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Sample records for informed safety margin

  1. 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.

  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 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

  5. 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

  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. 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.

  8. 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.

  9. 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.

  10. 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.

  11. 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

  12. 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.

  13. 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.

  14. 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.

  15. 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.

  16. 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

  17. 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

  18. 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

  19. 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

  20. Workshop on Program for Elimination of Requirements Marginal to Safety: Proceedings

    SciTech Connect (OSTI)

    Dey, M.; Arsenault, F.; Patterson, M.; Gaal, M.

    1993-09-01

    These are the proceedings of the Public Workshop on the US Nuclear Regulatory Commission`s Program for Elimination of Requirements Marginal to Safety. The workshop was held at the Holiday Inn, Bethesda, on April 27 and 28, 1993. The purpose of the workshop was to provide an opportunity for public and industry input to the program. The workshop addressed the institutionalization of the program to review regulations with the purpose of eliminating those that are marginal. The objective is to avoid the dilution of safety efforts. One session was devoted to discussion of the framework for a performance-based regulatory approach. In addition, panelists and attendees discussed scope, schedules and status of specific regulatory items: containment leakage testing requirements, fire protection requirements, requirements for environmental qualification of electrical equipment, requests for information under 10CFR50.54(f), requirements for combustible gas control systems, and quality assurance requirements.

  1. Margin of Safety Definition and Examples Used in Safety Basis Documents and the USQ Process

    SciTech Connect (OSTI)

    Beaulieu, R. A.

    2013-10-03

    The Nuclear Safety Management final rule, 10 CFR 830, provides an undefined term, margin of safety (MOS). Safe harbors listed in 10 CFR 830, Table 2, such as DOE-STD-3009 use but do not define the term. This lack of definition has created the need for the definition. This paper provides a definition of MOS and documents examples of MOS as applied in a U.S. Department of Energy (DOE) approved safety basis for an existing nuclear facility. If we understand what MOS looks like regarding Technical Safety Requirements (TSR) parameters, then it helps us compare against other parameters that do not involve a MOS. This paper also documents parameters that are not MOS. These criteria could be used to determine if an MOS exists in safety basis documents. This paper helps DOE, including the National Nuclear Security Administration (NNSA) and its contractors responsible for the safety basis improve safety basis documents and the unreviewed safety question (USQ) process with respect to MOS.

  2. 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

  3. Estimation of Inherent Safety Margins in Loaded Commercial Spent Nuclear Fuel Casks

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Banerjee, Kaushik; Robb, Kevin R.; Radulescu, Georgeta; Scaglione, John M.

    2016-06-15

    We completed a novel assessment to determine the unquantified and uncredited safety margins (i.e., the difference between the licensing basis and as-loaded calculations) available in as-loaded spent nuclear fuel (SNF) casks. This assessment was performed as part of a broader effort to assess issues and uncertainties related to the continued safety of casks during extended storage and transportability following extended storage periods. Detailed analyses crediting the actual as-loaded cask inventory were performed for each of the casks at three decommissioned pressurized water reactor (PWR) sites to determine their characteristics relative to regulatory safety criteria for criticality, thermal, and shielding performance.more » These detailed analyses were performed in an automated fashion by employing a comprehensive and integrated data and analysis tool—Used Nuclear Fuel-Storage, Transportation & Disposal Analysis Resource and Data System (UNF-ST&DARDS). Calculated uncredited criticality margins from 0.07 to almost 0.30 Δkeff were observed; calculated decay heat margins ranged from 4 to almost 22 kW (as of 2014); and significant uncredited transportation dose rate margins were also observed. The results demonstrate that, at least for the casks analyzed here, significant uncredited safety margins are available that could potentially be used to compensate for SNF assembly and canister structural performance related uncertainties associated with long-term storage and subsequent transportation. The results also suggest that these inherent margins associated with how casks are loaded could support future changes in cask licensing to directly or indirectly credit the margins. Work continues to quantify the uncredited safety margins in the SNF casks loaded at other nuclear reactor sites.« less

  4. Intrusion Margins and Associated Fractures | Open Energy Information

    Open Energy Info (EERE)

    Rim Margins Lithologically Controlled Fractures caused by igneous activity creates permeability, allowing water to circulate deep beneath the surface thus becoming heated in the...

  5. 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 ...

  6. Seismic Safety Margins Research Program (Phase I). Project IV. Structural building response; Structural Building Response Review

    SciTech Connect (OSTI)

    Healey, J.J.; Wu, S.T.; Murga, M.

    1980-02-01

    As part of the Phase I effort of the Seismic Safety Margins Research Program (SSMRP) being performed by the University of California Lawrence Livermore Laboratory for the US Nuclear Regulatory Commission, the basic objective of Subtask IV.1 (Structural Building Response Review) is to review and summarize current methods and data pertaining to seismic response calculations particularly as they relate to the objectives of the SSMRP. This material forms one component in the development of the overall computational methodology involving state of the art computations including explicit consideration of uncertainty and aimed at ultimately deriving estimates of the probability of radioactive releases due to seismic effects on nuclear power plant facilities.

  7. 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)

  8. Handbook of nuclear power plant seismic fragilities, Seismic Safety Margins Research Program

    SciTech Connect (OSTI)

    Cover, L.E.; Bohn, M.P.; Campbell, R.D.; Wesley, D.A.

    1983-12-01

    The Seismic Safety Margins Research Program (SSMRP) has a gola to develop a complete fully coupled analysis procedure (including methods and computer codes) for estimating the risk of an earthquake-induced radioactive release from a commercial nuclear power plant. As part of this program, calculations of the seismic risk from a typical commercial nuclear reactor were made. These calculations required a knowledge of the probability of failure (fragility) of safety-related components in the reactor system which actively participate in the hypothesized accident scenarios. This report describes the development of the required fragility relations and the data sources and data reduction techniques upon which they are based. Both building and component fragilities are covered. The building fragilities are for the Zion Unit 1 reactor which was the specific plant used for development of methodology in the program. Some of the component fragilities are site-specific also, but most would be usable for other sites as well.

  9. 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

  10. 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

  11. 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.

  12. 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.

  13. 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...

  14. 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...

  15. 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.

  16. 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 ...

  17. Seismic safety margins research program. Phase I. Final report: plant/site selection and data collection (Project I)

    SciTech Connect (OSTI)

    Chuang, T. Y.

    1981-05-01

    Project I of Phase I of the Seismic Safety Margins Research Program (SSMRP) comprised two parts: the selection of a representative nuclear power plant/site for study in Phase I and the collection of data needed by the other SSMRP projects. Unit 1 of the Zion Nuclear Power Plant in Zion, Illinois, was selected for the SSMRP Phase I studies. The Zion plant and its site were found to be reasonably representative of operating and future plants with regard to its nuclear steam supply system; the type of containment structure (prestressed concrete); its electrical capacity (1100 MWe); its location (the Midwest); the peak seismic accelaration used for design (0.17g); and the properties of the underlying soil (the low-strain shear-wave velocity is 1650 ft/s in a 50- to 100-ft-thick layer of soil overlying sedimentary bedrock).

  18. 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...

  19. 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...

  20. 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.

  1. 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.

  2. 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

  3. 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.

  4. 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.

  5. 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 ...

  6. 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...

  7. 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...

  8. MNSR transient analyses and thermal hydraulic safety margins for HEU and LEU cores using the RELAP5-3D code

    SciTech Connect (OSTI)

    Dunn, F.E.; Thomas, J.; Liaw, J.; Matos, J.E.

    2008-07-15

    For safety analyses to support conversion of MNSR reactors from HEU fuel to LEU fuel, a RELAP5-3D model was set up to simulate the entire MNSR system. This model includes the core, the beryllium reflectors, the water in the tank and the water in the surrounding pool. The MCNP code was used to obtain the power distributions in the core and to obtain reactivity feedback coefficients for the transient analyses. The RELAP5-3D model was validated by comparing measured and calculated data for the NIRR-1 reactor in Nigeria. Comparisons include normal operation at constant power and a 3.77 mk rod withdrawal transient. Excellent agreement was obtained for core coolant inlet and outlet temperatures for operation at constant power, and for power level, coolant inlet temperature, and coolant outlet temperature for the rod withdrawal transient. In addition to the negative reactivity feedbacks from increasing core moderator and fuel temperatures, it was necessary to calculate and include positive reactivity feedback from temperature changes in the radial beryllium reflector and changes in the temperature and density of the water in the tank above the core and at the side of the core. The validated RELAP5-3D model was then used to analyze 3.77 mk rod withdrawal transients for LEU cores with two UO{sub 2} fuel pin designs. The impact of cracking of oxide LEU fuel is discussed. In addition, steady-state power operation at elevated power levels was evaluated to determine steady-state safety margins for onset of nucleate boiling and for onset of significant voiding. (author)

  9. 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.

  10. 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.

  11. 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 ...

  12. seismic margin

    Office of Scientific and Technical Information (OSTI)

    ... event tree SMA seismic margins analysis SNF spent nuclear fuel SRTC site rail transfer cart SSC ... Safeguards and Security System Safeguards and Security Entire NA NA NA NA System ...

  13. 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

  14. 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.

  15. 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.

  16. 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

  17. 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...

  18. 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 ...

  19. 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.

  20. 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.

  1. 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.''

  2. 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

  3. 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.

  4. 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).

  5. 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.

  6. 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.

  7. Seismic Safety Margins Research Program, Phase I. Project II: seismic input. Compilation, assessment and expansion of the strong earthquake ground motion data base

    SciTech Connect (OSTI)

    Crouse, C B; Hileman, J A; Turner, B E; Martin, G R

    1980-04-01

    A catalog has been prepared which contains information for: (1) world-wide, ground-motion accelerograms, (2) the accelerograph sites where these records were obtained, and (3) the seismological parameters of the causative earthquakes. The catalog is limited to data for those accelerograms which have been digitized and published. In addition, the quality and completeness of these data are assessed. This catalog is unique because it is the only publication which contains comprehensive information on the recording conditions of all known digitized accelerograms. However, information for many accelerograms is missing. Although some literature may have been overlooked, most of the missing data has not been published. Nevertheless, the catalog provides a convenient reference and useful tool for earthquake engineering research and applications.

  8. 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.

  9. 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.

  10. 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

  11. 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.

  12. 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.

  13. 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.

  14. 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.

  15. 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.

  16. 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)

  17. 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...

  18. 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...

  19. 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.

  20. 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.

  1. 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.

  2. 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

  3. 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.

  4. 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...

  5. 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.

  6. 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.

  7. 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.'

  8. 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.

  9. 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 ...

  10. 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.

  11. Marginal Energy Prices - RECS97 Update

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

    Marginal Energy Prices - RECS97 Update The original estimation of residential marginal energy prices at the individual household level (as reported in the Marginal Energy Prices ...

  12. 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.

  13. 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).

  14. 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.

  15. Caldera Rim Margins | Open Energy Information

    Open Energy Info (EERE)

    Tectonics Mississippian-Pennsylvanian; Pleistocene, 1.6 to 1.25 Ma Limestone-Madera Formation "MIPu"; Rhyolitic tuff-Intracaldera Bandelier Tuff (upper Tshirege "Qbt" and...

  16. 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

  17. 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

  18. Neutronics and safety characteristics of a 100% MOX fueled PWR using weapons grade plutonium

    SciTech Connect (OSTI)

    Biswas, D.; Rathbun, R.; Lee, Si Young; Rosenthal, P.

    1993-12-31

    Preliminary neutronics and safety studies, pertaining to the feasibility of using 100% weapons grade mixed-oxide (MOX) fuel in an advanced PWR Westinghouse design are presented in this paper. The preliminary results include information on boron concentration, power distribution, reactivity coefficients and xenon and control rode worth for the initial and the equilibrium cycle. Important safety issues related to rod ejection and steam line break accidents and shutdown margin requirements are also discussed. No significant change from the commercial design is needed to denature weapons-grade plutonium under the current safety and licensing criteria.

  19. 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) ...

  20. 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.

  1. 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...

  2. 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.

  3. 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.

  4. Steel Industry Marginal Opportunity Analysis

    SciTech Connect (OSTI)

    none,

    2005-09-01

    The Steel Industry Marginal Opportunity Analysis (PDF347 KB) identifies opportunities for developing advanced technologies and estimates both the necessary funding and the potential payoff. This analysis determines what portion of the energy bandwidth can be captured through the adoption of state-of-the-art technology and practices. R&D opportunities for addressing the remainder of the bandwidth are characterized and plotted on a marginal opportunity curve.

  5. 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.

  6. 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.

  7. 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 ...

  8. 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. ...

  9. 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

  10. SU-E-T-573: The Robustness of a Combined Margin Recipe for Uncertainties During Radiotherapy

    SciTech Connect (OSTI)

    Stroom, J; Vieira, S; Greco, C [Champalimaud Foundation, Lisbon, Lisbon (Portugal)

    2014-06-01

    Purpose: To investigate the variability of a safety margin recipe that combines CTV and PTV margins quadratically, with several tumor, treatment, and user related factors. Methods: Margin recipes were calculated by monte-carlo simulations in 5 steps. 1. A spherical tumor with or without isotropic microscopic was irradiated with a 5 field dose plan2. PTV: Geometric uncertainties were introduced using systematic (Sgeo) and random (sgeo) standard deviations. CTV: Microscopic disease distribution was modelled by semi-gaussian (Smicro) with varying number of islets (Ni)3. For a specific uncertainty set (Sgeo, sgeo, Smicro(Ni)), margins were varied until pre-defined decrease in TCP or dose coverage was fulfilled. 4. First, margin recipes were calculated for each of the three uncertainties separately. CTV and PTV recipes were then combined quadratically to yield a final recipe M(Sgeo, sgeo, Smicro(Ni)).5. The final M was verified by simultaneous simulations of the uncertainties.Now, M has been calculated for various changing parameters like margin criteria, penumbra steepness, islet radio-sensitivity, dose conformity, and number of fractions. We subsequently investigated A: whether the combined recipe still holds in all these situations, and B: what the margin variation was in all these cases. Results: We found that the accuracy of the combined margin recipes remains on average within 1mm for all situations, confirming the correctness of the quadratic addition. Depending on the specific parameter, margin factors could change such that margins change over 50%. Especially margin recipes based on TCP-criteria are more sensitive to more parameters than those based on purely geometric Dmin-criteria. Interestingly, measures taken to minimize treatment field sizes (by e.g. optimizing dose conformity) are counteracted by the requirement of larger margins to get the same tumor coverage. Conclusion: Margin recipes combining geometric and microscopic uncertainties quadratically are

  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. 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.

  13. 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.

  14. 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 ...

  15. 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.

  16. Marginal Energy Price Report - July 1999

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

    J:marginalFinalDraftReport7-29-99.wpd DRAFT Marginal Energy Prices Report July 1999 U.S. Department of Energy Assistant Secretary, Energy Efficiency & Renewable Energy Office of ...

  17. Sandia National Laboratories: Predicting Performance Margins

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

    Predicting Performance Margins Facebook Twitter YouTube Flickr RSS Top Predicting Performance Margins Project Organization PPM Team Members Publications Future Directions News Predicting Performance Margins Predicting Performance Margins Texture density plots EBSD measurements and CP-FEM predictions of tantalum oligocrystal. Texture density plots Strain field A comparison of measured and predicted surface strain fields at 4.3% applied strain. Strain field Grain boundary structure

  18. 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: ...

  19. 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

  20. 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.

  1. 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...

  2. 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...

  3. 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.

  4. 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.

  5. 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.

  6. 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 &...

  7. 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

  8. Path to development of quantitative safety goals

    SciTech Connect (OSTI)

    Joksimovic, V.; Houghton, W.J.

    1980-04-01

    There is a growing interest in defining numerical safety goals for nuclear power plants as exemplified by an ACRS recommendation. This paper proposes a lower frequency limit of approximately 10/sup -4//reactor-year for design basis events. Below this frequency, down, to a small frequency such as 10/sup -5//reactor-year, safety margin can be provided by, say, site emergency plans. Accident sequences below 10/sup -5/ should not impact public safety, but it is prudent that safety research programs examine sequences with significant consequences. Once tentatively agreed upon, quantitative safety goals together with associated implementation tools would be factored into regulatory and design processes.

  9. AFR-100 safety analyses

    SciTech Connect (OSTI)

    Sumner, T.; Moisseytsev, A.; Wei, T. Y. C.

    2012-07-01

    The Advanced Fast Reactor-100 (AFR-100) is Argonne National Laboratory's 250 MWth metal-fueled modular sodium-cooled pool-type fast reactor concept. [1] A series of accident sequences that focused on the AFR-100's ability to provide protection against reactor damage during low probability accident sequences resulting from multiple equipment failures were examined. Protected and Unprotected Loss of Flow (PLOF and ULOF) and Unprotected Transient Over-Power (UTOP) accidents were simulated using the SAS4A/SASSYS-1 safety analysis code. The large heat capacity of the sodium in the pool-type reactor allows the AFR-100 to absorb large amounts of energy during a PLOF with relatively small temperature increases throughout the system. During a ULOF with a 25-second flow halving time, coolant and cladding temperatures peak around 720 deg. C within the first minute before reactivity feedback effects decrease power to match the flow. Core radial expansion and fuel Doppler provide the necessary feedback during the UTOP to bring the system back to critical before system temperatures exceed allowable limits. Simulation results indicate that adequate ULOF safety margins exist for the AFR-100 design with flow halving times of twenty-five seconds. Significant safety margins are maintained for PLOF accidents as well as UTOP accidents if a rod stop is used. (authors)

  10. 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...

  11. 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

  12. 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...

  13. Safety evaluation of MHTGR licensing basis accident scenarios

    SciTech Connect (OSTI)

    Kroeger, P.G.

    1989-04-01

    The safety potential of the Modular High-Temperature Gas Reactor (MHTGR) was evaluated, based on the Preliminary Safety Information Document (PSID), as submitted by the US Department of Energy to the US Nuclear Regulatory Commission. The relevant reactor safety codes were extended for this purpose and applied to this new reactor concept, searching primarily for potential accident scenarios that might lead to fuel failures due to excessive core temperatures and/or to vessel damage, due to excessive vessel temperatures. The design basis accident scenario leading to the highest vessel temperatures is the depressurized core heatup scenario without any forced cooling and with decay heat rejection to the passive Reactor Cavity Cooling System (RCCS). This scenario was evaluated, including numerous parametric variations of input parameters, like material properties and decay heat. It was found that significant safety margins exist, but that high confidence levels in the core effective thermal conductivity, the reactor vessel and RCCS thermal emissivities and the decay heat function are required to maintain this safety margin. Severe accident extensions of this depressurized core heatup scenario included the cases of complete RCCS failure, cases of massive air ingress, core heatup without scram and cases of degraded RCCS performance due to absorbing gases in the reactor cavity. Except for no-scram scenarios extending beyond 100 hr, the fuel never reached the limiting temperature of 1600/degree/C, below which measurable fuel failures are not expected. In some of the scenarios, excessive vessel and concrete temperatures could lead to investment losses but are not expected to lead to any source term beyond that from the circulating inventory. 19 refs., 56 figs., 11 tabs.

  14. 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.

  15. 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...

  16. 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...

  17. 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.

  18. 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

  19. 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.

  20. 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.

  1. 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.

  2. 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.

  3. 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

  4. Preservation of FFTF Data Related to Passive Safety Testing

    SciTech Connect (OSTI)

    Wootan, David W.; Butner, R. Scott; Omberg, Ronald P.; Makenas, Bruce J.; Nielsen, Deborah L.

    2010-10-01

    experience to a large-size LMR and obtain data for validating design analysis computer codes, and 3) to develop and test passive safety enhancements that might be used for future LMRs. These tests were designed to provide data sufficient to allow separation of fuel temperature effects from structural temperature effects. The data developed through this testing program were used to verify the predictive capability of passive safety analysis methods as well as provide a data base for calibrating design tools such as the SASSYS/SAS4A codes. These tests were instrumental in improving understanding of reactivity feedback mechanisms in LMRs and demonstrating passive safety margins available in an LMR. Knowledge preservation at the FFTF is focused on the areas of design, construction, startup, and operation of the reactor. This information may be of potential use for international exchanges with other LMR programs around the world. This information provides the basis for creating benchmarks for validating and testing large scale computer programs. All information preserved to date is now being stored and categorized consistent with the IAEA international standardized taxonomy. The test results information exists in several different formats depending upon the final stage of the test evaluation. Over 100 documents relevant to passive safety testing have been identified and are being recovered, scanned, and catalogued. Attempts to recover plant data tapes are also in progress. Documents related to passive safety testing are now being categorized consistent with internationally agreed upon IAEA standards. Documents are being converted to electronic format compatible with a general search engine being developed by INL. The data from the FFTF passive safety tests provides experimental verification of structural reactivity effects that should be very useful to innovative designers seeking to optimize passive safety in the design of new LMRs.

  5. 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

  6. 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...

  7. 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.

  8. 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.

  9. 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.

  10. 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.

  11. 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.

  12. ITP Steel: Steel Industry Marginal Opportunity Study September...

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

    Marginal Opportunity Study September 2005 ITP Steel: Steel Industry Marginal Opportunity Study September 2005 steelmarginalopportunity.pdf (346.86 KB) More Documents & Publications ...

  13. Assessment of Biomass Resources from Marginal Lands in APEC Countries...

    Open Energy Info (EERE)

    Biomass Resources from Marginal Lands in APEC Countries Jump to: navigation, search Logo: Assessment of Biomass Resources from Marginal Lands in APEC Countries Name Assessment of...

  14. 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

  15. Marginal Abatement Cost Tool (MACTool) | Open Energy Information

    Open Energy Info (EERE)

    also determines which economic sectors would be likely to respond to a given carbon price, thus assessing the effectiveness of a cap-and-trade system. When to Use This Tool...

  16. 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.

  17. 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...

  18. 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) ...

  19. 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 ...

  20. 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...

  1. 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.

  2. 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.

  3. 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.

  4. Improvement of the thermal margins in the Swedish Ringhals-3 PWR by introducing new fuel assemblies with thorium

    SciTech Connect (OSTI)

    Lau, C. W.; Demaziere, C.; Nylen, H.; Sandberg, U.

    2012-07-01

    Thorium is a fertile material and most of the past research has focused on breeding thorium to fissile material. In this paper, the focus is on using thorium to improve the thermal margins by homogeneously distributing thorium in the fuel pellets. A proposed uranium-thorium-based fuel assembly is simulated for the Swedish Ringhals-3 PWR core in a realistic demonstration. All the key safety parameters, such as isothermal temperature coefficient of reactivity, Doppler temperature of reactivity, boron worth, shutdown margins and fraction of delayed neutrons are studied in this paper, and are within safety limits for the new core design using the uranium-thorium-based fuel assemblies. The calculations were performed by the two-dimensional transport code CASMO-4E and the two group steady-state three dimensional nodal code SIMULATE-3 from Studsvik Scandpower. The results showed that the uranium-thorium-based fuel assembly improves the thermal margins, both in the pin peak power and the local power (Fq). The improved thermal margins would allow more flexible core designs with less neutron leakage or could be used in power uprates to offer efficient safety margins. (authors)

  5. 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

  6. Focus on Venezuelan heavy crude: refining margins

    SciTech Connect (OSTI)

    Not Available

    1984-01-25

    Of six crudes refined in the US Gulf Coast, heavy Venezuelan crude Lagunillas (15/sup 0/ API) provides the best margin per barrel. Data for end of December 1983 and the first three weeks of January show that margins on all crudes are on the rise in this market, due to a turnaround in product prices. The lighter crudes are showing the greatest increase in Gross Product Worth. This is having a modest shrinking effect on the margin differential between light and heavy crudes in this market. The domestic crude West Texas Intermediate, at 40/sup 0/ API, provides the highest GPW in this crude slate sample, over US $31 per barrel, compared to GPW of under US $28 per barrel for Lagunillas. Still, as Lagunillas cost about US $8 less than does WTI, refiners with sufficient residue conversion capacity can be earning about US $3.50 more in margin per barrel than they can with WTI. Although few refiners would be using a 15/sup 0/ API crude exclusively for any length of time, heavier oil's inclusion in modern refiners' diets is enhancing their competitive position more than any other single factor. This issue of Energy Detente presents the fuel price/tax series and industrial fuel prices for January 1984 for countries of the Western Hemisphere.

  7. 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

  8. Validation of nuclear criticality safety software and 27 energy group ENDF/B-IV cross sections. Revision 1

    SciTech Connect (OSTI)

    Lee, B.L. Jr.; D`Aquila, D.M.

    1996-01-01

    The original validation report, POEF-T-3636, was documented in August 1994. The document was based on calculations that were executed during June through August 1992. The statistical analyses in Appendix C and Appendix D were completed in October 1993. This revision is written to clarify the margin of safety being used at Portsmouth for nuclear criticality safety calculations. This validation gives Portsmouth NCS personnel a basis for performing computerized KENO V.a calculations using the Lockheed Martin Nuclear Criticality Safety Software. The first portion of the document outlines basic information in regard to validation of NCSS using ENDF/B-IV 27-group cross sections on the IBM3090 at ORNL. A basic discussion of the NCSS system is provided, some discussion on the validation database and validation in general. Then follows a detailed description of the statistical analysis which was applied. The results of this validation indicate that the NCSS software may be used with confidence for criticality calculations at the Portsmouth Gaseous Diffusion Plant. For calculations of Portsmouth systems using the specified codes and systems covered by this validation, a maximum k{sub eff} including 2{sigma} of 0.9605 or lower shall be considered as subcritical to ensure a calculational margin of safety of 0.02. The validation of NCSS on the IBM 3090 at ORNL was extended to include NCSS on the IBM 3090 at K-25.

  9. 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

  10. 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.

  11. 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

  12. 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.

  13. 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 ...

  14. 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, ...

  15. Subcooling margin system for cooling fluid in a nuclear reactor

    SciTech Connect (OSTI)

    Ball, R. M.; Womack, E. A. Jr.

    1984-11-13

    A monitoring system for providing a display of the margin between actual and saturation pressure as well as a display between actual and saturation temperature for the cooling fluid of a nuclear reactor. The system also has an alarm which is set off whenever the pressure margin to saturation pressure reaches a predetermined limit as well as a temperature margin alarm which sets off an alarm whenever the temperature margin to saturation temperature reaches a predetermined limit.

  16. 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.

  17. Growth rates of upper Permian carbonate platform, Capitan margin of northern Delaware basin

    SciTech Connect (OSTI)

    Harris, P.M.; Grover, G.A.

    1989-03-01

    Subsurface and outcrop studies of the Capitan margin (late Guadalupian, Capitanian) in the northern Delaware basin have revealed that over 80% of the total progradation of the margin, over half the total aggradation of the platform (150 of 290 m), and over two-thirds of the basin fill (190 of 280 m) occurred during an early phase of development equating with Seven Rivers beds on the platform. The amount of progradation varied from 6 km from outcrop data in the Guadalupe Mountains to 19 km along trend to the east from subsurface information. The later phase of Capitan margin development was coincident with Yates and Tansill deposition on the platform and was dominated by aggradation and steepening of the margin. Corresponding to this two-phase model, two third-order cycles of relative sea level occur within the Capitanian on the eustasy curve of Ross and Ross: a Seven Rivers cycle lasting 1.5 m.y. and a Yates-Tansill cycle of 1.0 m.y. Progradation rates for the Capitan range from 2.6 to 8.3 m/1000 years. Similar rates are calculated from high-resolution seismic lines across the Cenozoic margin of northwestern great Bahama Bank. Accumulation rates for the Capitan, uncorrected for compaction, average 125 ..mu..m/year and 335 ..mu..m/year for the early phase shelf and shelf margin, respectively, and 160 ..mu..m/year and 430..mu..m/year for the later phase shelf and shelf margin. These accumulation rates are similar to those of other ancient, prograding platforms.

  18. 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.

  19. Hierarchical Marginal Land Assessment for Land Use Planning

    SciTech Connect (OSTI)

    Kang, Shujiang; Post, Wilfred M; Wang, Dali; Nichols, Dr Jeff A; Bandaru, Vara Prasad

    2013-01-01

    Marginal land provides an alternative potential for food and bioenergy production in the face of limited land resources; however, effective assessment of marginal lands is not well addressed. Concerns over environmental risks, ecosystem services and sustainability for marginal land have been widely raised. The objective of this study was to develop a hierarchical marginal land assessment framework for land use planning and management. We first identified major land functions linking production, environment, ecosystem services and economics, and then classified land resources into four categories of marginal land using suitability and limitations associated with major management goals, including physically marginal land, biologically marginal land, environmental-ecological marginal land, and economically marginal land. We tested this assessment framework in south-western Michigan, USA. Our results indicated that this marginal land assessment framework can be potentially feasible on land use planning for food and bioenergy production, and balancing multiple goals of land use management. We also compared our results with marginal land assessment from the Conservation Reserve Program (CRP) and land capability classes (LCC) that are used in the US. The hierarchical assessment framework has advantages of quantitatively reflecting land functions and multiple concerns. This provides a foundation upon which focused studies can be identified in order to improve the assessment framework by quantifying high-resolution land functions associated with environment and ecosystem services as well as their criteria are needed to improve the assessment framework.

  20. 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...

  1. 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...

  2. 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...

  3. 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...

  4. 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 ...

  5. 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.

  6. 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.

  7. 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.

  8. 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 ...

  9. 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 ...

  10. MARGINAL EXPENSE OIL WELL WIRELESS SURVEILLANCE MEOWS

    SciTech Connect (OSTI)

    Mason M. Medizade; John R. Ridgely; Donald G. Nelson

    2004-11-01

    A marginal expense oil well wireless surveillance system to monitor system performance and production from rod-pumped wells in real time from wells operated by Vaquero Energy in the Edison Field, Main Area of Kern County in California has been successfully designed and field tested. The surveillance system includes a proprietary flow sensor, a programmable transmitting unit, a base receiver and receiving antenna, and a base station computer equipped with software to interpret the data. First, the system design is presented. Second, field data obtained from three wells is shown. Results of the study show that an effective, cost competitive, real-time wireless surveillance system can be introduced to oil fields across the United States and the world.

  11. Regnar -- Development of a marginal field

    SciTech Connect (OSTI)

    Thalund, K.M.; Brodersen, F.P.; Roigaard-Petersen, B.

    1994-12-31

    Regnar is a small marginal field located some 13 km from the main Dan F complex and is the first subsea completion in Danish waters, operated by Maersk Olie og Gas AS. A short lifetime has been predicted for the field which therefore has been developed as a low cost project, using a combination of subsea technology and minimum topside facilities. Regnar consists of a subsea x-mas tree producing through a 6 inch pipeline with a 2 1/2 inch chemical piggyback line to Dan F. The x-mas tree and the subsea choke valve are controlled from a buoy moored nearby the well. The buoy is radio linked to Dan F. The Regnar field was brought on stream on September 26, 1993.

  12. 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

  13. Geologic hazards on the Atlantic continental margin of the United States

    SciTech Connect (OSTI)

    Folger, D.W.

    1985-01-01

    Although 46 exploratory holes have failed to reveal commercial hydrocarbon accumulations on the US Atlantic margin, about twice that number were drilled on the contiguous Canadian margin before large reserves were discovered. Thus, despite the initial results, exploration on the US margin will probably continue and additional information will be needed to augment the extensive environmental data base acquired over the past 10 years. The extent, timing, causes, and importance of sediment instability of the Continental Slopes of Georges Bank, Baltimore Canyon Trough and Carolina Trough--where future exploration will take place--remain controversial. Many question remain to be answered regarding such phenomena as creep on the upper slope, mass wasting in canyons and gullies, and slumping associated with faults and salt diapirs. Along the southeastern margin, the distribution of cavernous porosity below the shelf is only broadly known. Caverns pose a potential threat to drilling operations ranging from collapse of rigs to circulation loss and sheared drill strings. In deeper waters of the Continental Slope (700-2000 m), clathrates or frozen gas hydrates are common. The potential hazard of blow-outs from gas trapped beneath this layer are unknown. Additional information is needed to assess the bottom stresses imposed by tidal, storm, and geostrophically-driven currents on offshore rigs and structures, particularly in such areas as Georges Bank, the Carolina Trough, and the Blake Plateau.

  14. 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.

  15. Marginal Energy Price Report - July 1999 | Department of Energy

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

    Price Report - July 1999 Marginal Energy Price Report - July 1999 Estimated Consumer Marginal Energy Prices for the Commercial and Residental Sectors for use in the Life-Cycle Cost Analyses for four of the High-Priority Appliance Rulemakings marg_eprice_0799.pdf (379.48 KB) More Documents & Publications Marginal Energy Prices - RECS97 Update Standby Rates for Customer-Sited Resources - Issues, Considerations, and the Elements of Model Tariffs, 2009 Solar Real-Time Pricing: Is Real-Time

  16. 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.

  17. 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.

  18. Marginal pricing of transmission services: An analysis of cost recovery

    SciTech Connect (OSTI)

    Perez-Arriaga, I.J.; Rubio, F.J.; Puerta, J.F.; Arceluz, J.; Marin, J.

    1995-02-01

    This paper presents an in-depth analysis of network revenues computed with marginal pricing, and in particular it investigates the reasons why marginal prices fail to recover the total incurred network costs in actual power systems. The basic theoretical results are presented and the major causes of the mismatch between network costs and marginal revenues are identified and illustrated with numerical examples, some tutorial and others of realistic size. The regulatory implications of marginal network pricing in the context of competitive electricity markets are analyzed, and suggestions are provided for the meaningful allocation of the costs of the network among its users.

  19. Marginal Energy Prices - RECS97 Update | Department of Energy

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

    An updated estimation of residential marginal energy prices at the individual house level using the 1997 RECS survey data margepricerecs97.pdf (18.15 KB) More Documents & ...

  20. 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.

  1. 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).

  2. 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 ...

  3. Core design of long life-cycle fast reactors operating without reactivity margin

    SciTech Connect (OSTI)

    Aristova, E. N.; Baydin, D. F.; Gol'din, V. Y.; Pestryakova, G. A.; Stoynov, M. I.

    2012-07-01

    In this paper we consider a possibility of designing a fast reactor core that operates without reactivity margin for a long time. This study is based on the physical principle of fast reactor operating in a self-adjustable neutron-nuclear regime (SANNR-1) introduced by L.P. Feoktistov (1988-1993) and improved by V. Ya. Gol'din SANNR-2 (1995). The mathematical modeling of active zones of fast reactors in SANNR modes is held by authors since 1992. The numerical simulation is based on solving the neutron transport equation coupled with quasi-diffusion equations. The calculations have been performed using standard 26 energy groups. We use a hierarchy of spatial models of 1D, 1.5D, 2D, and 3D geometries. The spatial models of higher dimensionality are used for verification of results. The calculations showed that operation of the reactor in this mode increases its efficiency, safety and simplifies management. It is possible to achieve continuous work of the reactor in SANNR-2 during 7-10 years without fuel overloads by means of further optimization of the mode. Small reactivity margin is used only for the reactor start up. After first 10-15 days the reactor in SANNR-2 operates without reactivity margin. (authors)

  4. 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%

  5. Assessment of Biomass Resources from Marginal Lands in APEC Economies

    SciTech Connect (OSTI)

    Milbrandt, A.; Overend, R. P.

    2009-08-01

    The goal of this study is to examine the marginal lands in Asia-Pacific Economic Cooperation (APEC) economies and evaluate their biomass productivity potential. Twelve categories of marginal lands are identified using the Global Agro-Ecological Zones system of the United Nations Food and Agriculture Organization.

  6. Criticality Safety Evaluation of Hanford Tank Farms Facility

    SciTech Connect (OSTI)

    WEISS, E.V.

    2000-12-15

    Data and calculations from previous criticality safety evaluations and analyses were used to evaluate criticality safety for the entire Tank Farms facility to support the continued waste storage mission. This criticality safety evaluation concludes that a criticality accident at the Tank Farms facility is an incredible event due to the existing form (chemistry) and distribution (neutron absorbers) of tank waste. Limits and controls for receipt of waste from other facilities and maintenance of tank waste condition are set forth to maintain the margin subcriticality in tank waste.

  7. 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.

  8. 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

  9. 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.

  10. 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.

  11. 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

  12. 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.

  13. 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 ...

  14. 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.

  15. 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 ...

  16. 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...

  17. Marginal erg facies: A trial approach toward a descriptive classification

    SciTech Connect (OSTI)

    Caputo, M.V. ); Langford, R.P. )

    1991-03-01

    During the late 1970s and early 1980s, sedimentologists began recognizing the margins of eolian sand seas as separate, components which differed from interior sand seas in geometry, extent, and facies. Stratigraphers have now observed these differences in eolian rocks. Erg margins may be grouped in five ways: (1) by associations with extradunal environments-coastal plain, lacustrine, periglacial, marine (tidal flat, coastal sabkha, beach, and lagoon), and arid alluvial (alluvial fan, fluvial, playa, inland sabkha); (2) by allocyclic controls-eustasy, plate tectonism, and climate; (3) by autocyclic controls-local tectonism, topography, vegetation, hydrology, structure, sediment source and supply, and wind regime; (4) by geographic position-upwind, downwind, and along-wind margins; and (5) by sedimentary facies-texture and architecture. In contrast with erg interiors, erg margins are characterized by smaller, less complex dune-forms related to thinner sand accumulation; elementary dune architecture; more vegetation and bioturbation; high occurrence of sand sheet, zibar, and serir facies; expansive, low-relief interdunes with widely distributed dunes; and a greater proportion of interbedded extradunal deposits. Some of the published studies on ancient eolian systems have identified erg margin facies that have been influences by marine and arid alluvial processes. Few reports have described lacustrine-eolian and periglacial-eolian interactions. This study is an attempt to organize known features of modern and ancient erg margins into a scheme based on erg margin controls.

  18. Radiotherapy margin design with particular consideration of high curvature CTVs

    SciTech Connect (OSTI)

    Herschtal, Alan; Kron, Tomas; Fox, Chris [Peter MacCallum Cancer Centre, St. Andrews Place, E. Melbourne, Victoria 3002 (Australia)

    2009-03-15

    In applying 3D conformal radiation therapy to a tumor clinical target volume (CTV), a margin is added around the CTV to account for any sources of error in the application of treatment which may result in misalignment between the CTV and the dose distribution actually delivered. The volume enclosed within the CTV plus the margin is known as the PTV, or planning target volume. The larger the errors are anticipated to be, the wider the margin will need to be to accommodate those errors. Based on the approach of van Herk et al. [''The probability of correct target dosage: Dose-population histograms for deriving treatment margins in radiotherapy,'' Int. J. Radiat. Oncol. Biol., Phys. 47(4), 1121-1135 (2000)] this paper develops the mathematical theory behind the calculation of the margin width required to ensure that the entire CTV receives sufficiently high dose with sufficiently high probability. The margin recipe developed not only considers the magnitude of the errors but also includes a term to adjust for curved CTV surfaces. In doing so, the accuracy of the margin recipe is enhanced yet remains mathematically concise enough to be readily implemented in the clinical setting. The results are particularly relevant for clinical situations in which the uncertainties in treatment are large relative to the size of the CTV.

  19. 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. ...

  20. 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 ...

  1. 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 ...

  2. 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 ...

  3. 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.

  4. 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.

  5. ITP Steel: Steel Industry Marginal Opportunity Study September 2005

    Office of Energy Efficiency and Renewable Energy (EERE)

    The objective of this study is to generate a marginal opportunity curve for the ITP steel subprogram showing the location of the current portfolio compared against all opportunities for steel manufacturing.

  6. 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)

  7. 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

  8. 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

  9. 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

  10. 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)

  11. 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

  12. 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

  13. 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)

  14. Electricity Prices in a Competitive Environment: Marginal Cost Pricing

    Reports and Publications (EIA)

    1997-01-01

    Presents the results of an analysis that focuses on two questions: (1) How are prices for competitive generation services likely to differ from regulated prices if competitive prices are based on marginal costs rather than regulated cost-of-service pricing? (2) What impacts will the competitive pricing of generation services (based on marginal costs) have on electricity consumption patterns, production costs, and the financial integrity of electricity suppliers?

  15. Criticality Safety Analysis Of As-loaded Spent Nuclear Fuel Casks

    SciTech Connect (OSTI)

    Banerjee, Kaushik; Scaglione, John M

    2015-01-01

    The final safety analysis report (FSAR) or the safety analysis report (SAR) for a particular spent nuclear fuel (SNF) cask system documents models and calculations used to demonstrate that a system meets the regulatory requirements under all normal, off-normal, and accident conditions of spent fuel storage, and normal and accident conditions of transportation. FSAR/SAR calculations and approved content specifications are intended to be bounding in nature to certify cask systems for a variety of fuel characteristics with simplified SNF loading requirements. Therefore, in general, loaded cask systems possess excess and uncredited criticality margins (i.e., the difference between the licensing basis and the as-loaded calculations). This uncredited margin could be quantified by employing more detailed cask-specific evaluations that credit the actual as-loaded cask inventory, and taking into account full (actinide and fission product) burnup credit. This uncredited criticality margin could be potentially used to offset (1) uncertainties in the safety basis that needs to account for the effects of system aging during extended dry storage prior to transportation, and (2) increases in SNF system reactivity over a repository performance period (e.g., 10,000 years or more) as the system undergoes degradation and internal geometry changes. This paper summarizes an assessment of cask-specific, as-loaded criticality margins for SNF stored at eight reactor sites (215 loaded casks were analyzed) under fully flooded conditions to assess the margins available during transportation after extended storage. It is observed that the calculated keff margin varies from 0.05 to almost 0.3 keff for the eight selected reactor sites, demonstrating that significant uncredited safety margins are present. In addition, this paper evaluates the sufficiency of this excess margin in applications involving direct disposal of currently loaded SNF casks.

  16. Criticality Safety Analysis Of As-loaded Spent Nuclear Fuel Casks

    SciTech Connect (OSTI)

    Banerjee, Kaushik; Scaglione, John M

    2015-01-01

    The final safety analysis report (FSAR) or the safety analysis report (SAR) for a particular spent nuclear fuel (SNF) cask system documents models and calculations used to demonstrate that a system meets the regulatory requirements under all normal, off-normal, and accident conditions of spent fuel storage, and normal and accident conditions of transportation. FSAR/SAR calculations and approved content specifications are intended to be bounding in nature to certify cask systems for a variety of fuel characteristics with simplified SNF loading requirements. Therefore, in general, loaded cask systems possess excess and uncredited criticality margins (i.e., the difference between the licensing basis and the as-loaded calculations). This uncredited margin could be quantified by employing more detailed cask-specific evaluations that credit the actual as-loaded cask inventory, and taking into account full (actinide and fission product) burnup credit. This uncredited criticality margin could be potentially used to offset (1) uncertainties in the safety basis that needs to account for the effects of system aging during extended dry storage prior to transportation, and (2) increases in SNF system reactivity over a repository performance period (e.g., 10,000 years or more) as the system undergoes degradation and internal geometry changes. This paper summarizes an assessment of cask-specific, as-loaded criticality margins for SNF stored at eight reactor sites (215 loaded casks were analyzed) under fully flooded conditions to assess the margins available during transportation after extended storage. It is observed that the calculated keff margin varies from 0.05 to almost 0.3 Δkeff for the eight selected reactor sites, demonstrating that significant uncredited safety margins are present. In addition, this paper evaluates the sufficiency of this excess margin in applications involving direct disposal of currently loaded SNF casks.

  17. 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.

  18. 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.

  19. 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. ...

  20. 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. ...

  1. 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.

  2. 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 ...

  3. 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.

  4. 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.

  5. 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.

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. 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.