Safety Occurrences – August 2013

    Broader source: Energy.gov [DOE]

    An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

  19. Monthly Analysis of Electrical Safety Occurrences – November 2011

    Broader source: Energy.gov [DOE]

    An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

  20. Monthly Analysis of Electrical Safety Occurrences – April 2012

    Broader source: Energy.gov [DOE]

    An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

  1. Monthly Analysis of Electrical Safety Occurrences – January 2012

    Broader source: Energy.gov [DOE]

    An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

  2. Monthly Analysis of Electrical Safety Occurrences – August 2011

    Broader source: Energy.gov [DOE]

    An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

  3. Monthly Analysis of Electrical Safety Occurrences – May 2013

    Broader source: Energy.gov [DOE]

    An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

  4. Monthly Analysis of Electrical Safety Occurrences – January 2013

    Broader source: Energy.gov [DOE]

    An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

  5. Monthly Analysis of Electrical Safety Occurrences – December 2012

    Broader source: Energy.gov [DOE]

    An analysis of the Occurrence Reporting and Processing System (ORPS) reports that was requested by the Electrical Safety Community for information exchange and continual learning.

  6. Facility Safety (For Informational Purposes Only)

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2014-12-04

    This draft has been scheduled for final review before the Directives Review Board on 12/18/14. All major comments and concerns should be provided to your DRB representative, following your organization process. If you do not know who your representative is, please see the list of DRB members. If your office is represented by Ingrid Kolb, Director, Office of Management, please submit your major concerns and comments to the DRB Liaison, Camille Beben (Camille.Beben@hq.doe.gov; 202-586-1014). All major comments and concerns should be submitted by COB 12/16/2014.

  7. Fire and Life Safety Information - Hanford Site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    - U.S Fire Administration Website PDF, 182 Kb Fire Extinguishers - Flash Presentation Smoke Detectors Smoke Detector Icon PDF, 182 Kb Smoke Alarms - What You Need to Know (PDF)...

  8. Ladder Safety Information Sheet | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    alternative, safer equipment for extended work at elevations, such as aerial lifts, ... Operating Experience Level 3, Fall Protection Can Prevent Serious Injuries Type A Accident ...

  9. Mathematical models for risk assessment

    SciTech Connect (OSTI)

    Zaikin, S.A.

    1995-12-01

    The use of mathematical models in risk assessment results in the proper understanding of many aspects of chemical exposure and allows to make more actual decisions. Our project ISCRA (Integrated Systems of Complex Risk Assessment) has the aim to create integrated systems of algorythms for prediction of pollutants` exposure on human and environmental health and to apply them for environmental monitoring, and decision-making. Mathematical model {open_quotes}MASTER{close_quotes} (Mathematical Algorythm of SimulaTion of Environmental Risk) represents the complex of algorythmical blocks and is intended for the prediction of danger of pollutants` exposure for human and environmental risk. Model LIMES (LIMits EStimation) is developed for prognosis of safety concentrations of pollutants in the environment both in the case of isolated exposure and in the case of complex exposure for concrete location. Model QUANT (QUANtity of Toxicant) represents the multicompartmental physiological pharmacokinetic model describing absorption, distribution, fate, metabolism, and elimination of pollutants in the body of different groups of human population, as a result of the different kind of exposure. Decision support system CLEVER (Complex LEVE1 of Risk) predicts the probability and the degree of development of unfavourable effects as result of exposure of pollutant on human health. System is based on the data of epidemiological and experimental researches and includes several mathematical models for analysis of {open_quotes}dose-time-response{close_quotes} relations and information about clinical symptoms of diseases. Model CEP (Combination Effect Prognosis) contains probabilistic algorythms for forecasting the effect of simultaneous impact of several factors polluting the environment. The result of the program work is the prediction of an independent exposure of two or more factors, and intensification or weakening of exposure in depending on factors` interactions.

  10. YUCCA MOUNTAIN SITE CHARACTERIZATION PROJECT EAST-WEST DRIFT SYSTEM SAFETY ANALYSIS

    SciTech Connect (OSTI)

    NA

    1999-06-08

    The purpose of this analysis is to systematically identify and evaluate hazards related to the design of the Yucca Mountain Project Exploratory Studies Facility (ESF) East-West Cross Drift. This analysis builds upon prior ESF System Safety Analyses and incorporates TS Main Drift scenarios, where applicable, into the East-West Drift scenarios. This System Safety Analysis (SSA) focuses on the personnel safety and health hazards associated with the engineered design of the East-West Drift. The analysis also evaluates other aspects of the East-West Drift, including purchased equipment (e.g., scientific mapping platform) or Systems/Structures/Components (SSCs) and out-of-tolerance conditions. In addition to recommending design mitigation features, the analysis identifies the potential need for procedures, training, or Job Safety Analyses (JSAs). The inclusion of this information in the SSA is intended to assist the organization(s) (e.g., constructor, Safety and Health, design) responsible for these aspects of the East-West Drift in evaluating personnel hazards and augment the information developed by these organizations. The SSA is an integral part of the systems engineering process, whereby safety is considered during planning, design, testing, and construction. A largely qualitative approach is used which incorporates operating experiences and recommendations from vendors, the constructor and the operating contractor. The risk assessment in this analysis characterizes the scenarios associated with East-West Drift SSCs in terms of relative risk and includes recommendations for mitigating all identified hazards. The priority for recommending and implementing mitigation control features is: (1) Incorporate measures to reduce risks and hazards into SSC designs. (2) Add safety features and capabilities to existing designs. (3) Develop procedures and conduct training to increase worker awareness of potential hazards, reduce exposure to hazards, and inform personnel of the

  11. Nuclear Safety Regulatory Framework

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Department of Energy Nuclear Safety Regulatory Framework DOE's Nuclear Safety Enabling Legislation Regulatory Enforcement & Oversight Regulatory Governance Atomic Energy Act 1946 Atomic Energy Act 1954 Energy Reorganization Act 1974 DOE Act 1977 Authority and responsibility to regulate nuclear safety at DOE facilities 10 CFR 830 10 CFR 835 10 CFR 820 Regulatory Implementation Nuclear Safety Radiological Safety Procedural Rules ISMS-QA; Operating Experience; Metrics and Analysis Cross Cutting

  12. Experiment Safety Requirements

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Experiment Safety Experiment Safety Requirements Print Safety at the ALS The mission of the ALS is to "Support users in doing outstanding science in a safe environment." How Do I...? Complete an Experiment Safety Sheet? (Do this upon receiving beam time.) Complete Safety Training? Bring and Use Electrical Equipment at the ALS? Determine what Personal Protective Equipment (PPE) to Wear? Get Authorization to Work with Lasers at the ALS? Ship Radioactive Materials to LBNL for Use at the

  13. Complete Safety Training

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Complete Safety Training Print Facility Safety Training Required for ALL Users Users must register with the ALS to obtain an LBNL ID number before they can complete safety training courses. Once registered, choose the non-LDAP login and enter your LBNL ID number to begin. ALS 1001: Safety at the ALS EHS 0470: General Employee Radiation Training (GERT) Special Training Required for Some Users Laser Safety Users working with a Class 3B/4 laser EHS 0302 Macromolecular Crystallography Users

  14. Complete Safety Training

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Complete Safety Training Print Facility Safety Training Required for ALL Users Users must register with the ALS to obtain an LBNL ID number before they can complete safety training courses. Once registered, choose the non-LDAP login and enter your LBNL ID number to begin. ALS 1001: Safety at the ALS EHS 0470: General Employee Radiation Training (GERT) Special Training Required for Some Users Laser Safety Users working with a Class 3B/4 laser EHS 0302 Macromolecular Crystallography Users

  15. Complete Safety Training

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Complete Safety Training Print Facility Safety Training Required for ALL Users Users must register with the ALS to obtain an LBNL ID number before they can complete safety training courses. Once registered, choose the non-LDAP login and enter your LBNL ID number to begin. ALS 1001: Safety at the ALS EHS 0470: General Employee Radiation Training (GERT) Special Training Required for Some Users Laser Safety Users working with a Class 3B/4 laser EHS 0302 Macromolecular Crystallography Users

  16. Complete Safety Training

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Complete Safety Training Print Facility Safety Training Required for ALL Users Users must register with the ALS to obtain an LBNL ID number before they can complete safety training courses. Once registered, choose the non-LDAP login and enter your LBNL ID number to begin. ALS 1001: Safety at the ALS EHS 0470: General Employee Radiation Training (GERT) Special Training Required for Some Users Laser Safety Users working with a Class 3B/4 laser EHS 0302 Macromolecular Crystallography Users

  17. Complete Safety Training

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Complete Safety Training Print Facility Safety Training Required for ALL Users Users must register with the ALS to obtain an LBNL ID number before they can complete safety training courses. Once registered, choose the non-LDAP login and enter your LBNL ID number to begin. ALS 1001: Safety at the ALS EHS 0470: General Employee Radiation Training (GERT) Special Training Required for Some Users Laser Safety Users working with a Class 3B/4 laser EHS 0302 Macromolecular Crystallography Users

  18. Plutonium Finishing Plant safety evaluation report

    SciTech Connect (OSTI)

    Not Available

    1995-01-01

    The Plutonium Finishing Plant (PFP) previously known as the Plutonium Process and Storage Facility, or Z-Plant, was built and put into operation in 1949. Since 1949 PFP has been used for various processing missions, including plutonium purification, oxide production, metal production, parts fabrication, plutonium recovery, and the recovery of americium (Am-241). The PFP has also been used for receipt and large scale storage of plutonium scrap and product materials. The PFP Final Safety Analysis Report (FSAR) was prepared by WHC to document the hazards associated with the facility, present safety analyses of potential accident scenarios, and demonstrate the adequacy of safety class structures, systems, and components (SSCs) and operational safety requirements (OSRs) necessary to eliminate, control, or mitigate the identified hazards. Documented in this Safety Evaluation Report (SER) is DOE`s independent review and evaluation of the PFP FSAR and the basis for approval of the PFP FSAR. The evaluation is presented in a format that parallels the format of the PFP FSAR. As an aid to the reactor, a list of acronyms has been included at the beginning of this report. The DOE review concluded that the risks associated with conducting plutonium handling, processing, and storage operations within PFP facilities, as described in the PFP FSAR, are acceptable, since the accident safety analyses associated with these activities meet the WHC risk acceptance guidelines and DOE safety goals in SEN-35-91.

  19. Information Collection | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Information Collection Information Collection The Office of Environment, Health, Safety and Security (EHSS) continues to seek for ways to minimize the burden of information collection on DOE and its contractors. DOE collects information concerning the health, safety and security of DOE employees including its contractors and facilities. The information collected will be used by DOE to exercise management oversight over Management and Operating (M&O) contractors of DOE's Government-Owned

  20. TWRS safety program plan

    SciTech Connect (OSTI)

    Calderon, L.M., Westinghouse Hanford

    1996-08-01

    Management of Nuclear Safety, Industrial Safety, Industrial Hygiene, and Fire Protection programs, functions, and field support resources for Tank Waste Remediation Systems (TWRS) has, until recently, been centralized in TWRS Safety, under the Emergency, Safety, and Quality organization. Industrial hygiene technician services were also provided to support operational needs related to safety basis compliance. Due to WHC decentralization of safety and reengineering efforts in West Tank Farms, staffing and safety responsibilities have been transferred to the facilities. Under the new structure, safety personnel for TWRS are assigned directly to East Tank Farms, West Tank Farms, and a core Safety Group in TWRS Engineering. The Characterization Project Operations (CPO) safety organization will remain in tact as it currently exists. Personnel assigned to East Tank Farms, West Tank Farms, and CPO will perform facility-specific or project-specific duties and provide field implementation of programs. Those assigned to the core group will focus on activities having a TWRS-wide or programmatic focus. Hanford-wide activities will be the responsibility of the Safety Center of Expertise. In order to ensure an effective and consistent safety program for TWRS under the new organization program functions, goals, organizational structure, roles, responsibilities, and path forward must be clearly established. The purpose of the TWRS Safety Program Plan is to define the overall safety program, responsibilities, relationships, and communication linkages for safety personnel under the new structure. In addition, issues associated with reorganization transition are addressed, including training, project ownership, records management, and dissemination of equipment. For the purpose of this document ``TWRS Safety`` refers to all safety professionals and technicians (Industrial Safety, Industrial Hygiene, Fire Protection, and Nuclear Safety) within the TWRS organization, regardless of their

  1. Management of National Nuclear Power Programs for assured safety

    SciTech Connect (OSTI)

    Connolly, T.J.

    1985-01-01

    Topics discussed in this report include: nuclear utility organization; before the Florida Public Service Commission in re: St. Lucie Unit No. 2 cost recovery; nuclear reliability improvement and safety operations; nuclear utility management; training of nuclear facility personnel; US experience in key areas of nuclear safety; the US Nuclear Regulatory Commission - function and process; regulatory considerations of the risk of nuclear power plants; overview of the processes of reliability and risk management; management significance of risk analysis; international and domestic institutional issues for peaceful nuclear uses; the role of the Institute of Nuclear Power Operations (INPO); and nuclear safety activities of the International Atomic Energy Agency (IAEA).

  2. Risk D&D Rapid Prototype: Scenario Documentation and Analysis Tool

    SciTech Connect (OSTI)

    Unwin, Stephen D.; Seiple, Timothy E.

    2009-05-28

    Report describes process and methodology associated with a rapid prototype tool for integrating project risk analysis and health & safety risk analysis for decontamination and decommissioning projects.

  3. Nuclear fuel cycle risk assessment: survey and computer compilation of risk-related literature. [Once-through Cycle and Plutonium Recycle

    SciTech Connect (OSTI)

    Yates, K.R.; Schreiber, A.M.; Rudolph, A.W.

    1982-10-01

    The US Nuclear Regulatory Commission has initiated the Fuel Cycle Risk Assessment Program to provide risk assessment methods for assistance in the regulatory process for nuclear fuel cycle facilities other than reactors. Both the once-through cycle and plutonium recycle are being considered. A previous report generated by this program defines and describes fuel cycle facilities, or elements, considered in the program. This report, the second from the program, describes the survey and computer compilation of fuel cycle risk-related literature. Sources of available information on the design, safety, and risk associated with the defined set of fuel cycle elements were searched and documents obtained were catalogued and characterized with respect to fuel cycle elements and specific risk/safety information. Both US and foreign surveys were conducted. Battelle's computer-based BASIS information management system was used to facilitate the establishment of the literature compilation. A complete listing of the literature compilation and several useful indexes are included. Future updates of the literature compilation will be published periodically. 760 annotated citations are included.

  4. An Integrated Safety Assessment Methodology for Generation IV Nuclear Systems

    SciTech Connect (OSTI)

    Timothy J. Leahy

    2010-06-01

    The Generation IV International Forum (GIF) Risk and Safety Working Group (RSWG) was created to develop an effective approach for the safety of Generation IV advanced nuclear energy systems. Early work of the RSWG focused on defining a safety philosophy founded on lessons learned from current and prior generations of nuclear technologies, and on identifying technology characteristics that may help achieve Generation IV safety goals. More recent RSWG work has focused on the definition of an integrated safety assessment methodology for evaluating the safety of Generation IV systems. The methodology, tentatively called ISAM, is an integrated toolkit consisting of analytical techniques that are available and matched to appropriate stages of Generation IV system concept development. The integrated methodology is intended to yield safety-related insights that help actively drive the evolving design throughout the technology development cycle, potentially resulting in enhanced safety, reduced costs, and shortened development time.

  5. Hydrogen and Gaseous Fuel Safety and Toxicity

    SciTech Connect (OSTI)

    Lee C. Cadwallader; J. Sephen Herring

    2007-06-01

    Non-traditional motor fuels are receiving increased attention and use. This paper examines the safety of three alternative gaseous fuels plus gasoline and the advantages and disadvantages of each. The gaseous fuels are hydrogen, methane (natural gas), and propane. Qualitatively, the overall risks of the four fuels should be close. Gasoline is the most toxic. For small leaks, hydrogen has the highest ignition probability and the gaseous fuels have the highest risk of a burning jet or cloud.

  6. Safety, Codes and Standards - Basics | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Safety, Codes & Standards » Safety, Codes and Standards - Basics Safety, Codes and Standards - Basics Hydrogen has a long history of safe use in the chemical and aerospace industries. An understanding of hydrogen properties, proper safety precautions and engineering controls, and established rules, regulations, and standards are the keys to this successful track record. As the use of hydrogen and fuel cell systems expands, codes and standards will be needed to provide the information to

  7. Nuclear Safety Basis Program Review Overview and Management Oversight

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Standard Review Plan | Department of Energy Safety Basis Program Review Overview and Management Oversight Standard Review Plan Nuclear Safety Basis Program Review Overview and Management Oversight Standard Review Plan This SRP, Nuclear Safety Basis Program Review, consists of five volumes. It provides information to help strengthen the technical rigor of line management oversight and federal monitoring of DOE nuclear facilities. It provides a primer on the safety basis development and

  8. Multimegawatt Space Reactor Safety

    SciTech Connect (OSTI)

    Stanley, M.L. )

    1989-01-01

    The Multimegawatt (MMW) Space Reactor Project supports the Strategic Defense Initiative Office requirement to provide reliable, safe, cost-effective, electrical power in the MMW range. Specifically, power may be used for neutral particle beams, free electron lasers, electromagnetic launchers, and orbital transfer vehicles. This power plant technology may also apply to the electrical power required for other uses such as deep-space probes and planetary exploration. The Multimegawatt Space Reactor Project, the Thermionic Fuel Element Verification Program, and Centaurus Program all support the Multimegawatt Space Nuclear Power Program and form an important part of the US Department of Energy's (DOE's) space and defense power systems activities. A major objective of the MMW project is the development of a reference flight system design that provides the desired levels of public safety, health protection, and special nuclear material (SNM) protection when used during its designated missions. The safety requirements for the MMW project are a hierarchy of requirements that consist of safety requirements/regulations, a safety policy, general safety criteria, safety technical specifications, safety design specifications, and the system design. This paper describes the strategy and philosophy behind the development of the safety requirements imposed upon the MMW concept developers. The safety organization, safety policy, generic safety issues, general safety criteria, and the safety technical specifications are discussed.

  9. Environment, Safety and Health Reporting

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2011-06-27

    The order addresses DOE/NNSA receiving timely, accurate information about events that have affected or could adversely affect the health, safety and security of the public or workers, the environment, the operations of DOE facilities, or the credibility of the Department. Cancels DOE N 234.1. Supersedes DOE O 231.1A Chg 1, DOE M 231.1-1A Chg 2.

  10. Risk Assessment Tool - DOE Directives, Delegations, and Requirements

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Risk Assessment Technical Experts Working Group Risk Assessment Technical Experts Working Group The Risk Assessment Technical Experts Working Group (RWG) is established to assist DOE in the appropriate and effective use of quantitative risk assessment in nuclear safety related activities. The activities of the group will help DOE ensure that risk assessments supporting nuclear safety decisions are conducted in a consistent manner, of appropriate quality, properly tailored to the needs of the

  11. Proceedings of the international meeting on thermal nuclear reactor safety. Vol. 1

    SciTech Connect (OSTI)

    1983-02-01

    Separate abstracts are included for each of the papers presented concerning current issues in nuclear power plant safety; national programs in nuclear power plant safety; radiological source terms; probabilistic risk assessment methods and techniques; non LOCA and small-break-LOCA transients; safety goals; pressurized thermal shocks; applications of reliability and risk methods to probabilistic risk assessment; human factors and man-machine interface; and data bases and special applications.

  12. Managing risk in software systems

    SciTech Connect (OSTI)

    Fletcher, S.K.; Jansma, R.M.; Murphy, M.D.

    1995-07-01

    A methodology for risk management in the design of software systems is presented. It spans security, safety, and correct operation of software within the context of its environment, and produces a risk analysis and documented risk management strategy. It is designed to be iteratively applied, to attain appropriate levels of detail throughout the analysis. The methodology and supporting tools are discussed. The methodology is critiqued relative to other research in the field. Some sample applications of the methodology are presented.

  13. AUDIT REPORT Follow-up on Nuclear Safety: Safety Basis and Quality Assurance at the Los Alamos National

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Nuclear Safety: Safety Basis and Quality Assurance at the Los Alamos National Laboratory DOE/IG-0941 July 2015 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 July 16, 2015 MEMORANDUM FOR THE SECRETARY FROM: Gregory H. Friedman Inspector General SUBJECT: INFORMATION: Audit Report: "Follow-up on Nuclear Safety: Safety Basis and Quality Assurance at the Los Alamos National Laboratory" BACKGROUND A primary

  14. Experiment Safety Requirements

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Experiment Safety Requirements Print Safety at the ALS The mission of the ALS is to "Support users in doing outstanding science in a safe environment." How Do I...? Complete an...

  15. Hydrogen Safety Knowledge Tools

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Data Partners Best Practices - LANL, SNL, NREL, NASA, Hydrogen Safety Panel, and IEA HIA Tasks 19 and 22 Incident Reporting - NASA and Hydrogen Safety Panel 3 Objectives H2...

  16. Optical Safety of LEDs

    SciTech Connect (OSTI)

    none,

    2013-06-01

    Solid-state lighting program technology fact sheet that clarifies the issue of LED lighting safety for the human eye and takes a look at current standards for photobiological safety.

  17. Office of Nuclear Safety

    Office of Energy Efficiency and Renewable Energy (EERE)

    The Office of Nuclear Safety establishes nuclear safety requirements and expectations for the Department to ensure protection of workers and the public from the hazards associated with nuclear operations with all Department operations.

  18. Program Analyst (Transportation Safety)

    Broader source: Energy.gov [DOE]

    A successful candidate in this position will serve as a Program Analyst(Transportation Safety) supporting and advising management on safety and health matters for nuclear and non-nuclear activities.

  19. Safety Issues with Hydrogen as a Vehicle Fuel

    SciTech Connect (OSTI)

    Cadwallader, Lee Charles; Herring, James Stephen

    1999-10-01

    This report is an initial effort to identify and evaluate safety issues associated with the use of hydrogen as a vehicle fuel in automobiles. Several forms of hydrogen have been considered: gas, liquid, slush, and hydrides. The safety issues have been discussed, beginning with properties of hydrogen and the phenomenology of hydrogen combustion. Safety-related operating experiences with hydrogen vehicles have been summarized to identify concerns that must be addressed in future design activities and to support probabilistic risk assessment. Also, applicable codes, standards, and regulations pertaining to hydrogen usage and refueling have been identified and are briefly discussed. This report serves as a safety foundation for any future hydrogen safety work, such as a safety analysis or a probabilistic risk assessment.

  20. Safety Issues with Hydrogen as a Vehicle Fuel

    SciTech Connect (OSTI)

    L. C. Cadwallader; J. S. Herring

    1999-09-01

    This report is an initial effort to identify and evaluate safety issues associated with the use of hydrogen as a vehicle fuel in automobiles. Several forms of hydrogen have been considered: gas, liquid, slush, and hydrides. The safety issues have been discussed, beginning with properties of hydrogen and the phenomenology of hydrogen combustion. Safety-related operating experiences with hydrogen vehicles have been summarized to identify concerns that must be addressed in future design activities and to support probabilistic risk assessment. Also, applicable codes, standards, and regulations pertaining to hydrogen usage and refueling have been identified and are briefly discussed. This report serves as a safety foundation for any future hydrogen safety work, such as a safety analysis or a probabilistic risk assessment.

  1. Experiment Safety Requirements

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Experiment Safety Requirements Print Safety at the ALS The mission of the ALS is to "Support users in doing outstanding science in a safe environment." How Do I...? Complete an Experiment Safety Sheet? (Do this upon receiving beam time.) Complete Safety Training? Bring and Use Electrical Equipment at the ALS? Determine what Personal Protective Equipment (PPE) to Wear? Get Authorization to Work with Lasers at the ALS? Ship Radioactive Materials to LBNL for Use at the ALS? Ship Samples

  2. Experiment Safety Requirements

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Experiment Safety Requirements Print Safety at the ALS The mission of the ALS is to "Support users in doing outstanding science in a safe environment." How Do I...? Complete an Experiment Safety Sheet? (Do this upon receiving beam time.) Complete Safety Training? Bring and Use Electrical Equipment at the ALS? Determine what Personal Protective Equipment (PPE) to Wear? Get Authorization to Work with Lasers at the ALS? Ship Radioactive Materials to LBNL for Use at the ALS? Ship Samples

  3. Safety | Argonne National Laboratory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    News Careers Education Community Diversity Directory Argonne National Laboratory About Safety News Careers Education Community Diversity Directory Energy Environment Security User Facilities Science Work with Argonne Safety Biosafety Safety Safety is integral to Argonne's scientific research and engineering technology mission. As a leading U.S. Department of Energy multi-program research laboratory, our obligation to the American people demands that we conduct our research and operations safely

  4. Nuclear Explosive Safety Manual

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2009-04-14

    This Manual provides supplemental details to support the requirements of DOE O 452.2D, Nuclear Explosive Safety.

  5. Index of /safety

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    safety Icon Name Last modified Size Description [DIR] Parent Directory - [DIR] hazardousradioactive..> 17-Apr-2013 12:29 -

  6. Experiment Safety Requirements

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Experiment Safety Requirements Print Safety at the ALS The mission of the ALS is to "Support users in doing outstanding science in a safe environment." How Do I...? Complete an Experiment Safety Sheet? (Do this upon receiving beam time.) Complete Safety Training? Bring and Use Electrical Equipment at the ALS? Determine what Personal Protective Equipment (PPE) to Wear? Get Authorization to Work with Lasers at the ALS? Ship Radioactive Materials to LBNL for Use at the ALS? Ship Samples

  7. Experiment Safety Requirements

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Experiment Safety Requirements Print Safety at the ALS The mission of the ALS is to "Support users in doing outstanding science in a safe environment." How Do I...? Complete an Experiment Safety Sheet? (Do this upon receiving beam time.) Complete Safety Training? Bring and Use Electrical Equipment at the ALS? Determine what Personal Protective Equipment (PPE) to Wear? Get Authorization to Work with Lasers at the ALS? Ship Radioactive Materials to LBNL for Use at the ALS? Ship Samples

  8. Experiment Safety Requirements

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Experiment Safety Requirements Print Safety at the ALS The mission of the ALS is to "Support users in doing outstanding science in a safe environment." How Do I...? Complete an Experiment Safety Sheet? (Do this upon receiving beam time.) Complete Safety Training? Bring and Use Electrical Equipment at the ALS? Determine what Personal Protective Equipment (PPE) to Wear? Get Authorization to Work with Lasers at the ALS? Ship Radioactive Materials to LBNL for Use at the ALS? Ship Samples

  9. Experiment Safety Requirements

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Experiment Safety Requirements Print Safety at the ALS The mission of the ALS is to "Support users in doing outstanding science in a safe environment." How Do I...? Complete an Experiment Safety Sheet? (Do this upon receiving beam time.) Complete Safety Training? Bring and Use Electrical Equipment at the ALS? Determine what Personal Protective Equipment (PPE) to Wear? Get Authorization to Work with Lasers at the ALS? Ship Radioactive Materials to LBNL for Use at the ALS? Ship Samples

  10. Integrated Safety Management Policy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    INTEGRATED SAFETY MANAGEMENT SYSTEM DESCRIPTION U.S. DEPARTMENT OF ENERGY Office of Environmental Management Headquarters May 2008 Preparation: Braj K. sin& Occupational Safety and Health Manager Office of Safety Management Concurrence: Chuan-Fu wu Director, Offlce of Safety Management Deputy Assistant Secretary for safe& Management andoperations Operations Officer for 1 Environmental Management Approval: Date p/-g Date Environmental Management TABLE OF CONTENTS

  11. Safety and Health

    Broader source: Energy.gov [DOE]

    PPPO’s Safety and Health (S&H) program integrates safety and health requirements and controls into all work activities and oversees implementation of Integrated Safety Management (ISM) within contractor activities to ensure protection to workers, the public, and the environment.

  12. Integrated Safety Management

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Safety Management BEHAVIOR (SAFETY CULTURE) - principles of behavior (values) - align motivations PLAN WORK define project scope define facility functional requirements define and analyze hazards mitigate hazards develop & implement controls authorize work assess & improve work execution reaction to changed conditions LEVELS - INSTITUTIONAL - site wide programs - DOE directives & requirements, cultural values - DOE/contractor interface - FACILITY OR PROJECT - Documented Safety

  13. Nuclear Safety | Department of Energy

    Office of Environmental Management (EM)

    Criticality Safety The Nuclear Facility Safety Program establishes and maintains the DOE requirements for nuclear criticality safety. The DOE detailed requirements for criticality ...

  14. Environment/Health/Safety (EHS)

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Safety Advisory Committee SAC Home Charter Sub-Committees Membership Minutes Annual Report ESH Peer Review Questions Welcome to the Safety Advisory Committee Web Site The Safety...

  15. Liquefied Natural Gas Safety Research

    Office of Environmental Management (EM)

    May 2012 Liquefied Natural Gas (LNG) Safety Research | Page 1 Liquefied Natural Gas Safety ... Energy | May 2012 Liquefied Natural Gas (LNG) Safety Research | Page i Message from the ...

  16. Environment, Safety and Health Assessments | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Environment, Safety and Health Assessments Environment, Safety and Health Assessments The Department of Energy's Office of Environment, Safety and Health Assessments, within the Office of Enterprise Assessments, is responsible for conducting assessments to provide information on programs and performance in protecting our workers, the public, and environment from hazards present at Department sites and operations. This information provides assurance to our stakeholders and identifies areas for

  17. Office of Nuclear Safety and Environmental Assessments | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Energy Nuclear Safety and Environmental Assessments Office of Nuclear Safety and Environmental Assessments MISSION The Office of Nuclear Safety and Environmental Assessments conducts assessments to provide critical feedback and objective information on programs and performance in protecting our workers, the public and environment from radiological hazards with a focus on hazardous nuclear facilities and operations.This information provides assurance to our stakeholders and identifies areas

  18. Radiation Safety Poster | Y-12 National Security Complex

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Radiation Safety Poster Radiation Safety Poster Radiation Safety Poster

  19. Safety analysis report for the Waste Storage Facility. Revision 2

    SciTech Connect (OSTI)

    Bengston, S.J.

    1994-05-01

    This safety analysis report outlines the safety concerns associated with the Waste Storage Facility located in the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The three main objectives of the report are: define and document a safety basis for the Waste Storage Facility activities; demonstrate how the activities will be carried out to adequately protect the workers, public, and environment; and provide a basis for review and acceptance of the identified risk that the managers, operators, and owners will assume.

  20. DOE Draft Standard, Development and Use of Probabilistic Risk Assessments

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    in Department of Energy Nuclear Safety Applications, 12/10 | Department of Energy DOE Draft Standard, Development and Use of Probabilistic Risk Assessments in Department of Energy Nuclear Safety Applications, 12/10 DOE Draft Standard, Development and Use of Probabilistic Risk Assessments in Department of Energy Nuclear Safety Applications, 12/10 The Department has taken several actions to provide an infrastructure for providing appropriate controls and support for use of risk assessments and

  1. Analysis of the safety and pharmacodynamics of human fibrinogen concentrate in animals

    SciTech Connect (OSTI)

    Beyerle, Andrea; Nolte, Marc W.; Solomon, Cristina; Herzog, Eva; Dickneite, Gerhard

    2014-10-01

    Fibrinogen, a soluble 340 kDa plasma glycoprotein, is critical in achieving and maintaining hemostasis. Reduced fibrinogen levels are associated with an increased risk of bleeding and recent research has investigated the efficacy of fibrinogen concentrate for controlling perioperative bleeding. European guidelines on the management of perioperative bleeding recommend the use of fibrinogen concentrate if significant bleeding is accompanied by plasma fibrinogen levels less than 1.5–2.0 g/l. Plasma-derived human fibrinogen concentrate has been available for therapeutic use since 1956. The overall aim of the comprehensive series of non-clinical investigations presented was to evaluate i) the pharmacodynamic and pharmacokinetic characteristics and ii) the safety and tolerability profile of human fibrinogen concentrate Haemocomplettan P® (RiaSTAP®). Pharmacodynamic characteristics were assessed in rabbits, pharmacokinetic parameters were determined in rabbits and rats and a safety pharmacology study was performed in beagle dogs. Additional toxicology tests included: single-dose toxicity tests in mice and rats; local tolerance tests in rabbits; and neoantigenicity tests in rabbits and guinea pigs following the introduction of pasteurization in the manufacturing process. Human fibrinogen concentrate was shown to be pharmacodynamically active in rabbits and dogs and well tolerated, with no adverse events and no influence on circulation, respiration or hematological parameters in rabbits, mice, rats and dogs. In these non-clinical investigations, human fibrinogen concentrate showed a good safety profile. This data adds to the safety information available to date, strengthening the current body of knowledge regarding this hemostatic agent. - Highlights: • A comprehensive series of pre-clinical investigations of human fibrinogen concentrate. • Human fibrinogen concentrate was shown to be pharmacodynamically active. • Human fibrinogen concentrate was well tolerated

  2. Managing a Process Safety Management inspection

    SciTech Connect (OSTI)

    Mulvey, N.P. [AcuTech Consulting, Inc., Princeton, NJ (United States)

    1995-12-31

    The Occupational Safety and Health Administration (OSHA) Process Safety Management (PSM) regulations (29 CFR {section} 1910.119) have been in effect for almost three years. State level risk management programs, in New Jersey, California, and Delaware have been in effect for over six years. More recently, Nevada and Louisiana have enacted process safety management programs. These regulations have had a significant impact on all phases of plant operations, including preliminary design, construction, startup, and operations. Through proper planning and the commitment of resources, many facilities are beginning to realize the benefits of well developed PSM programs. This paper will discuss in greater detail some of these benefits, and in particular, the subject of governmental inspections of facilities for process safety management programs.

  3. Safety Cinema: Safety Videos: Los Alamos National Laboratory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    linked in Search Safety CinemaTM VideosINDUSTRIAL HYGIENE AND SAFETY Safety Videos » Safety Cinema Safety Videos Home Safety Cinema Human Beings Beryllium Integrated Safety CONTACTS Occupational Safety and Health Division Office 505 606-0295 Video Contact Lorrie Bonds Lopez safetyvideos@lanl.gov 505 667-0216 Safety Cinema Play videos - download flyers and more Safety practices for work and home, supporting the well-being of every worker throughout each day. safety cinema logo "Let's take

  4. Hanford Site Safety Standards - Hanford Site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Hanford Site Safety Standards Documents Documents Hanford Site Cleanup Completion Framework Tri-Party Agreement Freedom of Information and Privacy Act Hanford Site Budget Hanford Site Safety Standards Hanford Hoisting and Rigging Manual DOE - ORP Contracts/Procurements DOE - RL Contracts/Procurements Integrated Waste Feed Delivery Plan Single-Shell Tank Evaluations Deep Vadose Zone 100-F RI/FS 100-D/H Operable Units RI/FS Sitewide Probabilistic Seismic Hazard Analysis Environmental Hanford Site

  5. Environment, Safety, and Health Reporting Manual

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2000-01-28

    This Manual provides detailed requirements to supplement DOE O 231.1, Environment, Safety and Health Reporting, which establishes management objectives and requirements for reporting environment, safety and health information. (Paragraphs 2a, 2a(1), 2a(2), 2b, 2b(1), 2b(2), and 2i(3)(a) through 2i(3)(d) of Chapter II, and Appendix A canceled by DOE N 231.1; Chapter IV canceled by DOE O 470.2A.)

  6. Electronic DOE Information Security System (eDISS) PIA, Office of Health

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Safety and Security | Department of Energy DOE Information Security System (eDISS) PIA, Office of Health Safety and Security Electronic DOE Information Security System (eDISS) PIA, Office of Health Safety and Security Electronic DOE Information Security System (eDISS) PIA, Office of Health Safety and Security Electronic DOE Information Security System (eDISS) PIA, Office of Health Safety and Security (88.14 KB) More Documents & Publications Integrated Safety Management Workshop

  7. DOE Draft Standard, Development and Use of Probabilistic Risk...

    Office of Environmental Management (EM)

    Draft Standard, Development and Use of Probabilistic Risk Assessments in Department of Energy Nuclear Safety Applications, 1210 DOE Draft Standard, Development and Use of ...

  8. Commentary: Risk Management and Reliability Design for Buildings

    SciTech Connect (OSTI)

    Berry, Dennis L.; Cranwell, Robert M.; Hunter, Regina L.

    1999-05-28

    Where there is a significant actuarial basis for decision making (e.g., the occurrence of fires in single-family dwellings), there is little incentive for formal risk management. Formal risk assessments are most useful in those cases where the value of the structure is high, many people may be affected, the societal perception of risk is high, consequences of a mishap would be severe, and the actuarial uncertainty is large. For these cases, there is little opportunity to obtain the necessary experiential data to make informed decisions, and the consequences in terms of money, lives, and societal confidence are severe enough to warrant a formal risk assessment. Other important factors include the symbolic value of the structure and vulnerability to single point failures. It is unlikely that formal risk management and assessment practices will or should replace the proven institutions of building codes and engineering practices. Nevertheless, formal risk assessment can provide valuable insights into the hazards threatening high-value and high-risk (perceived or actual) buildings and structures, which can in turn be translated into improved public health, safety, and security. The key is to choose and apply the right assessment tool to match the structure in question. Design-for-reliability concepts can be applied to buildings, bridges, transportation sys- tems, dams, and other structures. The use of these concepts could have the dual benefits of lowering life-cycle costs by reducing the necessity for maintenance and repair and of enhancing the saiiety and security of the structure's users.

  9. Hydrogen quantitative risk assessment workshop proceedings.

    SciTech Connect (OSTI)

    Groth, Katrina M.; Harris, Aaron P.

    2013-09-01

    The Quantitative Risk Assessment (QRA) Toolkit Introduction Workshop was held at Energetics on June 11-12. The workshop was co-hosted by Sandia National Laboratories (Sandia) and HySafe, the International Association for Hydrogen Safety. The objective of the workshop was twofold: (1) Present a hydrogen-specific methodology and toolkit (currently under development) for conducting QRA to support the development of codes and standards and safety assessments of hydrogen-fueled vehicles and fueling stations, and (2) Obtain feedback on the needs of early-stage users (hydrogen as well as potential leveraging for Compressed Natural Gas [CNG], and Liquefied Natural Gas [LNG]) and set priorities for %E2%80%9CVersion 1%E2%80%9D of the toolkit in the context of the commercial evolution of hydrogen fuel cell electric vehicles (FCEV). The workshop consisted of an introduction and three technical sessions: Risk Informed Development and Approach; CNG/LNG Applications; and Introduction of a Hydrogen Specific QRA Toolkit.

  10. Safety in urban environment and emergency notice boards

    SciTech Connect (OSTI)

    Confortini, Claudia; Tira, Maurizio

    2008-07-08

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

  11. ORISE: Crisis and Risk Communication

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    U.S. Department of Energy (DOE) Oak Ridge Office (ORO), ORISE provides crisis and risk communication support through the management of its Joint Information Center (JIC)...

  12. Nuclear Facility Risk Ranking | Department of Energy

    Broader source: Energy.gov (indexed) [DOE]

    risk-informed and balanced approach, the CNS performed a methodical assessment of the EM nuclear facilities. This risk-informed approach provides a data-driven foundation on which...

  13. Nuclear Facility Risk Ranking | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Facility Risk Ranking Nuclear Facility Risk Ranking Nuclear Facility Risk Ranking The CNS has purview of over ninety EM nuclear facilities across the DOE complex. To ensure that limited resources are applied in a risk-informed and balanced approach, the CNS performed a methodical assessment of the EM nuclear facilities. This risk-informed approach provides a data-driven foundation on which to construct a balanced set of operating plans and staff assignments. 2015 Risk Analysis Methodology.jpg

  14. Chemical Hygiene and Safety Plan

    SciTech Connect (OSTI)

    Berkner, K.

    1992-08-01

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

  15. Risk communication in environmental assessment

    SciTech Connect (OSTI)

    Rahm-Crites, L.

    1996-08-26

    Since the enactment of NEPA and other environmental legislation, the concept of `risk communication` has expanded from simply providing citizens with scientific information about risk to exploring ways of making risk information genuinely meaningful to the public and facilitating public involvement in the very processes whereby risk is analyzed and managed. Contemporary risk communication efforts attempt to find more effective ways of conveying increasingly complex risk information and to develop more democratic and proactive approaches to community involvement, in particular to ensuring the participation of diverse populations in risk decisions. Although considerable progress has been made in a relatively short time, risk communication researchers and practitioners currently face a number of challenges in a time of high expectations, low trust, and low budgets.

  16. Environmental Restoration Disposal Facility (Project W-296) Safety Assessment

    SciTech Connect (OSTI)

    Armstrong, D.L.

    1994-08-01

    This Safety Assessment is based on information derived from the Conceptual Design Report for the Environmental Restoration Disposal Facility (DOE/RL 1994) and ancillary documentation developed during the conceptual design phase of Project W-296. The Safety Assessment has been prepared to support the Solid Waste Burial Ground Interim Safety Basis document. The purpose of the Safety Assessment is to provide an evaluation of the design to determine if the process, as proposed, will comply with US Department of Energy (DOE) Limits for radioactive and hazardous material exposures and be acceptable from an overall health and safety standpoint. The evaluation considered affects on the worker, onsite personnel, the public, and the environment.

  17. Risk assessment and management of radiofrequency radiation exposure

    SciTech Connect (OSTI)

    Dabala, Dana; Surducan, Emanoil; Surducan, Vasile; Neamtu, Camelia

    2013-11-13

    Radiofrequency radiation (RFR) industry managers, occupational physicians, security department, and other practitioners must be advised on the basic of biophysics and the health effects of RF electromagnetic fields so as to guide the management of exposure. Information on biophysics of RFR and biological/heath effects is derived from standard texts, literature and clinical experiences. Emergency treatment and ongoing care is outlined, with clinical approach integrating the circumstances of exposure and the patient's symptoms. Experimental risk assessment model in RFR chronic exposure is proposed. Planning for assessment and monitoring exposure, ongoing care, safety measures and work protection are outlining the proper management.

  18. Information Security

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2007-06-29

    Establishes security requirements for the protection and control of information and matter required to be classified or controlled by statutes, regulations, or Department of Energy directives. Section E, Technical Surveillance Countermeasures Program, is Official Use Only. Please contact the DOE Office of Health, Safety and Security at 301-903-0292 if your official duties require you to have access to this part of the directive. Cancels: DOE M 471.2-1B, DOE M 471.2-1C, DOE M 471.2-4, and DOE O 471.2A

  19. Information Security

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2005-08-26

    This Manual establishes security requirements for the protection and control of information and matter required to be classified or controlled by statutes, regulations, or Department of Energy directives. Attachment E, Technical Surveillance Countermeasures Program, is for Official Use Only. Contact the Office of Security and Safety Performance Assurance at 301-903-3653 if your official duties require you to have access to this part of the directive. Cancels: DOE M 471.2-1B, DOE M 471.2-1C, DOE M 471.2-4, and DOE O 471.2A.

  20. Quantitative Risk Assessment

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Risk Assessment - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Energy Defense Waste Management Programs Advanced Nuclear

  1. Probabilistic Risk Assessment

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Risk Assessment - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Energy Defense Waste Management Programs Advanced Nuclear

  2. Security Risk Assessment

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Security Risk Assessment - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Energy Defense Waste Management Programs Advanced

  3. WIPP Documents - Nuclear Safety

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Nuclear Safety DOE/WIPP-07-3372, Revision 5b, WIPP Documented Safety Analysis Approved April 2016 The Documented Safety Analysis addresses all hazards (both radiological and nonradiological) and the controls necessary to provide adequate protection to the public, workers, and the environment. The WIPP DSA demonstrates the extent to which the Waste Isolation Pilot Plant can be operated safely with respect to workers, the public, and the environment. DOE/WIPP-07-3373, Revision 5b, WIPP Technical

  4. Integrated Safety Management Safety Culture Resources | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Energy Safety Culture Resources Integrated Safety Management Safety Culture Resources A collection of resources available in implementing ISM safety culture activities Safety from the Operator's Perspective: We are All in This Together (2005) Transcript, Keeping the Edge: Enhancing Performance Through Managing Culture (2003), Edgar H. Schein, Ph.D. Proceedings of the Advisory Committee on Reactor Safeguards Safety Culture Workshop (2003) Safety Culture in Nuclear Installations: Guidance for

  5. Analytic concepts for assessing risk as applied to human space flight

    SciTech Connect (OSTI)

    Garrick, B.J.

    1997-04-30

    Quantitative risk assessment (QRA) principles provide an effective framework for quantifying individual elements of risk, including the risk to astronauts and spacecraft of the radiation environment of space flight. The concept of QRA is based on a structured set of scenarios that could lead to different damage states initiated by either hardware failure, human error, or external events. In the context of a spacecraft risk assessment, radiation may be considered as an external event and analyzed in the same basic way as any other contributor to risk. It is possible to turn up the microscope on any particular contributor to risk and ask more detailed questions than might be necessary to simply assess safety. The methods of QRA allow for as much fine structure in the analysis as is desired. For the purpose of developing a basis for comprehensive risk management and considering the tendency to {open_quotes}fear anything nuclear,{close_quotes} radiation risk is a prime candidate for examination beyond that necessary to answer the basic question of risk. Thus, rather than considering only the customary damage states of fatalities or loss of a spacecraft, it is suggested that the full range of damage be analyzed to quantify radiation risk. Radiation dose levels in the form of a risk curve accomplish such a result. If the risk curve is the complementary cumulative distribution function, then it answers the extended question of what is the likelihood of receiving a specific dose of radiation or greater. Such results can be converted to specific health effects as desired. Knowing the full range of the radiation risk of a space mission and the contributors to that risk provides the information necessary to take risk management actions [operational, design, scheduling of missions around solar particle events (SPE), etc.] that clearly control radiation exposure.

  6. Unreviewed Safety Question Requirements

    Office of Environmental Management (EM)

    DOE G 424.1-1, Implementation Guide for Use in Addressing Unreviewed Safety Question Requirements Performance Objective 1: Contractor Program Documentation 1. The USQ ...

  7. Aviation Management and Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2011-06-15

    To establish a policy framework that will ensure safety, efficiency and effectiveness of government or contractor aviation operations. Cancels DOE O 440.2B.

  8. safety analysis report

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering ...

  9. safety of space

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering ...

  10. FEOSH Annual Safety Training

    Office of Energy Efficiency and Renewable Energy (EERE)

    The Department of Energy (DOE) has developed an annual safety training course that is mandatory for all current DOE Federal employees and for each new hire.

  11. Complete Safety Training

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    EHS 0470: General Employee Radiation Training (GERT) Special Training Required for Some Users Laser Safety Users working with a Class 3B4 laser EHS 0302 Macromolecular ...

  12. H. UNREVIEWED SAFETY QUESTIONS

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    3 Department of Energy Pt. 835 H. UNREVIEWED SAFETY QUESTIONS 1. The USQ process is an important tool to evaluate whether changes affect the safety basis. A contractor must use the USQ proc- ess to ensure that the safety basis for a DOE nuclear facility is not undermined by changes in the facility, the work performed, the associated hazards, or other factors that support the adequacy of the safety basis. 2. The USQ process permits a contractor to make physical and procedural changes to a nuclear

  13. Aviation Management and Safety

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2011-06-15

    To establish a policy framework that will ensure safety, efficiency and effectiveness of government or contractor aviation operations. Supersedes DOE O 440.2B.

  14. Coiled Tubing Safety Manual

    SciTech Connect (OSTI)

    Crow, W.

    1999-04-06

    This document addresses safety concerns regarding the use of coiled tubing as it pertains to the preservation of personnel, environment and the wellbore.

  15. SSRL Safety Office Memo

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    new regulations (NFPA70E) which outline the "Standard for Electrical Safety in the Workplace". Specifically it requires that the Arc Flash Hazard be categorized and PPE stated...

  16. Safety & Quality Assurance

    Broader source: Energy.gov [DOE]

    Together, our Facility Operations Division and Engineering, Safety and Quality Division work to ensure EM conducts its operations and cleanup safely through sound practices. These divisions ensure...

  17. DOE Explosives Safety Manual

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1996-03-29

    This Manual describes DOE's explosives safety requirements applicable to operations involving the development, testing, handling, and processing of explosives or assemblies containing explosives.

  18. Reactor Safety Research: Semiannual report, July-December 1986

    SciTech Connect (OSTI)

    Not Available

    1987-11-01

    Sandia National Laboratories is conducting, under USNRC sponsorship, phenomenological research related to the safety of commercial nuclear power reactors. The research includes experiments to simulate the phenomenology of the accident conditions and the development of analytical models, verified by experiment, which can be used to predict reactor and safety systems performance and behavior under abnormal conditions. The objective of this work is to provide NRC requisite data bases and analytical methods to (1) identify and define safety issues, (2) understand the progression of risk-significant accident sequences, and (3) conduct safety assessments. The collective NRC-sponsored effort at Sandia National Laboratories is directed at enhancing the tehcnology base supporting licensing decisions.

  19. Health Safety & Environmental Protection Committee Meeting Summaries -

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Hanford Site Hanford Advisory Board Committee Meeting Information Health Safety and Environ Hanford Advisory Board Convening Report SSAB Guidance Memorandum of Understanding Membership Nomination and Appointment Process Operating Ground Rules Calendars Advice and Responses Full Board Meeting Information Committee Meeting Information Outgoing Board Correspondence Key Board Products and Special Reports HAB Annual Report HAB and Committee Lists Points of Contact Related Links Health Safety

  20. Information Center | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Center Information Center The U.S. Department of Energy's (DOE) Office of Enterprise Assessments (EA) provides expert evaluations of management performance in safety, security and other areas by seasoned experts who are independent of line management. Information related to enforcement, safety, security, emergency management and cyber performance management is made available to the public in the EA Information Center. Enforcement Info Center The Department's Enforcement Office conducts

  1. Facility Safety | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Facility Safety Facility Safety In addition to establishing nuclear safety requirements related to safety management programs that are essential to the safety of DOE nuclear facilities, the U.S. Department of Energy's (DOE) Office of Nuclear Facility Safety works proactively with headquarters and field offices to foster continuous improvement and nuclear safety excellence. In addition, the Office provides high quality, customer-oriented assistance that enables improved DOE program and field

  2. Industrial Safety | The Ames Laboratory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Safety General Safety includes traditional safety disciplines such as machine guarding, personal protective equipment (PPE), electrical safety, accident prevention and investigation, building design and code review, fire safety, and Occupational Safety and Health Administration (OSHA) regulatory compliance. Safety's role is to protect the health and well-being of employees, visitors, and the public from hazards present at or created in the workplace. These factors may be present as a result of

  3. Risk assessment in the DOE Assurance Program for Remedial Action

    SciTech Connect (OSTI)

    Marks, S.; Cross, F.T.; Denham, D.H.; Kennedy, W.E.; Stenner, R.D.

    1985-08-01

    This document provides information obtained during the performance of risk assessment tasks in support of the Assurance Program for Remedial Action (APRA) sponsored by the Office of Operational Safety of the Department of Energy. We have presented a method for the estimation of projected health effects at properties in the vicinity of uranium mill tailing piles due to transported tailings or emissions from the piles. Because radon and radon daughter exposure is identified as the principal factor contributing to health effects at such properties, the basis for estimating lung cancer risk as a result of such exposure is discussed in detail. Modeling of health risk due to a secondary pathway, ingestion of contaminated, home-grown food products, is also discussed since it is a potentially important additional source of exposure in certain geographic locations. Risk assessment methods used in various mill tailings reports are reviewed. The protocols for radiological surveys conducted in DOE-sponsored remedial action programs are critically reviewed with respect to their relevance to the needs of health risk estimation. The relevance of risk assessment to the APRA program is discussed briefly.

  4. Quantitative risk of oil tanker groundings. Master`s thesis

    SciTech Connect (OSTI)

    Amrozowicz, M.D.

    1996-06-01

    The culture, design, and operation of the maritime industry all contribute to create an error-inducing system. As oil tankers have become larger, the tolerance for error has decreased as the consequences have increased. Tankers are the largest contributor by vessel type to worldwide oil spill volume. Human error has consistently been attributed to 80 percent of the marine accidents. A closer look reveals that many accidents attributed to human error are system errors. In fact, the term human error is unwarranted in many high-risk accidents and its use is a perforation of the context. The maritime industry has been identified as a high risk operation, requiring an active risk management program. A probabilistic risk assessment (PRA) provides a formal process of determining the full range of possible adverse occurrences, probabilities, and expected costs for any undesirable event. A PRA can identify those areas that offer the greatest risk-reducing potential. This thesis focuses on the first level of a proposed three-level risk model to determine the probability of a tanker grounding. The approach utilizes fault trees and event trees and incorporates The Human Error Rate Prediction data to quantify individual errors. The result allows the identification of high-leverage factors in order to determine the most effective and efficient use of resources to reduce the probability of grounding; showing that the development of the Electronic Chart Display and Information System incorporated with the International Safety Management Code can significantly reduce the probability of grounding.

  5. Validation and verification plan for safety and PRA codes. Revision 1

    SciTech Connect (OSTI)

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

    1991-04-01

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

  6. CRAD, Facility Safety- Nuclear Facility Safety Basis

    Office of Energy Efficiency and Renewable Energy (EERE)

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) that can be used for assessment of a contractor's Nuclear Facility Safety Basis.

  7. CRAD, Facility Safety- Technical Safety Requirements

    Office of Energy Efficiency and Renewable Energy (EERE)

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) that can be used for assessment of a contractor's Technical Safety Requirments (TSA).

  8. CRAD, Facility Safety- Documented Safety Analysis

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) that can be used for assessment of a contractor's Documented Safety Analysis.

  9. Nuclear Explosive Safety Study Process

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    3015-2001 February 2001 Superseding DOE-STD-3015-97 January 1997 DOE STANDARD NUCLEAR EXPLOSIVE SAFETY STUDY PROCESS U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from

  10. Integrated Safety Management Policy

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2011-04-25

    The policy establishes DOE's expectation for safety, including integrated safety management that will enable the Department’s mission goals to be accomplished efficiently while ensuring safe operations at all departmental facilities and activities. Supersedes DOE P 450.4, DOE P 411.1, DOE P 441.1, DOE P 450.2A, and DOE P 450.7

  11. Fire Safety Committee

    Broader source: Energy.gov [DOE]

    The purpose of the Department of Energy /National Nuclear Security Administration (DOE) Fire Safety Committee is to provide a forum to facilitate the interaction between the DOE, its program offices and contractor personnel with common interests regarding the identification and resolution of fire safety-related issues including the development of appropriate fire protection Orders, Guides, and Technical Standards.

  12. The color of safety

    SciTech Connect (OSTI)

    Carter, R.A.

    2006-06-15

    The industry's workforce is getting grayer as veteran miners approach retirement, and greener as new hires come onboard. Will the changing complexion of the industry affect future safety technology? The article discusses problems of noise, vibration, and communication faced by coal miners and reports some developments by manufacturers of mining equipment to improve health and safety. 1 fig., 4 photos.

  13. Safety of Accelerator Facilities

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2001-01-08

    To establish accelerator-specific safety requirements which, when supplemented by other applicable safety and health requirements, will serve to prevent injuries and illnesses associated with Department of Energy (DOE) or National Nuclear Security Administration (NNSA) accelerator operations. Cancels DOE O 420.2. Canceled by DOE O 420.2B.

  14. Safety of Accelerator Facilities

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2004-07-23

    To establish accelerator-specific safety requirements which, when supplemented by other applicable safety and health requirements, will serve to prevent injuries and illnesses associated with Department of Energy (DOE) or National Nuclear Security Administration (NNSA) accelerator operations. Cancels DOE O 420.2A. Certified 5-13-08. Canceled by DOE O 420.2C.

  15. Safety of Accelerator Facilities

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2011-07-21

    The order defines accelerators and establishes accelerator specific safety requirements and approval authorities which, when supplemented by other applicable safety and health requirements, promote safe operations to ensure protection of workers, the public, and the environment. Supersedes DOE O 420.2B.

  16. Geographic information system for Long Island: An epidemiologic systems approach to identify environmental breast cancer risks on Long Island. Phase 1

    SciTech Connect (OSTI)

    Barancik, J.I.; Kramer, C.F.; Thode, H.C. Jr.

    1995-12-01

    BNL is developing and implementing the project ``Geographic Information System (GIS) for Long Island`` to address the potential relationship of environmental and occupational exposures to breast cancer etiology on Long Island. The project is divided into two major phases: The four month-feasibility project (Phase 1), and the major development and implementation project (Phase 2). This report summarizes the work completed in the four month Phase 1 Project, ``Feasibility of a Geographic Information System for Long Island.`` It provides the baseline information needed to further define and prioritize the scope of work for subsequent tasks. Phase 2 will build upon this foundation to develop an operational GIS for the Long Island Breast Cancer Study Project (LIBCSP).

  17. Risk management study for the retired Hanford Site facilities: Qualitative risk evaluation for the retired Hanford Site facilities. Volume 3

    SciTech Connect (OSTI)

    Coles, G.A.; Shultz, M.V.; Taylor, W.E.

    1993-09-01

    This document provides a risk evaluation of the 100 and 200 Area retired, surplus facilities on the Hanford Site. Also included are the related data that were compiled by the risk evaluation team during investigations performed on the facilities. Results are the product of a major effort performed in fiscal year 1993 to produce qualitative information that characterizes certain risks associated with these facilities. The retired facilities investigated for this evaluation are located in the 100 and 200 Areas of the 1,450-km{sup 2} (570-mi{sup 2}) Hanford Site. The Hanford Site is a semiarid tract of land in southeastern Washington State. The nearest population center is Richland, Washington, (population 32,000) 30-km (20 mi) southeast of the 200 Area. During walkdown investigations of these facilities, data on real and potential hazards that threatened human health or safety or created potential environmental release issues were identified by the risk evaluation team. Using these findings, the team categorized the identified hazards by facility and evaluated the risk associated with each hazard. The factors contributing to each risk, and the consequence and likelihood of harm associated with each hazard also are included in this evaluation.

  18. Office of Safety Infrastructure & Operations | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration Safety Infrastructure & Operations NNSA's G2 Management Information System Wins Association for Enterprise Information's (AFEI) "Excellence in Enterprise Information Award" The G2 team and the 2015 Association for Enterprise Information's (AFEI) Excellence in Enterprise Information Award. (WASHINGTON, D.C) - The National Nuclear Security Administration (NNSA) has received the 2015 Association for Enterprise Information's (AFEI) Excellence in Enterprise

  19. K Basin safety analysis

    SciTech Connect (OSTI)

    Porten, D.R.; Crowe, R.D.

    1994-12-16

    The purpose of this accident safety analysis is to document in detail, analyses whose results were reported in summary form in the K Basins Safety Analysis Report WHC-SD-SNF-SAR-001. The safety analysis addressed the potential for release of radioactive and non-radioactive hazardous material located in the K Basins and their supporting facilities. The safety analysis covers the hazards associated with normal K Basin fuel storage and handling operations, fuel encapsulation, sludge encapsulation, and canister clean-up and disposal. After a review of the Criticality Safety Evaluation of the K Basin activities, the following postulated events were evaluated: Crane failure and casks dropped into loadout pit; Design basis earthquake; Hypothetical loss of basin water accident analysis; Combustion of uranium fuel following dryout; Crane failure and cask dropped onto floor of transfer area; Spent ion exchange shipment for burial; Hydrogen deflagration in ion exchange modules and filters; Release of Chlorine; Power availability and reliability; and Ashfall.

  20. Sociocultural definitions of risk

    SciTech Connect (OSTI)

    Rayner, S.

    1990-10-01

    Public constituencies frequently are criticized by technical experts as being irrational in response to low-probability risks. This presentation argued that most people are concerned with a variety of risk attributes other than probability and that is rather irrational to exclude these from the definition and analysis of technological risk. Risk communication, which is at the heart of the right-to-know concept, is described as the creation of shared meaning rather than the mere transmission of information. A case study of utilities, public utility commissions, and public interest groups illustrates how the diversity of institutional cultures in modern society leads to problems for the creation of shared meanings in establishing trust, distributing liability, and obtaining consent to risk. This holistic approach to risk analysis is most appropriate under conditions of high uncertainty and/or decision stakes. 1 fig., 5 tabs.

  1. Mixed Waste Management Facility Preliminary Safety Analysis Report. Chapters 1 to 20

    SciTech Connect (OSTI)

    Not Available

    1994-09-01

    This document provides information on waste management practices, occupational safety, and a site characterization of the Lawrence Livermore National Laboratory. A facility description, safety engineering analysis, mixed waste processing techniques, and auxiliary support systems are included.

  2. Ordering Information | U.S. DOE Office of Science (SC)

    Office of Science (SC) Website

    Ordering Information NBL Program Office NBL PO Home About Programs Certified Reference Materials (CRMs) Prices and Certificates Ordering Information NEPA Documents News Safety Data ...

  3. SEISMIC ANALYSIS FOR PRECLOSURE SAFETY

    SciTech Connect (OSTI)

    E.N. Lindner

    2004-12-03

    The purpose of this seismic preclosure safety analysis is to identify the potential seismically-initiated event sequences associated with preclosure operations of the repository at Yucca Mountain and assign appropriate design bases to provide assurance of achieving the performance objectives specified in the Code of Federal Regulations (CFR) 10 CFR Part 63 for radiological consequences. This seismic preclosure safety analysis is performed in support of the License Application for the Yucca Mountain Project. In more detail, this analysis identifies the systems, structures, and components (SSCs) that are subject to seismic design bases. This analysis assigns one of two design basis ground motion (DBGM) levels, DBGM-1 or DBGM-2, to SSCs important to safety (ITS) that are credited in the prevention or mitigation of seismically-initiated event sequences. An application of seismic margins approach is also demonstrated for SSCs assigned to DBGM-2 by showing a high confidence of a low probability of failure at a higher ground acceleration value, termed a beyond-design basis ground motion (BDBGM) level. The objective of this analysis is to meet the performance requirements of 10 CFR 63.111(a) and 10 CFR 63.111(b) for offsite and worker doses. The results of this calculation are used as inputs to the following: (1) A classification analysis of SSCs ITS by identifying potential seismically-initiated failures (loss of safety function) that could lead to undesired consequences; (2) An assignment of either DBGM-1 or DBGM-2 to each SSC ITS credited in the prevention or mitigation of a seismically-initiated event sequence; and (3) A nuclear safety design basis report that will state the seismic design requirements that are credited in this analysis. The present analysis reflects the design information available as of October 2004 and is considered preliminary. The evolving design of the repository will be re-evaluated periodically to ensure that seismic hazards are properly

  4. 2011 Annual Criticality Safety Program Performance Summary

    SciTech Connect (OSTI)

    Andrea Hoffman

    2011-12-01

    The 2011 review of the INL Criticality Safety Program has determined that the program is robust and effective. The review was prepared for, and fulfills Contract Data Requirements List (CDRL) item H.20, 'Annual Criticality Safety Program performance summary that includes the status of assessments, issues, corrective actions, infractions, requirements management, training, and programmatic support.' This performance summary addresses the status of these important elements of the INL Criticality Safety Program. Assessments - Assessments in 2011 were planned and scheduled. The scheduled assessments included a Criticality Safety Program Effectiveness Review, Criticality Control Area Inspections, a Protection of Controlled Unclassified Information Inspection, an Assessment of Criticality Safety SQA, and this management assessment of the Criticality Safety Program. All of the assessments were completed with the exception of the 'Effectiveness Review' for SSPSF, which was delayed due to emerging work. Although minor issues were identified in the assessments, no issues or combination of issues indicated that the INL Criticality Safety Program was ineffective. The identification of issues demonstrates the importance of an assessment program to the overall health and effectiveness of the INL Criticality Safety Program. Issues and Corrective Actions - There are relatively few criticality safety related issues in the Laboratory ICAMS system. Most were identified by Criticality Safety Program assessments. No issues indicate ineffectiveness in the INL Criticality Safety Program. All of the issues are being worked and there are no imminent criticality concerns. Infractions - There was one criticality safety related violation in 2011. On January 18, 2011, it was discovered that a fuel plate bundle in the Nuclear Materials Inspection and Storage (NMIS) facility exceeded the fissionable mass limit, resulting in a technical safety requirement (TSR) violation. The TSR limits fuel

  5. Remedial investigation/feasibility study of the Clinch River/Poplar Creek Operable Unit. Volume 3. Risk assessment information. Appendixes E, F

    SciTech Connect (OSTI)

    1996-03-01

    This report presents the findings of an investigation into contamination of the Clinch River and Poplar Creek near the U.S. Department of Energy`s (DOE`s) Oak Ridge Reservation (ORR) in eastern Tennessee. For more than 50 years, various hazardous and radioactive substances have been released to the environment as a result of operations and waste management activities at the ORR. In 1989, the ORR was placed on the National Priorities List (NPL), established and maintained under the federal Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Under CERCLA, NPL sites must be investigated to determine the nature and extent of contamination at the site, assess the risk to human health and the environment posed by the site, and, if necessary, identify feasible remedial alternatives that could be used to clean the site and reduce risk. To facilitate the overall environmental restoration effort at the ORR, CERCLA activities are being implemented individually as distinct operable units (OUs). This document is Volume 3 of the combined Remedial Investigation and Feasibility Study Report for the Clinch River/Poplar Creek OU.

  6. Remedial investigation/feasibility study of the Clinch River/Poplar Creek operable unit. Volume 3: Appendixes E and F -- Risk assessment information

    SciTech Connect (OSTI)

    1996-06-01

    This report presents the findings of an investigation into contamination of the Clinch River and Poplar Creek near the US Department of Energy`s (DOE`s) Oak Ridge Reservation (ORR) in eastern Tennessee. For more than 50 years, various hazardous and radioactive substances have been released to the environment as a result of operations and waste management activities at the ORR. In 1989, the ORR was placed on the National Priorities List (NPL), established and maintained under the federal Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Under CERCLA, NPL sites must be investigated to determine the nature and extent of contamination at the site, assess the risk to human health and the environment posed by the site, and, if necessary, identify feasible remedial alternatives that could be used to clean the site and reduce risk. To facilitate the overall environmental restoration effort at the ORR, CERCLA activities are being implemented individually as distinct operable units (OUs). This document is the combined Remedial Investigation and Feasibility Study Report for the Clinch River/Poplar Creek OU.

  7. User Safety | U.S. DOE Office of Science (SC)

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    User Safety User Facilities User Facilities Home User Facilities at a Glance User Resources Getting Started User Safety Access Models User Agreements Data Management Resources Acknowledging User Facilities User Statistics Policies and Processes Frequently Asked Questions User Facility Science Highlights User Facility News Contact Information Office of Science U.S. Department of Energy 1000 Independence Ave., SW Washington, DC 20585 P: (202) 586-5430 User Resources User Safety Print Text Size: A

  8. Health risks in perspective: Judging health risks of energy technologies

    SciTech Connect (OSTI)

    Rowe, M.D.

    1992-09-18

    Almost daily, Americans receive reports from the mass news media about some new and frightening risk to health and welfare. Most such reports emphasize the newsworthiness of the risks -- the possibility of a crisis, disagreements among experts, how things happened, who is responsible for fixing them, how much will it cost, conflict among parties involved, etc. As a rule, the magnitudes of the risks, or the difficulty of estimating those magnitudes, have limited newsworthiness, and so they are not mentioned. Because of this emphasis in the news media, most people outside the risk assessment community must judge the relative significance of the various risks to which we all are exposed with only that information deemed newsworthy by reporters. This information is biased and shows risks in isolation. There is no basis for understanding and comparing the relative importance of risks among themselves, or for comparing one risk, perhaps a new or newly-discovered one, in the field of all risks. The purpose of this report is to provide perspective on the various risks to which we are routinely exposed. It serves as a basis for understanding the meaning of quantitative risk estimates and for comparing new or newly-discovered risks with other, better-understood risks. Specific emphasis is placed on health risks of energy technologies.

  9. Program Information | National Nuclear Security Administration...

    National Nuclear Security Administration (NNSA)

    Program Information FY 2015 Performance Evaluation Plan (PEP) FY 2013 Performance ... Description and Worker Safety and Health Program 2015 Small Business Program (FY 2009 - ...

  10. Site Information | National Nuclear Security Administration | (NNSA)

    National Nuclear Security Administration (NNSA)

    Site Information Facilities & Projects Nuclear Operations Environment, Safety & Health Safeguards & Security Performance & Quality Assurance Programs NEPA Reading Room

  11. Safety and Security Policy (SSP) Homepage | U.S. DOE Office of Science (SC)

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Health Safety and Health Office of Industrial Hygiene and Safety Information for Department of Energy Headquarters Personnel Our mission is to promote and coordinate safety and health for DOE Headquarters property (facilities) in addition to oversight of building operations, lease/project/space management, and support services for DOE Headquarters buildings. The Office of Industrial Hygiene and Safety provides information, guidelines, documentation, training, and materials pertaining to many

  12. Generic Deep Geologic Disposal Safety Case

    Broader source: Energy.gov [DOE]

    The Generic Deep Geologic Disposal Safety Case presents generic information that is of use in understanding potential deep geologic disposal options (e.g., salt, shale, granite, deep borehole) in the U.S. for used nuclear fuel (UNF) from reactors and high-level radioactive waste (HLW).

  13. EM Health and Safety Plan Guidelines

    SciTech Connect (OSTI)

    Not Available

    1994-12-01

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

  14. Safety and Security Enforcement Coordinator Handbook

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    SAFETY AND SECURITY ENFORCEMENT COORDINATOR HANDBOOK APRIL 2015 Office of Enforcement Office of Enterprise Assessments U.S. Department of Energy Table of Contents Ensure use of the current version of this document by checking the Office of Enterprise Assessments website at: http://energy.gov/ea/services/enforcement/enforcement-program-and- process-guidance-and-information Acronyms

  15. Rooftop Solar PV & Firefighter Safety

    Broader source: Energy.gov [DOE]

    Solar photovoltaic (PV) installations have experienced significant growth in recent years. Due to technological innovations and cost reductions, solar energy is a viable option for an increasing number of residences and businesses across the United States. Rooftop solar is considered safe – to date there has been no documented case of death from the electric shock, chemical burn or conventional fire caused by a solar panel; however, as more buildings install rooftop solar systems, the likelihood increases that fires will occur on buildings with solar, making it critical for firefighters to receive comprehensive solar education and training. This SolarOPs fact sheet gives a brief overview of typical solar PV installations, addresses the major hazards and risks to firefighters, discusses fire safety in Germany (the country with the most installed solar PV per capita), and suggests recommendations and resources to ensure that first responders are prepared to fight fires on homes and buildings with rooftop solar PV.

  16. Safety shutdown separators

    DOE Patents [OSTI]

    Carlson, Steven Allen; Anakor, Ifenna Kingsley; Farrell, Greg Robert

    2015-06-30

    The present invention pertains to electrochemical cells which comprise (a) an anode; (b) a cathode; (c) a solid porous separator, such as a polyolefin, xerogel, or inorganic oxide separator; and (d) a nonaqueous electrolyte, wherein the separator comprises a porous membrane having a microporous coating comprising polymer particles which have not coalesced to form a continuous film. This microporous coating on the separator acts as a safety shutdown layer that rapidly increases the internal resistivity and shuts the cell down upon heating to an elevated temperature, such as 110.degree. C. Also provided are methods for increasing the safety of an electrochemical cell by utilizing such separators with a safety shutdown layer.

  17. Complete Experiment Safety Documentation

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Complete Experiment Safety Documentation Print User Safety Overview Upon receiving beam time: 1. Log in to ALSHub to complete an Experiment Safety Sheet (ESS). The ALS This e-mail address is being protected from spambots. You need JavaScript enabled to view it is available to support you through this process. Please contact This e-mail address is being protected from spambots. You need JavaScript enabled to view it at the email link or at (510) 486-7222 at if you have questions or need more

  18. Complete Experiment Safety Documentation

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Complete Experiment Safety Documentation Print User Safety Overview Upon receiving beam time: 1. Log in to ALSHub to complete an Experiment Safety Sheet (ESS). The ALS This e-mail address is being protected from spambots. You need JavaScript enabled to view it is available to support you through this process. Please contact This e-mail address is being protected from spambots. You need JavaScript enabled to view it at the email link or at (510) 486-7222 at if you have questions or need more

  19. Complete Experiment Safety Documentation

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Complete Experiment Safety Documentation Print User Safety Overview Upon receiving beam time: 1. Log in to ALSHub to complete an Experiment Safety Sheet (ESS). The ALS This e-mail address is being protected from spambots. You need JavaScript enabled to view it is available to support you through this process. Please contact This e-mail address is being protected from spambots. You need JavaScript enabled to view it at the email link or at (510) 486-7222 at if you have questions or need more

  20. Complete Experiment Safety Documentation

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Complete Experiment Safety Documentation Print User Safety Overview Upon receiving beam time: 1. Log in to ALSHub to complete an Experiment Safety Sheet (ESS). The ALS This e-mail address is being protected from spambots. You need JavaScript enabled to view it is available to support you through this process. Please contact This e-mail address is being protected from spambots. You need JavaScript enabled to view it at the email link or at (510) 486-7222 at if you have questions or need more