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Note: This page contains sample records for the topic "risk informed safety" from the National Library of EnergyBeta (NLEBeta).
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1

RISK-INFORMED SAFETY MARGIN CHARACTERIZATION  

Science Conference Proceedings (OSTI)

The concept of safety margins has served as a fundamental principle in the design and operation of commercial nuclear power plants (NPPs). Defined as the minimum distance between a system’s “loading” and its “capacity”, plant design and operation is predicated on ensuring an adequate safety margin for safety-significant parameters (e.g., fuel cladding temperature, containment pressure, etc.) is provided over the spectrum of anticipated plant operating, transient and accident conditions. To meet the anticipated challenges associated with extending the operational lifetimes of the current fleet of operating NPPs, the United States Department of Energy (USDOE), the Idaho National Laboratory (INL) and the Electric Power Research Institute (EPRI) have developed a collaboration to conduct coordinated research to identify and address the technological challenges and opportunities that likely would affect the safe and economic operation of the existing NPP fleet over the postulated long-term time horizons. In this paper we describe a framework for developing and implementing a Risk-Informed Safety Margin Characterization (RISMC) approach to evaluate and manage changes in plant safety margins over long time horizons.

Nam Dinh; Ronaldo Szilard

2009-07-01T23:59:59.000Z

2

Risk Informed Safety Margin Characterization (RISMC) Advanced Test Reactor  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Risk Informed Safety Margin Characterization (RISMC) Advanced Test Risk Informed Safety Margin Characterization (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 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 Risk Informed Safety Margin Characterization (RISMC)

3

Risk Informed Safety Categorization (RISC-3) Seismic Assessment Guidelines  

Science Conference Proceedings (OSTI)

The Nuclear Regulatory Commission (NRC) has amended its regulations to provide an alternative approach for treatment of structures, systems, and components (SSCs) for nuclear power reactors using a risk-informed method of categorizing SSCs according to their safety significance.

2005-12-19T23:59:59.000Z

4

A risk-informed approach to safety margins analysis  

SciTech Connect

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.

Curtis Smith; Diego Mandelli

2013-07-01T23:59:59.000Z

5

Risk Assessment in Support of DOE Nuclear Safety, Risk Information Notice,  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Risk Assessment in Support of DOE Nuclear Safety, Risk Information Risk Assessment in Support of DOE Nuclear Safety, Risk Information Notice, June 2010 Risk Assessment in Support of DOE Nuclear Safety, Risk Information Notice, June 2010 On August 12, 2009, the Defense Nuclear Facilities Safety Board (DNFSB) issued Recommendation 2009-1, Risk Assessment Methodologies at Defense Nuclear Facilities. This recommendation focused on the need for clear direction on use of quantitative risk assessments in nuclear safety applications at defense nuclear facilities. The Department of Energy (DOE) is presently analyzing directives, standards, training, and other tools that may support more effective development and use of risk assessment. Working with the Chief of Defense Nuclear Safety and the Chief of Nuclear Safety, staff from the Office of Health,

6

Risk Informed Safety Margin Characterization (RISMC) Advanced Test Reactor  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

(RISMC) Advanced Test (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 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 Risk Informed Safety Margin Characterization (RISMC) Pathway research and development (R&D) is to support plant decisions for

7

Risk Informed Safety Margin Characterization Case Study: Selection of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Case Study: Selection 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 present report documents (in Appendix A) a case study, carrying out key steps of the Reference 1 process, using an actual plant Probabilistic Risk Assessment (PRA) model. 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

8

Framework for Risk-Informed Safety Margin Characterization  

Science Conference Proceedings (OSTI)

Commercial nuclear power plants in operation continue to undergo design and operational changes to support cost-effective long-term operation. Additionally, as plant operational lifetimes are extended, it is imperative that they effectively manage aging degradation, prevent the occurrence of any safety-significant operational events, and analytically demonstrate acceptable (and even improved) nuclear safety risk. This report describes initial research to develop and validate an integrated framework and a...

2009-12-22T23:59:59.000Z

9

Evaluation of Risk Informed Safety Margin Characterization for Applicability to Significance Determination Process Evaluations  

Science Conference Proceedings (OSTI)

This report describes an industry application of the risk-informed safety margin characterization (RISMC) framework to the analysis of a plant event previously subjected to a significance determination process (SDP) evaluation. Within the nuclear regulatory system in the United States, the SDP uses risk insights, where appropriate, to help inspectors and regulatory staff determine the safety or security significance of inspection findings identified within the seven cornerstones of safety at ...

2013-12-16T23:59:59.000Z

10

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

Science Conference Proceedings (OSTI)

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.

Robert W Youngblood

2010-09-01T23:59:59.000Z

11

Pilot Application of Risk-Informed Safety Margins to Support Nuclear Plant Long-Term Operation Decisions  

Science Conference Proceedings (OSTI)

This report describes an industry application of the risk-informed safety margin characterization (RISMC) framework to the analysis of the impacts of a power uprate to a loss of main feedwater (LOMFW) event. The primary objective of this effort was to assess the changes in the safety margins for this event that result from the elevated power levels associated with a hypothetical plant power uprate. This analysis focused on the probabilistic risk assessment modeling of feed-and-bleed operation for ...

2012-12-12T23:59:59.000Z

12

Risk-Informed and Performance-Based Safety Culture Assessment Method for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

This report provides an update of the risk management effectiveness assessment (RMEA) described in EPRI Report 1011761, Risk Management Effectiveness Assessment Application Guide. This update was performed to evaluate the capability of the RMEA to assess the effectiveness of the plant safety culture. The update considered results reported in the research literature since the 2005 publication of the application guide. It also evaluated the RMEA against the safety culture components identified by the U.S. ...

2008-12-09T23:59:59.000Z

13

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

SciTech Connect

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.

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

2012-08-01T23:59:59.000Z

14

SI Safety Information  

NLE Websites -- All DOE Office Websites (Extended Search)

Information Information Policies and Procedures Radiation Safety Device List (full version)(compressed version) APS QA APS Safety Page DOE Orders DOE Order 420.2 (11/08/95) DOE Order 420.2A (01/08/01) Accelerator Safety Implementation Guide for DOE Order 420.2 DOE Order 420.2B (07/23/04) Expires (07/23/08) (html) (pdf) Accelerator Facility Safety Implementation Guide for DOE O 420.2B (html) (pdf) Safety of Accelerator Facilities (02/18/05) Accelerator Facility Safety Implementation Guide for DOE O 420.2B (pdf) Safety of Accelerator Facilities (7/1/05) ESH Manual Guidance 5480.25 Guidance for an Accelerator Facility Safety Program 5480.25 Guidance (09/01/93) Bases & Rationale for Guidance for an Accelerator Facitlity Safety Program (October 1994) NCRP Report No. 88 "Radiation Alarms and Access Control Systems" (1987) ISBN

15

Pilot Application of Risk Informed Safety Margins to Support Nuclear Plant Long-Term Operation Decisions: Impacts on Safety Margins of Extended Power Uprates for BWR Station Blackout Events  

Science Conference Proceedings (OSTI)

The risk-informed safety margin characterization (RISMC) framework is a technically robust approach that could be used to analyze nuclear power plant (NPP) safety margins for issues of significance to NPP safety. This report describes application of the RISMC framework to analysis of the impacts of an extended power uprate (EPU) to a boiling water reactor (BWR) station blackout (SBO) event, with emphasis on changes in safety margins due to elevated power levels. The analysis focused on probabilistic ...

2013-08-27T23:59:59.000Z

16

Reliability Engineering and System Safety 92 (2007) 609618 The nuclear industry's transition to risk-informed regulation and  

E-Print Network (OSTI)

standards and the use of the newly instituted risk-informed reactor oversight process. Key factors affecting developed a probabilistic risk assessment policy in the early 1980s and nuclear reactor regulation (NRR in the development of risk- informed technologies and its use in the regulatory arena formed a small owner's group

17

Risk-Informed Asset Management  

Science Conference Proceedings (OSTI)

This report contains business requirements for Risk-Informed Asset Management (RIAM) software. The requirements pertain to both a full-blown version of RIAM (including uncertainty analysis of the economic and safety risk of a proposed equipment improvement project) and for RIAM Level 1 project screening software. The RIAM Level 1 analysis is a bounding process intended to estimate the most optimistic effect that the proposed investment would have on plant safety, cost, and revenue. The optimistic assumpt...

2006-02-24T23:59:59.000Z

18

Incorporating safety risk in early system architecture trade studies  

E-Print Network (OSTI)

Ideally, safety should be a part of the early decision making used in conceptual system design. However, effectively evaluating safety risk3 early enough to inform the early trade studies is not possible with current ...

Dulac, Nicholas

19

Safety Basis Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

Analysis (SESA) SESA Home Mission & Functions Office of Sustainability, Environment, Safety and Anaylsis (SESA) Sustainability Support Environmental Policy & Assistance ...

20

Nuclear Safety Information Dashboard  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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...

Note: This page contains sample records for the topic "risk informed safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

June 2010, Risk Assessment in Support of DOE Nuclear Safety  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Office of Nuclear Safety Policy and Assistance Office of Nuclear Safety Policy and Assistance Nuclear Safety, Quality Assurance and Environment Information Notice June 2010 1 BACKGROUND & PURPOSE: On August 12, 2009, the Defense Nuclear Facilities Safety Board (DNFSB) issued Recommendation 2009-1, Risk Assessment Methodologies at Defense Nuclear Facilities. This recommendation focused on the need for clear direction on use of quantitative risk assessments in nuclear safety applications at defense nuclear facilities. The Department of Energy (DOE) is presently analyzing directives, standards, training, and other tools that may support more effective development and use of

22

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

SciTech Connect

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.”

Curtis Smith; Cristian Rabiti; Richard Martineau

2012-11-01T23:59:59.000Z

23

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

Energy.gov (U.S. Department of Energy (DOE))

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 present report documents (in...

24

Safety Organization and Contact Information  

NLE Websites -- All DOE Office Websites (Extended Search)

Safety Organization and Contact Information Print Safety Organization and Contact Information Print Safety Staff Contact Information 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 Work Planning/Permit/span> This e-mail address is being protected from spambots. You need JavaScript enabled to view it This e-mail address is being protected from spambots. You need JavaScript enabled to view it 7358 6793 80-151 80-233 ALS-EHS Program This e-mail address is being protected from spambots. You need JavaScript enabled to view it (Interim Manager, EHS Program Management) This e-mail address is being protected from spambots. You need JavaScript enabled to view it (Interim Manager, Accelerator Facility Safety)

25

Safety Organization and Contact Information  

NLE Websites -- All DOE Office Websites (Extended Search)

Organization and Contact Information Print Organization and Contact Information Print Safety Staff Contact Information 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 Work Planning/Permit/span> This e-mail address is being protected from spambots. You need JavaScript enabled to view it This e-mail address is being protected from spambots. You need JavaScript enabled to view it 7358 6793 80-151 80-233 ALS-EHS Program This e-mail address is being protected from spambots. You need JavaScript enabled to view it (Interim Manager, EHS Program Management) This e-mail address is being protected from spambots. You need JavaScript enabled to view it (Interim Manager, Accelerator Facility Safety)

26

Safety Organization and Contact Information  

NLE Websites -- All DOE Office Websites (Extended Search)

Organization and Contact Information Print Organization and Contact Information Print Safety Staff Contact Information 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 Work Planning/Permit/span> This e-mail address is being protected from spambots. You need JavaScript enabled to view it This e-mail address is being protected from spambots. You need JavaScript enabled to view it 7358 6793 80-151 80-233 ALS-EHS Program This e-mail address is being protected from spambots. You need JavaScript enabled to view it (Interim Manager, EHS Program Management) This e-mail address is being protected from spambots. You need JavaScript enabled to view it (Interim Manager, Accelerator Facility Safety)

27

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

SciTech Connect

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.

D. Blanchard; R. Youngblood

2012-04-01T23:59:59.000Z

28

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

SciTech Connect

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.

R. Youngblood; D. Blanchard

2011-09-01T23:59:59.000Z

29

Public Safety and Security Information in MML  

Science Conference Proceedings (OSTI)

Public Safety and Security Information in MML. ... MML plays a key role in enhancing the nation's homeland security. Through ...

2010-10-05T23:59:59.000Z

30

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

risk assessment information used to evaluate and remediate legacy contamination from the Manhattan Project. The RAIS was designed to provide all risk assessment processes in a...

31

Total Risk Approach in Applying PRA to Criticality Safety  

SciTech Connect

As nuclear industry continues marching from an expert-base support to more procedure-base support, it is important to revisit the total risk concept to criticality safety. A key objective of criticality safety is to minimize total criticality accident risk. The purpose of this paper is to assess key constituents of total risk concept pertaining to criticality safety from an operations support perspective and to suggest a risk-informed means of utilizing criticality safety resources for minimizing total risk. A PRA methodology was used to assist this assessment. The criticality accident history was assessed to provide a framework for our evaluation. In supporting operations, the work of criticality safety engineers ranges from knowing the scope and configurations of a proposed operation, performing criticality hazards assessment to derive effective controls, assisting in training operators, response to floor questions, surveillance to ensure implementation of criticality controls, and response to criticality mishaps. In a compliance environment, the resource of criticality safety engineers is increasingly being directed towards tedious documentation effort to meet some regulatory requirements to the effect of weakening the floor support for criticality safety. By applying a fault tree model to identify the major contributors of criticality accidents, a total risk picture is obtained to address relative merits of various actions. Overall, human failure is the key culprit in causing criticality accidents. Factors such as failure to follow procedures, lacks of training, lack of expert support at the floor level etc. are main contributors. Other causes may include lack of effective criticality controls such as inadequate criticality safety evaluation. Not all of the causes are equally important in contributing to criticality mishaps. Applying the limited resources to strengthen the weak links would reduce risk more than continuing emphasis on the strong links of criticality safety support. For example, some compliance failures such as lack of detailed documentation may not be as relevant as the lack of floor support in answering operator's questions during operations. Misuse of resources in reducing lesser causes rather than on major causes of criticality accidents is not risk free without severe consequences. A regulatory mandate without due consideration of total risk may have its opposite effect of increasing the total risk of an accident. A lesson is to be learned here. For regulatory standard/guide development, use of ANS/ANSI standard process, which provides the pedigree of consensus participation, is recommended.

Huang, S T

2005-03-24T23:59:59.000Z

32

Criticality Safety Information Meeting for the Hanford Plutonium...  

NLE Websites -- All DOE Office Websites (Extended Search)

Safety and Security (HSS), conducted a criticality safety information meeting with Hanford site criticality safety engineers on May 14, 2012, to discuss criticality safety...

33

Nuclear Safety Information Dashboard | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Reporting » Analytical Dashboards » Nuclear Safety Reporting » Analytical Dashboards » Nuclear Safety Information Dashboard 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 reported into ORPS, assigned unique ORPS reporting criteria and used for trending. ORPS reporting criteria are assigned a weighted value to indicate their relative importance to nuclear safety; associated ORPS reporting criteria are combined in key groups and charted over time to index trends in nuclear

34

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

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.

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

2012-09-20T23:59:59.000Z

35

Risk-Informed Safety Requirements for H2 Codes and Standards Development - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

NLE Websites -- All DOE Office Websites (Extended Search)

5 5 FY 2012 Annual Progress Report DOE Hydrogen and Fuel Cells Program Aaron Harris (Primary Contact), Jeffrey LaChance, Katrina Groth Sandia National Laboratories P.O. Box 969 Livermore, CA 94551-0969 Phone: (925) 294-4530 Email: apharri@sandia.gov DOE Manager HQ: Antonio Ruiz Phone: (202) 586-0729 Email: Antonio.Ruiz@ee.doe.gov Project Start Date: October 1, 2003 Project End Date: Project continuation and direction determined annually by DOE Fiscal Year (FY) 2012 Objectives Present results of indoor refueling risk assessment to the * National Fire Protection Association (NFPA) 2 Fueling Working Group. Perform and document required risk assessment (with * input from NFPA 2 and others) for developing science- based risk-informed codes and standards for indoor

36

Reactor operation safety information document  

Science Conference Proceedings (OSTI)

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)

Not Available

1990-01-01T23:59:59.000Z

37

Safety Analysis, Hazard and Risk Evaluations [Nuclear Waste Management  

NLE Websites -- All DOE Office Websites (Extended Search)

Safety Analysis, Hazard Safety Analysis, Hazard and Risk Evaluations Nuclear Fuel Cycle and Waste Management Technologies Overview Modeling and analysis Unit Process Modeling Mass Tracking System Software Waste Form Performance Modeling Safety Analysis, Hazard and Risk Evaluations Development, Design, Operation Overview Systems and Components Development Expertise System Engineering Design Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Waste Management using Electrometallurgical Technology Safety Analysis, Hazard and Risk Evaluations Bookmark and Share NE Division personnel had a key role in the creation of the FCF Final Safety Analysis Report (FSAR), FCF Technical Safety Requirements (TSR)

38

Department of Environmental Health & Safety Risk Management Services  

E-Print Network (OSTI)

Department of Environmental Health & Safety Risk Management Services November 2009 Version 1 receive health & safety training specific to the hazards present in the lab. Where a laboratory or core of Environmental Health & Safety Risk Management Services November 2009 Version 1 January 2012 Version 2

Machel, Hans

39

Environment, Safety, and Health Risk Assessment Program (ESHRAP)  

SciTech Connect

The Environment, Safety and Health Risk Assessment Program (ESHRAP) models human safety and health risk resulting from waste management and environmental restoration activities. Human safety and health risks include those associated with storing, handling, processing, transporting, and disposing of radionuclides and chemicals. Exposures to these materials, resulting from both accidents and normal, incident-free operation, are modeled. In addition, standard industrial risks (falls, explosions, transportation accidents, etc.) are evaluated. Finally, human safety and health impacts from cleanup of accidental releases of radionuclides and chemicals to the environment are estimated. Unlike environmental impact statements and safety analysis reports, ESHRAP risk predictions are meant to be best estimate, rather than bounding or conservatively high. Typically, ESHRAP studies involve risk predictions covering the entire waste management or environmental restoration program, including such activities as initial storage, handling, processing, interim storage, transportation, and final disposal. ESHRAP can be used to support complex environmental decision-making processes and to track risk reduction as activities progress.

Eide, Steven Arvid; Thomas Wierman

2003-12-01T23:59:59.000Z

40

Public Order and Safety | Open Energy Information  

Open Energy Info (EERE)

Order and Safety Order and 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 station; fire station; jail, reformatory, or penitentiary; courthouse or probation office References EIA CBECS Building Types [1] References ↑ EIA CBECS Building Types U.S. Energy Information Administration (Oct 2008) Retrieved from "http://en.openei.org/w/index.php?title=Public_Order_and_Safety&oldid=270119" Category: CBECS Building Types What links here Related changes Special pages Printable version Permanent link Browse properties 429 Throttled (bot load) Error 429 Throttled (bot load) Throttled (bot load) Guru Meditation: XID: 1863505291 Varnish cache server

Note: This page contains sample records for the topic "risk informed safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

Principles of safety. Safety in general, criticality risk in perspective  

SciTech Connect

The role of management in the responsibility for training personnel in the fundamentals of safety and accident prevention is discussed. Program for radiation protection, with emphasis on criticality safety, are discussed briefly. (CH)

Reider, R.

1974-04-30T23:59:59.000Z

42

Technical Support to NEI on Risk-Informed Regulations--2005  

Science Conference Proceedings (OSTI)

This report documents work performed in CY 2005 by EPRI in support of the Nuclear Energy Institute (NEI). As part of its annual program, the EPRI Risk Safety/Management (R/SM) Program, formerly named Risk and Reliability Based Methods (R&RBM), provides technical support on regulatory and licensing issues to the Nuclear Energy Institute (NEI). Support for risk-informed regulations is consistent with the EPRI Nuclear Strategic Plan (NSP). The NSP Action Plan for Safety Risk Technology and Applications spec...

2005-12-23T23:59:59.000Z

43

Sharing of Nuclear Safety Information through Distributed Database Systems  

SciTech Connect

This presentation discusses the sharing of nuclear safety information through distributed database systems.

Ley, H.

2004-10-03T23:59:59.000Z

44

Failure rate data for fusion safety and risk assessment  

SciTech Connect

The Fusion Safety Program (FSP) at the Idaho National Engineering Laboratory (INEL) conducts safety research in materials, chemical reactions, safety analysis, risk assessment, and in component research and development to support existing magnetic fusion experiments and also to promote safety in the design of future experiments. One of the areas of safety research is applying probabilistic risk assessment (PRA) methods to fusion experiments. To apply PRA, we need a fusion-relevant radiological dose code and a component failure rate data base. This paper describes the FSP effort to develop a failure rate data base for fusion-specific components.

Cadwallader, L.C.

1993-01-01T23:59:59.000Z

45

Failure rate data for fusion safety and risk assessment  

SciTech Connect

The Fusion Safety Program (FSP) at the Idaho National Engineering Laboratory (INEL) conducts safety research in materials, chemical reactions, safety analysis, risk assessment, and in component research and development to support existing magnetic fusion experiments and also to promote safety in the design of future experiments. One of the areas of safety research is applying probabilistic risk assessment (PRA) methods to fusion experiments. To apply PRA, we need a fusion-relevant radiological dose code and a component failure rate data base. This paper describes the FSP effort to develop a failure rate data base for fusion-specific components.

Cadwallader, L.C.

1993-04-01T23:59:59.000Z

46

Information Flow Safety in Multiparty Sessions  

E-Print Network (OSTI)

We consider a calculus for multiparty sessions enriched with security levels for messages. We propose a monitored semantics for this calculus, which blocks the execution of processes as soon as they attempt to leak information. We illustrate the use of our monitored semantics with various examples, and show that the induced safety property implies a noninterference property studied previously.

Capecchi, Sara; Dezani-Ciancaglini, Mariangiola; 10.4204/EPTCS.64.2

2011-01-01T23:59:59.000Z

47

Comparison of Integrated Safety Analysis (ISA) and Probabilistic Risk  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Comparison of Integrated Safety Analysis (ISA) and Probabilistic Comparison of Integrated Safety Analysis (ISA) and Probabilistic Risk Assessment (PRA) for Fuel Cycle Facilities, 2/17/11 Comparison of Integrated Safety Analysis (ISA) and Probabilistic Risk Assessment (PRA) for Fuel Cycle Facilities, 2/17/11 During the 580th meeting of the Advisory Committee on Reactor Safeguards (ACRS), February 10-12, 2011, we reviewed the staff's white paper, "A Comparison of Integrated Safety Analysis and Probabilistic Risk Assessment." Our Radiation Protection and Nuclear Materials Subcommittee also reviewed this matter during a meeting on January 11, 2011. During these meetings we met with representatives of the NRC staff and the Nuclear Energy Institute. We also had the benefit of the documents referenced. Comparison of Intergrated Safety Analysis (ISA) and Probabilistic Risk

48

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

Plant: Relative Risk Ranking Sites Plant: Relative Risk Ranking Sites These rankings are based on the EM-40 Release Site Methodology. Select a release site to receive information concerning that site. Please note that not all of the listed sites are linked to further information. Abandoned Nitric Acid Pipeline ACN Drum Yard Bear Creek Burial Grounds Bear Creek Contaminated Floodplain Soils Beta-4 Security Pits Building 81-10 Area Mercury Contaminated Soils Building 9201-2 Transformer and Capacitor Storage Area Building 9201-3 Coolant Salt Technology Facility Building 9201-4 Building 9201-4 External Pipes Building 9201-5E Northeast Yard Waste Storage Area Building 9202 East Pad Waste Storage Area Building 9204-2 West Yard Waste Storage Area Building 9206 Underground Tank Building 9215 West Pad Waste Storage Area

49

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

ETTP: Relative Risk Ranking Sites ETTP: Relative Risk Ranking Sites These rankings are based on the EM-40 Release Site Methodology. Select a release site to receive information concerning that site. Please note that not all of the listed sites are linked to further information. 518 Main Substation 600 Series Oil Storage Area 695/687 Oil Storage Operations Building 523 Grease {Burial Site} Building 526 Heavy Equipment Shop Building 569 Heavy Equipment Shop Building 665 Steam Shed Building F-29 Gasoline Station Demolition Materials Placement Area Duct Island Road F-05 Laboratory Burial Ground F-07 Material Warehouse F-08 Laboratory Flannagans Loop Road Groundwater Plume Centered Under North Side of K-1070-C/D Groundwater Plume Emanating from K-1401 Acid Line Groundwater Plume near Mitchell Branch Groundwater Plume Originating from K-1420 Building

50

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

ORR Offsite: Relative Risk Ranking Sites ORR Offsite: Relative Risk Ranking Sites These rankings are based on the EM-40 Release Site Methodology. Select a release site to receive information concering that site. Please note that not all of the listed sites are linked to further information. Animal Burial Site I Animal Burial Site II Animal Burial Site III Atomic City Auto Parts - Contaminated Creek Sediments Atomic City Auto Parts - Contaminated Soils Atomic City Auto Parts - Surface Debris Clinch River/Poplar Creek CSX Railroad David Witherspoon, Inc., 1630 Site David Witherspoon, Inc., 901 Site Low Dose Rate Irradiation Facility (LDRIF) Lower East Fork Poplar Creek - Bruner Site Lower East Fork Poplar Creek - NOAA Site Lower Watts Bar Reservoir Oak Ridge Tool Engineering, Inc. Solway Drums Site Swine Waste Lagoons

51

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

ORNL: Relative Risk Ranking Sites ORNL: Relative Risk Ranking Sites These rankings are based on the EM-40 Release Site Methodology. Select a release site to receive information concerning that site. Please note that not all of the listed sites are linked to further information. 3001 Storage Canal (OGR) 3517 Filter Pit (Fission Product Development Laboratory) Abandoned Burn Pit Abandoned Sanitary Waste Pipeline and Septic Tank N of 7917 Abandoned Underground Waste Oil Storage Tank 7002A Above-ground Demineralized-water Holding Tanks Aircraft Reactor Experiment Contaminated Tool Storage Aircraft Reactor Experiment Surface Impoundment Buried Scrap Metal Area C-14 Allocation in White Oak Trees C-14 Allocation in White Pine Trees C-14 Allocation in Woody Biomass Plantation Species C-14 Efflux in Yellow Poplar Stand

52

Technical information resources for criticality safety  

SciTech Connect

This paper will discuss some basic technical information resources that would be helpful to the novice nuclear criticality safety specialist. These include bibliographic and benchmark compilations, handbooks, and online resources. The specialist should also be familiar with benchmark quality experimental data needed for code validation. This paper will also discuss the critical experiment data obtained in the 1950s and 1960s at the Lawrence Livermore National Laboratory.

Heinrichs, D.P.; Koponen, B.L.

1997-06-25T23:59:59.000Z

53

Application of Risk Assessment and Management to Nuclear Safety |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Application of Risk Assessment and Management to Nuclear Safety Application of Risk Assessment and Management to Nuclear Safety Application of Risk Assessment and Management to Nuclear Safety September 20, 2012 Presenter: Commissioner George Apostolakis US Nuclear Regulatory Commission Topics covered: Management of (unquantified at the time) uncertainty was always a concern. Defense-in-depth and safety margins became embedded in the regulations. "Defense-in-Depth is an element of the NRC's safety philosophy that employs successive compensatory measures to prevent accidents or mitigate damage if a malfunction, accident, or naturally caused event occurs at a nuclear facility." [Commission's White Paper, February 1999] Design Basis Accidents are postulated accidents that a nuclear facility must be designed and built to withstand without loss to the

54

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

Frequently Asked Questions Frequently Asked Questions This page represents the most commonly approached topics from our users. What internet browser works best for the RAIS? We attempt to accommodate every browser. If there is a problem viewing the RAIS pages or downloading items, let us know what browser you are using and we will try and fix the problem. How can I use the information on the RAIS? The information on the RAIS can be used for teaching material and performing risk assessments that comply with EPA guidance. Feel free to use the information; it is available to the public. However, please give proper credit to the RAIS and the team from Oak Ridge National Laboratory and The University of Tennessee where you see fit. Also, the databases we maintain are updated on a quarterly basis or sooner, so you may need to "time-stamp"

55

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

Risk Assessment Documents Risk Assessment Documents ORNL RA Graphic Results ORNL Baseline Risk Assessment Results ORNL Screening Risk Assessment Results ORNL Other Risk Assessment Results ORNL RA Graphic Results WAG 2 Residential Landuse Sediment - Total Risk Sediment - Cesium 137 Risk Sediment - Cobalt 60 Risk Surface Water - Total Hazard Surface Water - Total Risk Surface Water - Strontium 90 Risk Surface Water - Tritium Risk Recreational Landuse Sediment - Total Risk Sediment - Cesium 137 Risk Sediment - Cobalt 60 Risk Surface Water - Total Hazard Surface Water - Total Risk Surface Water - Strontium 90 Risk Surface Water - Tritium Risk Recreational Landuse (No Fish) Surface Water - Total Hazard Surface Water - Total Risk Surface Water - Strontium 90 Risk Surface Water - Tritium Risk Industrial Landuse

56

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

Technical Memorandum , Part II. Screening Level Risk Assessment 92-225-161-49 K-33 Cooling Towers screening risk assessments (2) K-770 sites screening risk assessment (9...

57

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

SELENIUM SELENIUM NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. MARCH 1993 Prepared by: Dennis M. Opresko, Ph.D, Chemical Hazard Evaluation Group, Biomedical Environmental Information Analysis Section, Health and Safety Research Division, Oak Ridge National Laboratory*, Oak Ridge, Tennessee. Prepared for: Oak Ridge Reservation Environmental Restoration Program. *Managed by Martin Marietta Energy Systems, Inc., for the U.S. Department of Energy under Contract No. DE-AC05-84OR21400. Selenium is an essential trace element important in many biochemical and physiological processes including the biosynthesis of coenzyme Q (a

58

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

Condensed Toxicity Summary for MOLYBDENUM Condensed Toxicity Summary for MOLYBDENUM NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. JANUARY 1993 Prepared by: Dennis M. Opresko, Ph.D., Chemical Hazard Evaluation Group, Biomedical and Environmental Information Analysis Section, Health and Safety Research Division, *, Oak Ridge, Tennessee. Prepared for: Oak Ridge Reservation Environmental Restoration Program. *Managed by Martin Marietta Energy Systems, Inc., for the U.S. Department of Energy under Contract No. DE-AC05-84OR21400. Molybdenum (Mo) occurs naturally in various ores; the principal source being molybdenite (MoS2) (Stokinger, 1981). Molybdenum compounds are used

59

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

Formal Toxicity Summary for SULFATE Formal Toxicity Summary for SULFATE NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. EXECUTIVE SUMMARY 1. INTRODUCTION 2. METABOLISM AND DISPOSITION 3. NONCARCINOGENIC HEALTH EFFECTS 3.1 ORAL EXPOSURES 3.2 INHALATION EXPOSURES 3.3 OTHER ROUTES OF EXPOSURE 3.4 TARGET ORGANS/CRITICAL EFFECTS 4. CARCINOGENICITY 5. REFERENCES JUNE 1991 Prepared by: Cheryl Bast, Chemical Hazard Evaluation and Communication Group, Biomedical and Environmental Information Analysis Section, Health and Safety Research Division, Oak Ridge National Laboratory*, Oak Ridge, Tennessee. Prepared for: Oak Ridge Reservation Environmental Restoration Program.

60

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

Condensed Toxicity Summary for TETRACHLOROETHYLENE Condensed Toxicity Summary for TETRACHLOROETHYLENE NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. MARCH 1993 Prepared by: Mary Lou Daugherty, M.S., Chemical Hazard Evaluation Group, Biomedical Environmental Information Analysis Section, Health and Safety Research Division, Oak Ridge National Laboratory*, Oak Ridge, Tennessee. Prepared for: Oak Ridge Reservation Environmental Restoration Program. *Managed by Martin Marietta Energy Systems, Inc., for the U.S. Department of Energy under Contract No. DE-AC05-84OR21400. Tetrachloroethylene (CAS No. 127-18-4) is a halogenated aliphatic

Note: This page contains sample records for the topic "risk informed safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

Condensed Toxicity Summary for ZINC AND ZINC COMPOUNDS Condensed Toxicity Summary for ZINC AND ZINC COMPOUNDS NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. April 1992 Prepared by Dennis M. Opresko, Ph.D., Chemical Hazard Evaluation and Communication Group, Biomedical and Environmental Information Analysis Section, Health and Safety Research Division, Oak Ridge National Laboratory*, Oak Ridge, Tennessee Prepared for OAK RIDGE RESERVATION ENVIRONMENTAL RESTORATION PROGRAM *Managed by Martin Marietta Energy Systems, Inc., for the U.S. Department of Energy under Contract No. DE-AC05-84OR21400 Zinc is used primarily in galvanized metals and metal alloys, but zinc

62

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

Condensed Toxicity Summary for VANADIUM Condensed Toxicity Summary for VANADIUM NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. DECEMBER 1991 Prepared by: Dennis M. Opresko, Ph.D., Chemical Hazard Evaluation and Communication Group Biomedical and Environmental Information Analysis Section, Health and Safety Research Division, *. Oak Ridge, Tennessee Prepared for: Oak Ridge Reservation Environmental Restoration Program. *Managed by Martin Marietta Energy Systems, Inc., for the U.S. Department of Energy under Contract No. DE-AC05-84OR21400. Vanadium is a metallic element that occurs in six oxidation states and

63

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

COPPER COPPER NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. DECEMBER 1992 Prepared by: Rosmarie A. Faust, Ph.D., Chemical Hazard Evaluation and Communication Group, Biomedical and Environmental Information Analysis Section, Health and Safety Research Division, *, Oak Ridge, Tennessee. Prepared for: Oak Ridge Reservation Environmental Restoration Program. *Managed by Martin Marietta Energy Systems, Inc., for the U.S. Department of Energy under Contract No. DE-AC05-84OR21400. Copper occurs naturally in elemental form and as a component of many minerals. Because of its high electrical and thermal conductivity, it is

64

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

TRICHLOROETHENE TRICHLOROETHENE NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. MARCH 1993 Prepared by: Rosmarie A. Faust, Ph.D, Chemical Hazard Evaluation Group, Biomedical Environmental Information Analysis Section, Health and Safety Research Division, *, Oak Ridge, Tennessee Prepared for: Oak Ridge Reservation Environmental Restoration Program. *Managed by Martin Marietta Energy Systems, Inc., for the U.S. Department of Energy under Contract No. DE-AC05-84OR21400. Trichloroethene (TCE) is an industrial solvent used primarily in metal degreasing and cleaning operations. TCE can be absorbed through the lungs,

65

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

Condensed Toxicity Summary for METHYL MERCURY Condensed Toxicity Summary for METHYL MERCURY NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. FEBRUARY, 1992 Prepared by: Robert A. Young, Ph.D., D.A.B.T., Chemical Hazard Evaluation and Communication Group Biomedical and Environmental Information Analysis Section, Health and Safety Research Division, *, Oak Ridge, Tennessee. Prepared for: Oak Ridge Reservation Environmental Restoration Program. *Managed by Martin Marietta Energy Systems, Inc., for the U.S. Department of Energy under Contract No. DE-AC05-84OR21400. Methyl mercury is formed by biotic and abiotic methylation of mercury

66

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

Condensed Toxicity Summary for BENZENE Condensed Toxicity Summary for BENZENE NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. September 1992 Prepared by: Mary Lou Daugherty, M.S., Chemical Hazard Evaluation and Communication Group, Biomedical and Environmental Information Analysis Section, Health and Safety Research Division*, , Oak Ridge, Tennessee. Prepared for OAK RIDGE RESERVATION ENVIRONMENTAL RESTORATION PROGRAM. *Managed by Martin Marietta Energy Systems, Inc., for the U.S. Department of Energy under Contract No. DE-AC05-84OR21400. Benzene is absorbed via ingestion, inhalation, and skin application.

67

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

CYANIDE CYANIDE NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. February 1994 Prepared by Rosmarie A. Faust, Ph.D., Chemical Hazard Evaluation and Communication Group, Biomedical and Environmental Information Analysis Section, Health and Safety Research Division, *, Oak Ridge, Tennessee. Prepared for OAK RIDGE RESERVATION ENVIRONMENTAL RESTORATION PROGRAM *Managed by Martin Marietta Energy Systems, Inc., for the U.S. Department of Energy under Contract No. DE-AC05-84OR21400 Cyanide most commonly occurs as hydrogen cyanide and its salts--sodium and potassium cyanide. Cyanides are both man-made and naturally occurring

68

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

Graphic Results Graphic Results Baseline Risk Assessment Results Screening Risk Assessment Results Other Risk Assessment Results Graphic Results K-25 Groundwater Residential Landuse Bedrock Wells - Total Hazard (range: 1-30) Bedrock Wells - Total Hazard (range: 0.1 - 1) Bedrock Wells - Total Risk Bedrock Wells - Arsenic Risk Bedrock Wells - Dichloroethene, 1,1- Risk Bedrock Wells - Trichloroethene Risk Unconsolidated Wells - Total Hazard (range: 1-150) Unconsolidated Wells - Total Hazard (range: 0.1 - 1) Unconsolidated Wells - Total Risk (range:10-4 - 1) Unconsolidated Wells - Total Risk (range:10-6 - 10-4) Unconsolidated Wells - Arsenic Risk Unconsolidated Wells - Trichloroethene Risk ORNL WAG 2 Residential Landuse Sediment - Total Risk Sediment - Cesium 137 Risk Sediment - Cobalt 60 Risk

69

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

Risk Assessment Documents Risk Assessment Documents Y-12 RA Graphic Results Y-12 Baseline Risk Assessment Results Y-12 Screening Risk Assessment Results Bullet Graphic Risk Results Arrow Bear Creek Valley Maps Residential Landuse Groundwater - Total Hazard (range: 1 - 900) Groundwater - Total Hazard (range: 0.1 - 1) Groundwater - Total Risk (range: 10-4 - 1) Groundwater - Total Risk (range: 10-5 - 10-4) Groundwater - Total Risk (range: 10-6 - 10-5) Groundwater - Dichloroethane, 1,1- Hazard Groundwater - Dichloroethene, 1,1- Hazard Groundwater - Dichloroethene, 1,1- Risk Groundwater - Dichloroethane, 1,2- Risk Groundwater - Dichloroethene, 1,2- Hazard Groundwater - Nitrate Hazard Groundwater - Radium Risk Groundwater - Technetium-99 Risk Groundwater - Tetrachloroethene Hazard Groundwater - Tetrachloroethene Risk

70

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

Debra Stewart at (865)482-2657 or dthomas3@utk.edu. Risk assessments conducted for the DOE-ORO should implement Guidance for Conducting Risk Assessments and Related Risk...

71

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

Science Conference Proceedings (OSTI)

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

Lana Buehrer, Michele Kelly, Fran Lemieux, Fred Williams

2007-11-30T23:59:59.000Z

72

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

Guidance for Conducting Risk Assessments and Related Risk Activities for the DOE-ORO Environmental Management Program. BJCOR-271 Guidance for Treatment of Variability and...

73

FTCP Site Specific Information - Chief of Nuclear Safety | Department...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

of Nuclear Safety FTCP Site Specific Information - Chief of Nuclear Safety FTCP Agent Organization Name Phone E-Mail CNS Richard Lagdon 202586-9471 chip.lagdon@hq.doe.gov...

74

Creation and Communication of Hurricane Risk Information  

Science Conference Proceedings (OSTI)

Reducing loss of life and harm when a hurricane threatens depends on people receiving hurricane risk information that they can interpret and use in protective decisions. To understand and improve hurricane risk communication, this article examines how ...

Julie L. Demuth; Rebecca E. Morss; Betty Hearn Morrow; Jeffrey K. Lazo

2012-08-01T23:59:59.000Z

75

N reactor individual risk comparison to quantitative nuclear safety goals  

Science Conference Proceedings (OSTI)

A full-scope level III probabilistic risk assessment (PRA) has been completed for N reactor, a US Department of Energy (DOE) production reactor located on the Hanford Reservation in the state of Washington. Sandia National Laboratories (SNL) provided the technical leadership for this work, using the state-of-the-art NUREG-1150 methodology developed for the US Nuclear Regulatory Commission (NRC). The main objectives of this effort were to assess the risks to the public and to the on-site workers posed by the operation of N reactor, to identify changes to the plant that could reduce the overall risk, and to compare those risks to the proposed NRC and DOE quantitative safety goals. This paper presents the methodology adopted by Westinghouse Hanford Company (WHC) and SNL for individual health risk evaluation, its results, and a comparison to the NRC safety objectives and the DOE nuclear safety guidelines. The N reactor results, are also compared with the five NUREG-1150 nuclear plants. Only internal events are compared here because external events are not yet reported in the current draft NUREG-1150. This is the first full-scope level III PRA study with a detailed quantitative safety goal comparison performed for DOE production reactors.

Wang, O.S.; Rainey, T.E.; Zentner, M.D.

1990-01-01T23:59:59.000Z

76

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

RAIS Risk Exposure Models for Radionuclides User's Guide RAIS Risk Exposure Models for Radionuclides User's Guide Note The RAIS presents this updated Risk calculator in response to the following: incorporating chemical-specific parameters from the lastest EPI release, addition of air as a media, and conversion to a new database structure. The previous RAIS Risk calculator presented Risks for radionuclides and chemcials together. Recent development of chemical and radionuclide exposure equations has necessitated that the RAIS separate the chemicals and the radionuclides. To calculate risks for chemicals, use the RAIS Risk Exposure Models for Chemicals calculator. Currently the agricultural equations for the RAIS chemical and radionuclide risk calculators are identical. The EPA's Preliminary Remediation Goals for

77

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

RAIS Chemical Risk Calculator RAIS Chemical Soil to Ground Water Calculator Radionuclide Calculators Preliminary Remediation Goals (PRGs) Radionuclide Calculator RAIS...

78

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

Radionuclide Decay Chain Radionuclide Decay Chain Using the Radionuclide Decay Chain Tool Click on the steps below for detailed instructions about each page of the Radionuclide Chain Tool. 1. Select Isotope 2. Decay Chain Table 3. Decay Chain Animation 1. Select Isotope Select the isotope of interest and click the "Submit" button. 2. Decay Chain Table A table of the ICRP 107 decay chain appears that displays the parent and all daughters in the decay chain through the stable isotope(s). The half-life, decay modes, and the branching fractions are given. Decay chains that are repeated as a result of multiple branching fractions are only presented once in the table. Text below the decay chain table contains decay mode definitions and further information on the daughters included in the +D slope factors for risk assessment purposes. A back button is provided to return to the main page. To watch an animated representation of the decay process, click the link "Click for visual diagram."

79

FTCP Site Specific Information - Office of Health, Safety & Security...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Security FTCP Site Specific Information - Office of Health, Safety & Security FTCP Agent Organization Name Phone E-Mail HSS HQ Pat Worthington Bradley Davy 301903-6929 301...

80

Criticality Safety Information Meeting for the Hanford Plutonium...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Evaluations Activity Report for Criticality Safety Information Meeting for the Plutonium Finishing Plant Dates of Activity : May 14, 2012 Report Preparer: Ivon Fergus...

Note: This page contains sample records for the topic "risk informed safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

Risk Exposure Models for Chemicals User's Guide Risk Exposure Models for Chemicals User's Guide 1. Introduction The purpose of this calculator is to assist Remedial Project Managers (RPMs), On Scene Coordinators (OSC's), risk assessors and others involved in decision-making at hazardous waste sites and to determine whether levels of contamination found at the site may warrant further investigation or site cleanup, or whether no further investigation or action may be required. The risk values presented on this site are chemical-specific values for individual contaminants in air, water, soil and biota that may warrant further investigation or site cleanup. It should be noted that the risks in this calculator are based upon human health risk and do not address potential ecological risk. Some sites in sensitive ecological settings may also need to be evaluated for potential

82

HTGR: an assessment of safety and investment risk  

SciTech Connect

Improvements in the present LWR designs which do not change the basic features that raise safety and economic concerns would not be expected to change public perception or be sufficient to encourage new nuclear investments by the utilities. The HTGR offers an attractive alternative, an alternative with proven operating experience and safety characteristics. This is demonstrated in this paper by an assessment of HTGR inherent safety features and by examining Fort St. Vrain operating experience data, which establish the HTGR as a forgiving design with respect to potential accidents. A further quantification of HTGR safety is made from a probabilistic risk assessment (PRA) of the 2240 MWt High-Temperature Gas-Cooled Reactor-Steam Cycle/Cogeneration (HTGR-SC/C) reference plant. These results are compared to NRC risk goals and achieved LWR safety. Finally, a proposed small HTGR reactor design is discussed. Although the relative costs and marketability of such a small reactor have yet to be determined, several additional passive safety characteristics of the small HTGR make such a plant essentially benign.

Fisher, C.; Fortescue, P.; Goodjohn, A.J.; Olsen, B.E.; Silady, F.A.

1984-11-01T23:59:59.000Z

83

A Risk Minimization Framework for Information Retrieval  

E-Print Network (OSTI)

A Risk Minimization Framework for Information Retrieval ChengXiang Zhai a John Lafferty b Carnegie Mellon University Abstract This paper presents a probabilistic information retrieval framework of decades of research in information retrieval, many different information retrieval models have been

Lafferty, John

84

A Risk Minimization Framework for Information Retrieval  

E-Print Network (OSTI)

A Risk Minimization Framework for Information Retrieval ChengXiang Zhai a John Lafferty b a University Abstract This paper presents a probabilistic information retrieval framework in which in information retrieval, many different information retrieval models have been proposed and studied. While

Lafferty, John

85

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

Risk Assessment Documents - ORR Risk Assessment Documents - ORR Bullet Baseline Risk Assessments Bullet Remedial Investigation/Feasibility Study Environmental Assessment Report South Campus Facility, Oak Ridge Tenn [DOE/OR/02-1274&D] Bullet Baseline Risk Assessment for Lower East Fork Poplar Creek [DOE/OR/1119 & D2 & V2] Bullet Remedial Investigation/ Feasibility Study Report for Lower Watts Bar Reservoir Operable Unit [DOE/OR/01 1282 & D1] [ORNL/ER-2] Bullet The Utility of Existing Data Conducting a CERCLA Baseline Risk Assessment for Lower Watts Bar Reservoir (draft) [ORNL/ER-?] Bullet East Fork Poplar Creek Sewer Line Beltway Remedial Investigation Report [DOE/OR/02-1119&D2] Bullet Screening Risk Assessments Bullet Preliminary Assessment of Radiation Doses to the Public from Cesium

86

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

U.S. EPA, Washington, D.C. 1992. Risk Assessment Forum. Wildlife Exposure Factors Handbook. Vol. I. United Staes Environmental Protection Agency. Office of Research and...

87

Nondestructive Evaluation: Risk-Informed In-Service Repair and Replacement: Draft Methodology  

Science Conference Proceedings (OSTI)

Code Case N-660, Revision 0, "Risk-Informed Safety Classification for Use in Risk-Informed Repair/Replacement Activities," was published by ASME and was developed to expand the breadth of risk-informed Section XI requirements to pressure boundary components. This report provides a generic draft methodology and technical basis for revisions to N-660 for Class 2 and 3 systems based on lessons learned from pilot application to Arkansas Nuclear One (ANO), Unit 2.

2009-12-23T23:59:59.000Z

88

Nuclear Safety Information Dashboard QuickStart Guide  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Safety Information Dashboard Nuclear Safety Information Dashboard QuickStart Guide September 2012 Office of Analysis (HS-24) Office of Environmental Protection, Sustainability Support and Corporate Safety Analysis Office of Health, Safety and Security (HSS) Purpose of Nuclear Safety Information (NSI) Dashboard * The 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. * ORPS reporting criteria associated with events at nuclear facilities have pre-assigned weighting factors according to their relative importance and are placed into groups. * This information can be evaluated to identify trends and, using insights from current events and nature of operations, enable

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Safety and Operational Guidelines | Open Energy Information  

Open Energy Info (EERE)

Community Login | Sign Up Search Page Edit History Facebook icon Twitter icon Safety and Operational Guidelines Jump to: navigation, search This article is a stub. You can...

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Dam Safety Program (Florida) | Open Energy Information  

Open Energy Info (EERE)

Summary Dam safety in Florida is a shared responsibility among the Florida Department of Environmental Protection (FDEP), the regional water management districts, the United...

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Visitor_Security_and_Safety_Information  

NLE Websites -- All DOE Office Websites (Extended Search)

in a designated lot near the main lobby and auditorium. Office of Health, Safety and Security Office of Security Operations Office of Headquarters Security Operations United...

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The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

a member of the Chemical Hazard Evaluation Group in the Biomedical and Environmental Information Analysis Section, Health Sciences Research Division, Oak Ridge National...

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

SciTech Connect

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

REEP, I.E.

1999-05-12T23:59:59.000Z

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Risk-Informed Maintenance Decision Analysis Methodology  

Science Conference Proceedings (OSTI)

Capabilities and proposed features of a risk-informed fossil plant maintenance planning process are described in this report. This research will serve as the basis for the development of a software module deployed in enterprise asset management systems, such as the Electric Power Research Institute's (EPRI's) PlantView suite. The report provides background on how risk-informed decisions can lead to improved plant availability by prioritizing activities based on component failure modes, probabilities, and...

2007-12-20T23:59:59.000Z

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Program on Technology Innovation: Probabilistic Risk Assessment Requirements for Passive Safety Systems  

Science Conference Proceedings (OSTI)

A key feature of the next generation of nuclear power reactors is a reliance on safety systems that are passive, that is, those that rely on natural physical laws and require minimal or no intervention by plant operators. These features are intended to significantly reduce the potential for serious events while simultaneously minimizing facility life-cycle costs. In addition to these features, these reactors will be licensed within a framework that will be risk-informed and performance-based. Because pro...

2007-12-20T23:59:59.000Z

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DOE/Contractor Fire Safety Workshop Information  

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The Office of Health, Safety and Security HSS Logo Department of Energy Seal Left Tab SEARCH Right Tab TOOLS Right Tab Left Tab HOME Right Tab Left Tab ABOUT US Right Tab Left Tab...

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OFFICE OF HEALH, SAFETY AND SECURITY INFORMATION COLLECTION PACKAGE  

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HEALH, SAFETY AND SECURITY HEALH, SAFETY AND SECURITY INFORMATION COLLECTION PACKAGE OMB 1910-0300: ES&H Reporting Systems Description of Collections April 10, 2012 The information obtained from DOE contractors by this information collection is used by Department management at the appropriate levels to manage the work pertaining to environment, safety and health throughout DOE and will include automated reporting of information into the following systems: Computerized Accident/Incident Reporting System (CAIRS) - The CAIRS is a database used to collect and analyze DOE and DOE contractor reports of injuries, illnesses, and other accidents that occur during DOE operations as described in DOE O 231.1B, Environment, Safety and Health Reporting. This system contains information from reporting contractors and

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Regulation of health, safety, and environmental risks,’ in A. Mitchell Polinsky and Steven Shavell, Handbook of law and economics  

E-Print Network (OSTI)

This paper provides a systematic review of the economic analysis of health, safety, and environmental regulations. Although the market failures that give rise to a rationale for intervention are well known, not all market failures imply that market risk levels are too great. Hazard warnings policies often can address informational failures. Some market failures may be exacerbated by government policies, particularly those embodying conservative risk assessment practices. Labor market estimates of the value of statistical life provide a useful reference point for the efficient risk tradeoffs for government regulation. Guided by restrictive legislative mandates, regulatory policies often strike a quite different balance with an inordinately high cost per life saved. The risk-risk analysis methodology enables analysts to assess the net safety implications of policy efforts. Inadequate regulatory enforcement and behavioral responses to regulation may limit their effectiveness, while rising societal wealth will continue to generate greater levels of health and safety. 1

W. Kip Viscusi; W. Kip Viscusi

2007-01-01T23:59:59.000Z

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The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

What's New What's New November 2013 Updates ECO mammalian SSLs were updated for cadmium, antimony , arsenic, inorganic, barium, Beryllium, chromium VI, cobalt, copper, lead, silver, vanadium, cyanide (total complex), methyl mercury, sulfide, thallium and tin. October 2013 Updates The biota intake rates for the radionuclide PRG and risk tools were updated to correct an improper units conversion. September 2013 Updates IRIS updates for 1,4-Dioxane and Biphenyl were completed. PPRTV values have been updated for Biphenyl, 3,4-Dichlorobenzotrifluoride, Trinitrophenylmethylnitramine (Tetryl), Endosulfan Sulfate, 1,1,2,2-Tetrachloroethane, Nitromethane, Dibenzothiophene, 2-Ethoxyethanol, 3,3'-Dimethoxybenzidine, Butylated hydroxytoluene, Ethyl Acetate, tert-Amyl Alcohol, 2,2-Difluoropropane,

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Chemical Profile Tool Chemical Profile Tool Using the Chemical Data Profiles Tool Click on the steps below for detailed instructions about each page of the Chemical Data Profiles Tool. 1. Select Chemical 2. Chemical Profile 1. Select Chemical Select the chemical of interest and click "submit". 2. Chemical Profile Basic information for the chemical is shown in the first section. Next, toxicity infomation (Oral RfDs, Inhalation RfCs, and Cancer Toxicity Values) is displayed in tables filled with data from IRIS, PPRTV, ATSDR, CALEPA, and HEAST. The last section contains an extensive list of parameters for the chemical followed by tables of parameters from EPI, CRC, PERRY, LANGE, and YAWS. Hover over the source to see more information. The "Back" button can be used to view a different chemical profile.

Note: This page contains sample records for the topic "risk informed safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

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Sites Sites These rankings are based on the EM-40 Release Site Methodology. Select a release site to receive information concerning that site. Please note that not all of the listed sites are linked to further information. Big Bayou Creek Big Bayou Creek Monitoring Station C-100 South Side Berm C-100 Trailer Complex Soil Contamination C-200 Underground Gasoline Tanks (UST) C-304 Bldg/HVAC Piping System (Soil Backfill) C-310 PCB Soil Contamination (West Side) C-331 PCB Soil Contamination (Southeast) C-331 PCB Soil Contamination (West) C-331 RCW Leak East Side C-331 RCW Leak Northwest Side C-333-A Vaporizer C-333 PCB Soil Contamination C-333 Cooling Tower Scrap Wood Pile C-333 PCB Soil Contamination (West) C-333 PCB Waste Storage Area C-333A Sewage Treatment Aeration Tank

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The Risk Assessment Information System  

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Chemical Toxicity MetaData Chemical Toxicity MetaData Using the Chemical Toxicity Metadata Tool Click on the steps below for detailed instructions about each page of the CPM Calculator. 1. Select Chemicals 2. Select Toxicity Metadata 3. Results 1. Select Chemicals Highlight the chemicals of interest and use the arrow buttons to move them to the "selected" box. 2. Select Toxicity Metadata Highlight the type of toxicity values to retrieve the desired toxicity metadata and press the "submit form" button. 3. Results The toxicity values and the metadata will be displayed in tables that are available for download. The Chemical Toxicity Metadata tool follows the same hierarchy as the Chemical Toxicity Value tool. Only one toxicity value type is given per chemical even though multiple sources may have values. The RAIS follows a hierarchy when selecting the toxicity values we use in PRG and risk calculations. The hierarchy is as follows:

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The Risk Assessment Information System  

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Glossary of Environmental Restoration Terms Glossary of Environmental Restoration Terms These definitions are from the United States Department of Energy (DOE) Oak Ridge Operations Office (ORO) Environmental Restoration/Waste Management Risk Assessment Program staff and affiliates and the following sources: Click on the letter that begins the term for which you are searching. To search for another term, at the end of each definition, click on the. If a link leaves the glossary to go to an outside page you will see a. A B C D E F G H I J K L M N O P Q R S T U V W X Y Z A Abatement: The reduction in degree or intensity of pollution. Absorbed Dose: The energy imparted to a unit mass of matter by ionizing radiation. The unit of absorbed dose is the rad or gray. One rad equals 100 ergs per gram. The amount of a substance absorbed into the body, usually

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The Risk Assessment Information System  

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Condensed Toxicity Summary for METHYLENE CHLORIDE Condensed Toxicity Summary for METHYLENE CHLORIDE NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. September 1993 Prepared by Cheryl B. Bast, Ph.D., Chemical Hazard Evaluation and Communication Program, Biomedical and Environmental Information Analysis Section, Health Sciences Research Division, *, Oak Ridge, Tennessee. Prepared for OAK RIDGE RESERVATION ENVIRONMENTAL RESTORATION PROGRAM. *Managed by Martin Marietta Energy Systems, Inc., for the U.S. Department of Energy under contract No. DE-AC05-84OR21400. Methylene chloride (CH2Cl2, CAS No. 75-09-2), also known as dichloromethane

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The Risk Assessment Information System  

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XYLENE XYLENE NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. EXECUTIVE SUMMARY 1. INTRODUCTION 2. METABOLISM AND DISPOSITION 2.1 ABSORPTION 2.2 DISTRIBUTION 2.3 METABOLISM 2.4 EXCRETION 3. NONCARCINOGENIC HEALTH EFFECTS 3.1 ORAL EXPOSURES 3.2 INHALATION EXPOSURES 3.3 OTHER ROUTES OF EXPOSURE 3.4 TARGET ORGANS/CRITICAL EFFECTS 4. CARCINOGENICITY 4.1 ORAL EXPOSURES 4.2 INHALATION EXPOSURES 4.3 OTHER ROUTES OF EXPOSURE 4.4 EPA WEIGHT-OF-EVIDENCE 4.5 CARCINOGENICITY SLOPE FACTORS 5. REFERENCES September 1994 Prepared by Carol S. Forsyth, Ph.D. and Rosmarie A. Faust, Ph.D., Chemical Hazard Evaluation Group, Biomedical and Environmental Information Analysis

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The Risk Assessment Information System  

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LITHIUM LITHIUM NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. May 1995 Prepared by Dennis M. Opresko, Ph.D., Chemical Hazard Evaluation and Communication Program, Biomedical and Environmental Information Analysis Section, Health Sciences Research Division, *, Oak Ridge, Tennessee. Prepared for OAK RIDGE RESERVATION ENVIRONMENTAL RESTORATION PROGRAM. *Managed by Martin Marietta Energy Systems, Inc., for the U.S. Department of Energy under contract No. DE-AC05-84OR21400. Lithium is an alkali metal similar to magnesium and sodium in its properties (Birch, 1988; Arena, 1986) and has a molecular weight of 6.941

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The Risk Assessment Information System  

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Condensed Toxicity Summary for ALUMINUM Condensed Toxicity Summary for ALUMINUM NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. September 1993 Prepared by Cheryl B. Bast, Chemical Hazard Evaluation Group, Biomedical Environmental Information Analysis Section, Health Sciences Research Division, *, Oak Ridge, Tennessee. Prepared for OAK RIDGE RESERVATION ENVIRONMENTAL RESTORATION PROGRAM. *Managed by Martin Marietta Energy Systems, Inc., for the U.S. Department of Energy under Contract No. DE-AC05-84OR21400. Aluminum is a silver-white flexible metal with a vast number of uses. It is poorly absorbed and efficiently eliminated; however, when absorption does

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The Risk Assessment Information System  

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ARSENIC ARSENIC NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. EXECUTIVE SUMMARY 1. INTRODUCTION 2. METABOLISM AND DISPOSITION 2.1 ABSORPTION 2.2 DISTRIBUTION 2.3 METABOLISM 2.4 EXCRETION 3. NONCARCINOGENIC HEALTH EFFECTS 3.1 ORAL EXPOSURES 3.2 INHALATION EXPOSURES 3.3 OTHER ROUTES OF EXPOSURE 3.4 TARGET ORGANS/CRITICAL EFFECTS 4. CARCINOGENICITY 4.1 ORAL EXPOSURES 4.2 INHALATION EXPOSURES 4.3 OTHER ROUTES OF EXPOSURE 4.4 EPA WEIGHT-OF-EVIDENCE 4.5 CARCINOGENICITY SLOPE FACTORS 5. REFERENCES April 1992 Prepared by: Dennis M. Opresko, Ph.D., Chemical Hazard Evaluation and Communication Group, Biomedical and Environmental Information Analysis

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Condensed Toxicity Summary for ETHYLBENZENE Condensed Toxicity Summary for ETHYLBENZENE NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. Prepared by: Dennis M. Opresko, Ph.D., Chemical Hazard Evaluation Group in the Biomedical and Environmental Information Analysis Section, Health Sciences Research Division, Oak Ridge National Laboratory*. Prepared for: Oak Ridge Reservation Environmental Restoration Program. *Managed by Martin Marietta Energy Systems, Inc., for the U.S. Department of Energy under Contract No. DE-AC05-84OR21400. Ethylbenzene is a colorless, flammable liquid with a pungent odor (Cavender 1994). The water solubility of ethylbenzene is 0.014 g/100 mL and its vapor

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The Risk Assessment Information System  

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BENZO[A]PYRENE BENZO[A]PYRENE NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. December 1994 Prepared by: Rosmarie A. Faust, Ph.D., Chemical Hazard Evaluation Group, Biomedical and Environmental Information Analysis Section, Health Sciences Research Division, *, Oak Ridge, Tennessee. Prepared for: OAK RIDGE RESERVATION ENVIRONMENTAL RESTORATION PROGRAM. *Managed by Martin Marietta Energy Systems, Inc., for the U.S. Department of Energy under Contract No. DE-AC05-84OR21400. Benzo[a]pyrene is a polycyclic aromatic hydrocarbon (PAH) that can be derived from coal tar. Benzo[a]pyrene occurs ubiquitously in products of

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The Risk Assessment Information System  

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Condensed Toxicity Summary for AROCLOR-1260 Condensed Toxicity Summary for AROCLOR-1260 NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. Prepared by C. B. Bast, Ph.D., D.A.B.T., Chemical Hazard Evaluation Group, Biomedical and Environmental Information Analysis Section, Health Sciences Research Division, *. Prepared for OAK RIDGE RESERVATION ENVIRONMENTAL RESTORATION PROGRAM *Managed by Martin Marietta Energy Systems, Inc., for the U.S. Department of Energy under Contract No. DE-AC05-84OR21400 Aroclor® 1260 is a polychlorinated biphenyl (PCB) mixture containing approximately 38% C12H4Cl6, 41% C12H3Cl7, 8% C12H2Cl8, and 12% C12H5Cl5

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The Risk Assessment Information System  

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Condensed Toxicity Summary for THALLIUM Condensed Toxicity Summary for THALLIUM NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. DECEMBER 1994 Prepared by: Tim Borges and Mary Lou Daugherty, Chemical Hazard Evaluation Group, Biomedical and Environmental Information Analysis Section, Health Sciences Research Division, Oak Ridge National Laboratory*, Oak Ridge, Tennessee. Prepared for: Oak Ridge Reservation Environmental Restoration Program. *Managed by Martin Marietta Energy Systems, Inc., for the U.S. Department of Energy under Contract No. DE-AC05-84OR21400. This report is an update of the Toxicity Summary for Thallium (CAS Registry

113

The Risk Assessment Information System  

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Condensed Toxicity Summary for ASBESTOS Condensed Toxicity Summary for ASBESTOS NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. August 1995 Prepared by: Rosmarie A. Faust, Ph.D., Chemical Hazard Evaluation Group, Biomedical and Environmental Information Analysis Section, Health Sciences Research Division, *, Oak Ridge, Tennessee. Prepared for OAK RIDGE RESERVATION ENVIRONMENTAL RESTORATION PROGRAM. *Managed by Lockheed Martin Energy Systems, Inc., for the U.S. Department of Energy under Contract No. DE-AC05-84OR21400. Asbestos (CAS No. 1332-21-4) is the generic name for a variety of naturally formed hydrated silicates containing metal cations such as sodium,

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The Risk Assessment Information System  

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Condensed Toxicity Summary for METHYL ISOBUTYL KETONE Condensed Toxicity Summary for METHYL ISOBUTYL KETONE NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. July 1995 Prepared by Rosmarie A. Faust, Ph.D., Chemical Hazard Evaluation and Communication Program, Biomedical and Environmental Information Analysis Section, Health Sciences Research Division, *, Oak Ridge, Tennessee. Prepared for OAK RIDGE RESERVATION ENVIRONMENTAL RESTORATION PROGRAM. *Managed by Lockheed Martin Energy Systems, Inc., for the U.S. Department of Energy under Contract No. DE-AC05-84OR21400. Methyl isobutyl ketone (MIBK) (CAS Reg. No. 108-10-1), a clear liquid with

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The Risk Assessment Information System  

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-DINITROTOLUENE -DINITROTOLUENE NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. Prepared by: Rosmarie A. Faust, Ph.D., Chemical Hazard Evaluation Group in the Biomedical and Environmental Information Analysis Section, Health Sciences Research Division, Oak Ridge National Laboratory*. Prepared for: Oak Ridge Reservation Environmental Restoration Program. *Managed by Martin Marietta Energy Systems, Inc., for the U.S. Department of Energy under Contract No. DE-AC05-84OR21400. This report is an update of the Toxicity Summary for 2,4-Dinitrotoluene (CAS Registry No. 121-14-2). The original summary for this chemical was

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The Risk Assessment Information System  

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COPPER COPPER NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. EXECUTIVE SUMMARY 1. INTRODUCTION 2. METABOLISM AND DISPOSITION 2.1 ABSORPTION 2.2 DISTRIBUTION 2.3 METABOLISM 2.4 EXCRETION 3. NONCARCINOGENIC HEALTH EFFECTS 3.1 ORAL EXPOSURES 3.2 INHALATION EXPOSURES 3.3 OTHER ROUTES OF EXPOSURE 3.4 TARGET ORGANS/CRITICAL EFFECTS 4. CARCINOGENICITY 4.1 ORAL EXPOSURES 4.2 INHALATION EXPOSURES 4.3 OTHER ROUTES OF EXPOSURE 4.4 EPA WEIGHT-OF-EVIDENCE 4.5 CARCINOGENICITY SLOPE FACTORS 5. REFERENCES DECEMBER 1992 Prepared by: Rosmarie A. Faust, Ph.D., Chemical Hazard Evaluation and Communication Group, Biomedical and Environmental Information Analysis

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The Risk Assessment Information System  

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Formal Toxicity Summary for STRONTIUM-90 Formal Toxicity Summary for STRONTIUM-90 NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. EXECUTIVE SUMMARY 1. INTRODUCTION 2. METABOLISM AND DISPOSITION 3. NONCARCINOGENIC HEALTH EFFECTS 3.1 ORAL EXPOSURES 3.2 INHALATION EXPOSURES 3.3 OTHER ROUTES OF EXPOSURE 3.4 TARGET ORGANS/CRITICAL EFFECTS 4. CARCINOGENICITY 4.1 ORAL EXPOSURES 4.2 INHALATION EXPOSURES 4.3 OTHER ROUTES OF EXPOSURE 4.4 EPA WEIGHT-OF-EVIDENCE 4.5 CARCINOGENICITY SLOPE FACTORS 5. REFERENCES DECEMBER 1994 Prepared by: Sylvia S. Talmage, Ph.D., D.A.B.T., Chemical Hazard Evaluation Group, Biomedical and Environmental Information Analysis Section, Health

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THALLIUM THALLIUM NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. EXECUTIVE SUMMARY 1. INTRODUCTION 2. METABOLISM AND DISPOSITION 2.1 ABSORPTION 2.2 DISTRIBUTION 2.3 METABOLISM 2.4 EXCRETION 3. NONCARCINOGENIC HEALTH EFFECTS 3.1 ORAL EXPOSURES 3.2 INHALATION EXPOSURES 3.3 OTHER ROUTES OF EXPOSURE 3.4 TARGET ORGANS/CRITICAL EFFECTS 4. CARCINOGENICITY 4.1 ORAL EXPOSURES 4.2 CARCINOGENICITY SLOPE FACTORS 5. REFERENCES DECEMBER 1994 Prepared by: Tim Borges and Mary Lou Daugherty, Chemical Hazard Evaluation Group, Biomedical and Environmental Information Analysis Section, Health Sciences Research Division, Oak Ridge National Laboratory*, Oak Ridge,

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The Risk Assessment Information System  

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Condensed Toxicity Summary for MANGANESE Condensed Toxicity Summary for MANGANESE NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. July 1995 Prepared by A. A. Francis and C. Forsyth, Chemical Hazard Evaluation Group, Biomedical and Environmental Information Analysis Section, Health Sciences Research Division, *, Oak Ridge, Tennessee Prepared for OAK RIDGE RESERVATION ENVIRONMENTAL RESTORATION PROGRAM *Managed by Lockheed Martin Energy Systems, Inc., for the U.S. Department of Energy under Contract No. DE-AC05-84OR21400 Manganese is an essential trace element in humans that can elicit a variety of serious toxic responses upon prolonged exposure to elevated

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2-DICHLOROETHANE 2-DICHLOROETHANE NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. May 1994 Prepared by Dennis M. Opresko, Ph.D., Chemical Hazard Evaluation and Communication Program, Biomedical and Environmental Information Analysis Section, Health Sciences Research Division, *, Oak Ridge, Tennessee. Prepared for OAK RIDGE RESERVATION ENVIRONMENTAL RESTORATION PROGRAM. *Managed by Martin Marietta Energy Systems, Inc., for the U.S. Department of Energy under contract No. DE-AC05-84OR21400. 1,2-Dichloroethane is used primarily in the manufacture of vinyl chloride, as well as in the synthesis of tetrachloroethylene, trichloroethylene,

Note: This page contains sample records for the topic "risk informed safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

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HEPTACHLOR HEPTACHLOR NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. EXECUTIVE SUMMARY 1. INTRODUCTION 2. METABOLISM AND DISPOSITION 2.1 ABSORPTION 2.2 DISTRIBUTION 2.3 METABOLISM 2.4 EXCRETION 3. NONCARCINOGENIC HEALTH EFFECTS 3.1 ORAL EXPOSURES 3.2 INHALATION EXPOSURES 3.3 OTHER ROUTES OF EXPOSURE 3.4 TARGET ORGANS/CRITICAL EFFECTS 4. CARCINOGENICITY 4.1 ORAL EXPOSURES 4.2 INHALATION EXPOSURES 4.3 OTHER ROUTES OF EXPOSURE 4.4 EPA WEIGHT-OF-EVIDENCE 4.5 CARCINOGENICITY SLOPE FACTORS 5. REFERENCES The toxicity information included in this summary was researched and compiled by R. A. Faust, Ph.D., who is a member of the Chemical Hazard

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The Risk Assessment Information System  

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CHLORDANE CHLORDANE NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. December 1994 Prepared by: Carol S. Forsyth, Ph.D., Chemical Hazard Evaluation Group, Biomedical and Environmental Information Analysis Section, Health Sciences Research Division, *, Oak Ridge, Tennessee. Prepared for: OAK RIDGE RESERVATION ENVIRONMENTAL RESTORATION PROGRAM. *Managed by Martin Marietta Energy Systems Inc., for the U.S. Department of Energy under Contract No. DE-AC05-84OR21400. Technical grade chlordane is a mixture of structurally related compounds including trans-chlordane, cis-chlordane, -chlordene, heptachlor, and

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The Risk Assessment Information System  

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CYANIDE CYANIDE NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. EXECUTIVE SUMMARY 1. INTRODUCTION 2. METABOLISM AND DISPOSITION 2.1 ABSORPTION 2.2 DISTRIBUTION 2.3 METABOLISM 2.4 EXCRETION 3. NONCARCINOGENIC HEALTH EFFECTS 3.1 ORAL EXPOSURES 3.2 INHALATION EXPOSURES 3.3 OTHER ROUTES OF EXPOSURE 3.4 TARGET ORGANS/CRITICAL EFFECTS 4. CARCINOGENICITY 4.1 ORAL EXPOSURES 4.2 INHALATION EXPOSURES 4.3 OTHER ROUTES OF EXPOSURE 4.4 EPA WEIGHT-OF-EVIDENCE 4.5 CARCINOGENICITY SLOPE FACTORS 5. REFERENCES February 1994 Prepared by Rosmarie A. Faust, Ph.D., Chemical Hazard Evaluation and Communication Group, Biomedical and Environmental Information Analysis

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FLUORANTHENE FLUORANTHENE NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. August 1993 Prepared by Rosmarie A. Faust, Ph.D., Chemical Hazard Evaluation and Communication Program, Biomedical and Environmental Information Analysis Section, Health Sciences Research Division, *, Oak Ridge, Tennessee. Prepared for OAK RIDGE RESERVATION ENVIRONMENTAL RESTORATION PROGRAM. *Managed by Martin Marietta Energy Systems, Inc., for the U.S. Department of Energy under contract No. DE-AC05-84OR21400. Fluoranthene is a polycyclic aromatic hydrocarbon (PAH) that can be derived from coal tar. Occurring ubiquitously in products of incomplete combustion

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The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

LEAD LEAD NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. EXECUTIVE SUMMARY 1. INTRODUCTION 2. METABOLISM AND DISPOSITION 2.1 ABSORPTION 2.2 DISTRIBUTION 2.3 METABOLISM 2.4 EXCRETION 3. NONCARCINOGENIC HEALTH EFFECTS 3.1 HUMAN 3.2 ANIMAL 3.3 REFERENCE DOSE 3.4 TARGET ORGANS/CRITICAL EFFECTS 4. CARCINOGENICITY 4.1 HUMAN 4.2 ANIMAL 4.3 EPA WEIGHT-OF-EVIDENCE 4.4 CARCINOGENICITY SLOPE FACTORS 5. REFERENCES December 1994 Prepared by Kowetha A. Davidson, Ph.D., Chemical Hazard Evaluation and Communication Program, Biomedical and Environmental Information Analysis Section, Health Sciences Research Division, *, Oak Ridge, Tennessee.

126

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

Condensed Toxicity Summary for 1,4-DICHLOROBENZENE Condensed Toxicity Summary for 1,4-DICHLOROBENZENE NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. Prepared by: James C. Norris, Ph.D, Chemical Hazard Evaluation Group in the Biomedical and Environmental Information Analysis Section, Health Sciences Research Division, Oak Ridge National Laboratory*. Prepared for: Oak Ridge Reservation Environmental Restoration Program. *Managed by Martin Marietta Energy Systems, Inc., for the U.S. Department of Energy under Contract No. DE-AC05-84OR21400. 1,4-Dichlorobenzene (CAS 106-46-7), also referred to as para-DCB, p-DCB, paracide, Paramoth®, Parazene®, PDB, and Santochlor®, has a benzene ring

127

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

Condensed Toxicity Summary for 2,6-DINITROTOLUENE Condensed Toxicity Summary for 2,6-DINITROTOLUENE NOTE: Although the toxicity values presented in these toxicity profiles were correct at the time they were produced, these values are subject to change. Users should always refer to the Toxicity Value Database for the current toxicity values. Prepared by: Rosmarie A. Faust, Ph.D., Chemical Hazard Evaluation Group in the Biomedical and Environmental Information Analysis Section, Health Sciences Research Division, Oak Ridge National Laboratory*. Prepared for: Oak Ridge Reservation Environmental Restoration Program. *Managed by Martin Marietta Energy Systems, Inc., for the U.S. Department of Energy under Contract No. DE-AC05-84OR21400. 2,6-Dinitrotoluene (2,6-DNT; 2-methyl-1,3-dinitrobenzene; CAS Reg. No. 606-20-2) is a pale yellow crystalline solid and one of six possible

128

Development of the Nuclear Safety Information Dashboard - September 2012 |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Development of the Nuclear Safety Information Dashboard - September Development of the Nuclear Safety Information Dashboard - September 2012 Development of the Nuclear Safety Information Dashboard - September 2012 September 2012 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. The sum of the severity-weighted factors for the sixty-five ORPS Reporting Criteria equals 100%. Paired pairing is an analytical tool used to determine weighted factors. A team evaluated pairs of ORPS reporting criteria and concurred on the relative importance of each pair. Each ORPS reporting criterion in a group was compared with one other ORPS reporting

129

Development of the Nuclear Safety Information Dashboard - September 2012 |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Development of the Nuclear Safety Information Dashboard - September Development of the Nuclear Safety Information Dashboard - September 2012 Development of the Nuclear Safety Information Dashboard - September 2012 September 2012 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. The sum of the severity-weighted factors for the sixty-five ORPS Reporting Criteria equals 100%. Paired pairing is an analytical tool used to determine weighted factors. A team evaluated pairs of ORPS reporting criteria and concurred on the relative importance of each pair. Each ORPS reporting criterion in a group was compared with one other ORPS reporting

130

The Risk Assessment Information System  

NLE Websites -- All DOE Office Websites (Extended Search)

Prepared by C. B. Bast, Ph.D., D.A.B.T., Chemical Hazard Evaluation Group, Prepared by C. B. Bast, Ph.D., D.A.B.T., Chemical Hazard Evaluation Group, Biomedical and Environmental Information Analysis Section, Health Sciences Research Division, *. Prepared for OAK RIDGE RESERVATION ENVIRONMENTAL RESTORATION PROGRAM *Managed by Martin Marietta Energy Systems, Inc., for the U.S. Department of Energy under Contract No. DE-AC05-84OR21400 Aroclor® 1254 is a polychlorinated biphenyl (PCB) mixture containing approximately 21% C12H6Cl4, 48% C12H5Cl5, 23% C12H4Cl6, and 6% C12H3Cl7 with an average chlorine content of 54% (USAF 1989). PCBs are inert, thermally and physically stable, and have dielectric properties. In the environment, the behavior of PCB mixtures is directly correlated to the degree of chlorination. Aroclor® is strongly sorbed to soil and remains

131

Risk and Safety Assessments - Nuclear Engineering Division (Argonne...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

132

State Traffic Safety Information - Fatal Crashes Involving Speeding :  

NLE Websites -- All DOE Office Websites (Extended Search)

Illinois (2007-2009) Illinois (2007-2009) Research Menu Data/Tools Apps Resources Let's Talk Research Alpha You are here Data.gov » Communities » Research » Data State Traffic Safety Information - Fatal Crashes Involving Speeding : Illinois (2007-2009) Dataset Summary Description The State Traffic Safety Information (STSI) portal is part of the larger Fatality Analysis Reporting System (FARS) Encyclopedia. STSI provides state-by-state traffic safety profiles, including: crash data, lives saved/savable, legislation, economic costs, grant funding, alcohol related crash data, performance measures, and geographic maps of crash data. Tags {geospatial,fatality,crash,data,safety,roadway,vehicle,human,person} Dataset Ratings Overall 0 No votes yet Data Utility 0 No votes yet Usefulness 0 No votes yet

133

State Traffic Safety Information - Fatal Crashes Involving a Large Truck :  

NLE Websites -- All DOE Office Websites (Extended Search)

Hawaii (2007-2009) Hawaii (2007-2009) Research Menu Data/Tools Apps Resources Let's Talk Research Alpha You are here Data.gov » Communities » Research » Data State Traffic Safety Information - Fatal Crashes Involving a Large Truck : Hawaii (2007-2009) Dataset Summary Description The State Traffic Safety Information (STSI) portal is part of the larger Fatality Analysis Reporting System (FARS) Encyclopedia. STSI provides state-by-state traffic safety profiles, including: crash data, lives saved/savable, legislation, economic costs, grant funding, alcohol related crash data, performance measures, and geographic maps of crash data. Tags {geospatial,fatality,crash,data,safety,roadway,vehicle,human,person} Dataset Ratings Overall 0 No votes yet Data Utility 0 No votes yet Usefulness 0 No votes yet

134

State Traffic Safety Information - Fatal Crashes Involving a Large Truck :  

NLE Websites -- All DOE Office Websites (Extended Search)

Delaware (2007-2009) Delaware (2007-2009) Research Menu Data/Tools Apps Resources Let's Talk Research Alpha You are here Data.gov » Communities » Research » Data State Traffic Safety Information - Fatal Crashes Involving a Large Truck : Delaware (2007-2009) Dataset Summary Description The State Traffic Safety Information (STSI) portal is part of the larger Fatality Analysis Reporting System (FARS) Encyclopedia. STSI provides state-by-state traffic safety profiles, including: crash data, lives saved/savable, legislation, economic costs, grant funding, alcohol related crash data, performance measures, and geographic maps of crash data. Tags {geospatial,fatality,crash,data,safety,roadway,vehicle,human,person} Dataset Ratings Overall 0 No votes yet Data Utility 0 No votes yet Usefulness

135

State Traffic Safety Information - Fatal Crashes Involving Speeding :  

NLE Websites -- All DOE Office Websites (Extended Search)

Hawaii (2007-2009) Research Menu Data/Tools Apps Resources Let's Talk Research Alpha You are here Data.gov » Communities » Research » Data State Traffic Safety Information - Fatal Crashes Involving Speeding : Hawaii (2007-2009) Dataset Summary Description The State Traffic Safety Information (STSI) portal is part of the larger Fatality Analysis Reporting System (FARS) Encyclopedia. STSI provides state-by-state traffic safety profiles, including: crash data, lives saved/savable, legislation, economic costs, grant funding, alcohol related crash data, performance measures, and geographic maps of crash data. Tags {geospatial,fatality,crash,data,safety,roadway,vehicle,human,person} Dataset Ratings Overall 0 No votes yet Data Utility 0 No votes yet Usefulness 0 No votes yet

136

State Traffic Safety Information - Fatal Crashes Involving a Large Truck :  

NLE Websites -- All DOE Office Websites (Extended Search)

District of Columbia (2007-2009) District of Columbia (2007-2009) Research Menu Data/Tools Apps Resources Let's Talk Research Alpha You are here Data.gov » Communities » Research » Data State Traffic Safety Information - Fatal Crashes Involving a Large Truck : District of Columbia (2007-2009) Dataset Summary Description The State Traffic Safety Information (STSI) portal is part of the larger Fatality Analysis Reporting System (FARS) Encyclopedia. STSI provides state-by-state traffic safety profiles, including: crash data, lives saved/savable, legislation, economic costs, grant funding, alcohol related crash data, performance measures, and geographic maps of crash data. Tags {geospatial,fatality,crash,data,safety,roadway,vehicle,human,person} Dataset Ratings Overall 0 No votes yet Data Utility

137

State Traffic Safety Information - Fatal Single Vehicle Crashes : District  

NLE Websites -- All DOE Office Websites (Extended Search)

District District of Columbia (2007-2009) Research Menu Data/Tools Apps Resources Let's Talk Research Alpha You are here Data.gov » Communities » Research » Data State Traffic Safety Information - Fatal Single Vehicle Crashes : District of Columbia (2007-2009) Dataset Summary Description The State Traffic Safety Information (STSI) portal is part of the larger Fatality Analysis Reporting System (FARS) Encyclopedia. STSI provides state-by-state traffic safety profiles, including: crash data, lives saved/savable, legislation, economic costs, grant funding, alcohol related crash data, performance measures, and geographic maps of crash data. Tags {geospatial,fatality,crash,data,safety,roadway,vehicle,human,person} Dataset Ratings Overall 0 No votes yet Data Utility 0 No votes yet

138

State Traffic Safety Information - Fatal Crashes Involving Speeding : Iowa  

NLE Websites -- All DOE Office Websites (Extended Search)

Iowa Iowa (2007-2009) Research Menu Data/Tools Apps Resources Let's Talk Research Alpha You are here Data.gov » Communities » Research » Data State Traffic Safety Information - Fatal Crashes Involving Speeding : Iowa (2007-2009) Dataset Summary Description The State Traffic Safety Information (STSI) portal is part of the larger Fatality Analysis Reporting System (FARS) Encyclopedia. STSI provides state-by-state traffic safety profiles, including: crash data, lives saved/savable, legislation, economic costs, grant funding, alcohol related crash data, performance measures, and geographic maps of crash data. Tags {geospatial,fatality,crash,data,safety,roadway,vehicle,human,person} Dataset Ratings Overall 0 No votes yet Data Utility 0 No votes yet Usefulness 0 No votes yet

139

State Traffic Safety Information - Fatal Crashes Involving a Large Truck :  

NLE Websites -- All DOE Office Websites (Extended Search)

Indiana (2007-2009) Indiana (2007-2009) Research Menu Data/Tools Apps Resources Let's Talk Research Alpha You are here Data.gov » Communities » Research » Data State Traffic Safety Information - Fatal Crashes Involving a Large Truck : Indiana (2007-2009) Dataset Summary Description The State Traffic Safety Information (STSI) portal is part of the larger Fatality Analysis Reporting System (FARS) Encyclopedia. STSI provides state-by-state traffic safety profiles, including: crash data, lives saved/savable, legislation, economic costs, grant funding, alcohol related crash data, performance measures, and geographic maps of crash data. Tags {geospatial,fatality,crash,data,safety,roadway,vehicle,human,person} Dataset Ratings Overall 0 No votes yet Data Utility 0 No votes yet Usefulness

140

State Traffic Safety Information - Fatal Crashes Involving a Large Truck :  

NLE Websites -- All DOE Office Websites (Extended Search)

Idaho (2007-2009) Idaho (2007-2009) Research Menu Data/Tools Apps Resources Let's Talk Research Alpha You are here Data.gov » Communities » Research » Data State Traffic Safety Information - Fatal Crashes Involving a Large Truck : Idaho (2007-2009) Dataset Summary Description The State Traffic Safety Information (STSI) portal is part of the larger Fatality Analysis Reporting System (FARS) Encyclopedia. STSI provides state-by-state traffic safety profiles, including: crash data, lives saved/savable, legislation, economic costs, grant funding, alcohol related crash data, performance measures, and geographic maps of crash data. Tags {geospatial,fatality,crash,data,safety,roadway,vehicle,human,person} Dataset Ratings Overall 0 No votes yet Data Utility 0 No votes yet Usefulness 0 No votes yet

Note: This page contains sample records for the topic "risk informed safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

State Traffic Safety Information - Fatal Crashes Involving Speeding :  

NLE Websites -- All DOE Office Websites (Extended Search)

Kansas (2007-2009) Research Menu Data/Tools Apps Resources Let's Talk Research Alpha You are here Data.gov » Communities » Research » Data State Traffic Safety Information - Fatal Crashes Involving Speeding : Kansas (2007-2009) Dataset Summary Description The State Traffic Safety Information (STSI) portal is part of the larger Fatality Analysis Reporting System (FARS) Encyclopedia. STSI provides state-by-state traffic safety profiles, including: crash data, lives saved/savable, legislation, economic costs, grant funding, alcohol related crash data, performance measures, and geographic maps of crash data. Tags {geospatial,fatality,crash,data,safety,roadway,vehicle,human,person} Dataset Ratings Overall 0 No votes yet Data Utility 0 No votes yet Usefulness 0 No votes yet

142

State Traffic Safety Information - Fatal Crashes Involving Speeding : Maine  

NLE Websites -- All DOE Office Websites (Extended Search)

Maine Maine (2007-2009) Research Menu Data/Tools Apps Resources Let's Talk Research Alpha You are here Data.gov » Communities » Research » Data State Traffic Safety Information - Fatal Crashes Involving Speeding : Maine (2007-2009) Dataset Summary Description The State Traffic Safety Information (STSI) portal is part of the larger Fatality Analysis Reporting System (FARS) Encyclopedia. STSI provides state-by-state traffic safety profiles, including: crash data, lives saved/savable, legislation, economic costs, grant funding, alcohol related crash data, performance measures, and geographic maps of crash data. Tags {geospatial,fatality,crash,data,safety,roadway,vehicle,human,person} Dataset Ratings Overall 0 No votes yet Data Utility 0 No votes yet Usefulness 0 No votes yet

143

Transactions of the nineteenth water reactor safety information meeting  

DOE Green Energy (OSTI)

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.

Weiss, A.J. (comp.)

1991-10-01T23:59:59.000Z

144

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

Science Conference Proceedings (OSTI)

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

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

1998-02-01T23:59:59.000Z

145

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

SciTech Connect

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

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

1997-07-01T23:59:59.000Z

146

Making the business case for process safety using value-at-risk concepts  

E-Print Network (OSTI)

An increasing emphasis on chemical process safety over the last two decades has led to the development and application of powerful risk assessment tools. Hazard analysis and risk evaluation techniques have developed to the point where quantitatively meaningful risks can be calculated for processes and plants. However, the results are typically presented in semi-quantitative �ranked list� or �categorical matrix� formats, which are certainly useful but not optimal for making business decisions. A relatively new technique for performing valuation under uncertainty, Value at Risk (VaR), has been developed in the financial world. VaR is a method of evaluating the probability of a gain or loss by a complex venture, by examining the stochastic behavior of its components. We believe that combining quantitative risk assessment techniques with VaR concepts will bridge the gap between engineers and scientists who determine process risk and business leaders and policy makers who evaluate, manage, or regulate risk. We present a few basic examples of the application of VaR to hazard analysis in the chemical process industry. We discover that by using the VaR tool we are able to present data that allows management to make better informed decisions.

Fang, Jayming Sha

2006-08-01T23:59:59.000Z

147

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

SciTech Connect

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).

Daling, P.M.; Lavender, J.C. [Pacific Northwest National Lab., Richland, WA (United States)

1996-07-01T23:59:59.000Z

148

Survey on the Use of Configuration Risk and Safety Management Tools at Nuclear Power Plants  

Science Conference Proceedings (OSTI)

A joint project of Electricite de France (EDF) and EPRI, this project analyzed use of configuration safety and risk management tools at nuclear power plants.

1998-09-24T23:59:59.000Z

149

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

Science Conference Proceedings (OSTI)

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

William E. Kastenberg; Edward Blandford; Lance Kim

2009-03-31T23:59:59.000Z

150

Modeling Credit Risk with Partial Information  

E-Print Network (OSTI)

This paper provides an alternative approach to Duffie and Lando [Econometrica 69 (2001) 633-664] for obtaining a reduced form credit risk model from a structural model. Duffie and Lando obtain a reduced form model by constructing an economy where the market sees the manager's information set plus noise. The noise makes default a surprise to the market. In contrast, we obtain a reduced form model by constructing an economy where the market sees a reduction of the manager's information set. The reduced information makes default a surprise to the market. We provide an explicit formula for the default intensity based on an Azema martingale, and we use excursion theory of Brownian motions to price risky debt.

Cetin, Umut; Protter, Philip; Yildirim, Yildiray; 10.1214/105051604000000251

2008-01-01T23:59:59.000Z

151

Lessons Learned From Implementation of Westinghouse Owners Group Risk-Informed Inservice Inspection Methodology for Piping  

SciTech Connect

Risk-informed inservice inspection (ISI) programs have been in use for over seven years as an alternative to current regulatory requirements in the development and implementation of ISI programs for nuclear plant piping systems. Programs using the Westinghouse Owners Group (WOG) (now known as the Pressurized Water Reactor Owners Group - PWROG) risk-informed ISI methodology have been developed and implemented within the U.S. and several other countries. Additionally, many plants have conducted or are in the process of conducting updates to their risk-informed ISI programs. In the development and implementation of these risk-informed ISI programs and the associated updates to those programs, the following important lessons learned have been identified and are addressed. Concepts such as 'loss of inventory', which are typically not modeled in a plant's probabilistic risk assessment (PRA) model for all systems. The importance of considering operator actions in the identification of consequences associated with a piping failure and the categorization of segments as high safety significant (HSS) or low safety significant (LSS). The impact that the above considerations have had on the large early release frequency (LERF) and categorization of segments as HSS or LSS. The importance of automation. Making the update process more efficient to reduce costs associated with maintaining the risk-informed ISI program. The insights gained are associated with many of the steps in the risk-informed ISI process including: development of the consequences associated with piping failures, categorization of segments, structural element selection and program updates. Many of these lessons learned have impacted the results of the risk-informed ISI programs and have impacted the updates to those programs. This paper summarizes the lessons learned and insights gained from the application of the WOG risk-informed ISI methodology in the U.S., Europe and Asia. (authors)

Stevenson, Paul R.; Haessler, Richard L. [Westinghouse Electric Company, LLC (United States); McNeill, Alex [Dominion Energy, Innsbrook Technical Center (United States); Pyne, Mark A. [Duke Energy (United States); West, Raymond A. [Dominion Nuclear Connecticut, Inc. - Dominion Generation (United States)

2006-07-01T23:59:59.000Z

152

Achieving safety/risk goals for less ATR backup power upgrades  

Science Conference Proceedings (OSTI)

The Advanced Test Reactor probabilistic risk assessment for internal fire and flood events defined a relatively high risk for a total loss of electric power possibly leading to core damage. Backup power sources were disabled due to fire and flooding in the diesel generator area with propagation of the flooding to a common switchgear room. The ATR risk assessment was employed to define options for relocation of backup power system components to achieve needed risk reduction while minimizing costs. The risk evaluations were performed using sensitivity studies and importance measures. The risk-based evaluations of relocation options for backup power systems saved over $3 million from what might have been otherwise considered {open_quotes}necessary{close_quotes} for safety/risk improvement. The ATR experience shows that the advantages of a good risk assessment are to define risk significance, risk specifics, and risk solutions which enable risk goals to be achieved at the lowest cost.

Atkinson, S.A.

1995-10-01T23:59:59.000Z

153

Information quality, trust, and risk perceptions in electronic data exchanges  

Science Conference Proceedings (OSTI)

This study investigates the influence of information quality, trust and risk perceptions on the expected transaction performance of inter-organizational data exchanges and on the user intent to continue using the exchange. This study provides empirical ... Keywords: Competence-trust, Electronic transaction performance, Exchange-risk, Goodwill-trust, Information quality, Intent to use, Performance-risk

Andreas I. Nicolaou; Mohammed Ibrahim; Eric Van Heck

2013-01-01T23:59:59.000Z

154

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

SciTech Connect

This three-volume report contains 90 papers out of the 102 that were presented at the Twenty-First Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 25--27, 1993. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Germany, Japan, Russia, Switzerland, Taiwan, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Individual papers have been cataloged separately. This document, Volume 1 covers the following topics: Advanced Reactor Research; Advanced Instrumentation and Control Hardware; Advanced Control System Technology; Human Factors Research; Probabilistic Risk Assessment Topics; Thermal Hydraulics; and Thermal Hydraulic Research for Advanced Passive Light Water Reactors.

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

1994-04-01T23:59:59.000Z

155

Environmental Health & Safety Risk Categories for EH&S Laboratory Inspections  

E-Print Network (OSTI)

and safety certification Training/ SOPs Risk Category Training and Procedure Requirements Level 1 - Requires Revised 01/11/2011 "Carcinogens" are chemicals which cause cancer. For the purpose of the CHP, chemicals

Elser, Jim

156

Risk Neutral Investors Do Not Acquire Information¤  

E-Print Network (OSTI)

Kerry and Shmuel Baruch, “Information in Securities Markets:and Pietro Veronesi, “Information Acquisition in FinancialDo Not Acquire Information ? Marc-Andreas Muendler ¶

Muendler, Marc-Andreas

2005-01-01T23:59:59.000Z

157

Risk Neutral Investors Do Not Acquire Information¤  

E-Print Network (OSTI)

attempt to extract market information from asset price (more than investors’ market information. Market clearing orasset price omits market information. Unrelated assumptions

Muendler, Marc-Andreas

2005-01-01T23:59:59.000Z

158

Real options in information technology risk management: an empirical validation of risk-option relationships  

Science Conference Proceedings (OSTI)

Recently, an option-based risk management (OBRiM) framework has been proposed to control risk and maximize value in information technology investment decisions. While the framework is prescriptive in nature, its core logic rests on a set of normative ... Keywords: IT investment, real options, risk, risk management

Michel Benaroch; Yossi Lichtenstein; Karl Robinson

2006-12-01T23:59:59.000Z

159

Visualizing Risks: Icons for Information Attack Scenarios  

Science Conference Proceedings (OSTI)

... impact of specific threats by avoiding or transferring risk, reducing vulnerability, recovering quickly ... Underground facility Optical cable ... Tornado Water ...

2000-11-03T23:59:59.000Z

160

SECTION 13-CHEMICAL SAFETY NOTE: Much of the information contained in this Chemical Safety section is duplicated from the  

E-Print Network (OSTI)

164 SECTION 13- CHEMICAL SAFETY NOTE: Much of the information contained in this Chemical Safety section is duplicated from the "Chemical Hygiene Plan for Laboratories" in the Louisiana Tech University ( Section 12) when working with chemicals. REQULATORY BASIS FOR RULES GOVERNING THE SAFE USE OF CHEMICALS

Selmic, Sandra

Note: This page contains sample records for the topic "risk informed safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

ENVIRONMENT, HEALTH & SAFETY Risk Management Services, University of Alberta  

E-Print Network (OSTI)

of contracted testing (air quality) Biosafety Provide technical expertise and support to ensure a safe working Management Plan and ACM database management Chemical Safety Management Occupational Hygiene evaluations e.g. noise, chemical exposures, etc Air quality assessments. Laboratory Audits WHMIS / Chemical Spill

Machel, Hans

162

Performance-based usability evaluation of a safety information and alarm system  

Science Conference Proceedings (OSTI)

Evaluation of the appropriateness of information technical systems for complex professional usage in safety-critical contexts poses significant methodical and practical challenges. In this study, the usability of a Safety Information and Alarm Panel ... Keywords: control room, information presentation, nuclear power plant, operators, practice, validation method

Leena Norros; Maaria Nuutinen

2005-09-01T23:59:59.000Z

163

The uses and benefits of probabilistic risk assessment in nuclear reactor safety  

SciTech Connect

Probabilistic risk assessment (PRA) has proven to be an important tool in the safety assessment of nuclear reactors throughout the world. Decision making with regard to many safety issues has been facilitated by both general insights from and direct application of this technology. Key uses of PRA are discussed and some examples of successful applications are cited. The benefits and limitations of PRA are also discussed as well as the broader outlook for applications of PRA. 9 refs.

Bari, R.A.; Speis, T.P. (Brookhaven National Lab., Upton, NY (USA); Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Regulatory Research)

1989-01-01T23:59:59.000Z

164

Application of risk assessment in upgrading safety and quality of radiochemical operations  

SciTech Connect

A Comprehensive Safety Assessment and Upgrade Program (CSAUP) was commenced by the Chemical Technology Division (Chem Tech) at Oak Ridge National Laboratory (ORNL) to achieve excellence in the safety and quality of its operations and condition of its facilities. In the course of conducting CSAUP, a number of issues of concern were identified. The safety risk of these issues has been assessed, and planned actions were prepared for those issues that require corrective actions or improvement/upgrading. The planned actions were evaluated on consideration for the uniqueness of Chem Tech facilities and operations to determine the risks (high, moderate or low) involved by failure to implement the actions. The risk was defined in terms of the frequency and severity of impact. Priority of categorized actions was based on the urgency of the actions. 2 refs., 1 fig., 3 tabs.

Lin, K.H.; Hightower, J.R.; Vaughen, V.C.A.

1990-01-01T23:59:59.000Z

165

Mobius Risk Group LLC | Open Energy Information  

Open Energy Info (EERE)

Risk Group LLC Risk Group LLC Jump to: navigation, search Name Mobius Risk Group LLC Place Houston, Texas Zip TX 77056 Product A risk advisor to energy-consuming companies, utilities and municipalities. Coordinates 29.76045°, -95.369784° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":29.76045,"lon":-95.369784,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

166

1 INTRODUCTION Probabilistic risk (or safety) assessments (PRA) pro-  

E-Print Network (OSTI)

reliability analyses. Finally, a case study in- volving a nuclear reactor is presented in Section 3. Dynamic for managing risks linked to engineering systems, notably in nuclear power plants, aerospace, and chemical of dynamic reliability was established under the name of Con- tinuous Event Tree (CET) theory, (Devooght

Paris-Sud XI, Université de

167

On the safety implications of e-governance: assessing the hazards of enterprise information architectures in safety-critical applications  

Science Conference Proceedings (OSTI)

Governments across Europe and North America have recently reviewed the ways in which they provide both the public and their own departments with access to electronic data. Information service architectures have been proposed as one important component ... Keywords: data integrity, e-governance, emergency planning, safety information

Christopher W. Johnson; Stefan Raue

2010-09-01T23:59:59.000Z

168

DOE safety goals comparison using NUREG-1150 PRA (probabilistic risk assessment) methodology  

Science Conference Proceedings (OSTI)

A full-scope Level 3 probabilistic risk assessment (PRA) including external events has been performed for N Reactor, a US Department of Energy (DOE) Category A production reactor. This four-year, multi-million dollar task was a joint effort by Westinghouse Hanford Company, Science Applications International Corporation (SAIC), and Sandia National Laboratories (SNL). Technical lead in external events and NUREG-1150 methodology was provided by SNL. SAIC led the effort in the Level 1 analysis for the internally initiated events. Westinghouse Hanford supported the task in many key areas, such as data collection and interpretation, accident progression, system interaction, human factor analyses, expert elicitation, peers review, etc. The main objective of this Level 3 PRA are to assess the risks to the public and onsite workers posed by the operation of N Reactor, to identify modifications to the plant that could reduce the overall risk, and to compare those risks to the proposed DOE and Nuclear Regulatory Commission (NRC) quantitative safety goals. This paper presents the methodology adopted by Westinghouse Hanford and SNL for estimating individual health risks, and the comparison of the N Reactor results and DOE quantitative nuclear safety guidelines. This paper is devoted to DOE quantitative safety guidelines interpretation and comparison; the NRC safety objectives are also presented in order to compare N Reactor results to commercial nuclear power plants included in the NUREG-1150 study. 7 refs., 7 tabs.

Wang., O.S.; Zentner, M.D.; Rainey, T.E.

1990-06-01T23:59:59.000Z

169

The Criticality Safety Information Resource Center at Los Alamos National Laboratory  

SciTech Connect

The mission of the Criticality Safety Information Resource Center (CSIRC) at Los Alamos National Laboratory (LANL) is the preservation of primary documentation supporting criticality safety. In many cases, but not all, this primary documentation consists of experimentalists` logbooks. Experience has shown that the logbooks and other primary information are vulnerable to being discarded. Destruction of these logbooks results in a permanent loss to the criticality safety community.

Henderson, B.D.; Meade, R.A. [Los Alamos National Lab., NM (United States); Pruvost, N.L. [Galaxy Computer Services, Inc., Santa Fe, NM (United States)

1997-05-01T23:59:59.000Z

170

Risk-Informed Process Hierarchy for Fossil Plant Maintenance Application  

Science Conference Proceedings (OSTI)

This report describes the functions, capabilities, and features of risk-informed maintenance processes for fossil power plants. This research is the basis on which to develop a software module in an enterprise asset management system (EAMS). Some power plants already use one of the processes described in this report. Additional capabilities are described to enhance that process. New processes are described that address additional applications for risk-informed maintenance.

2008-12-23T23:59:59.000Z

171

Global Framework for Climate Risk Exposure | Open Energy Information  

Open Energy Info (EERE)

Framework for Climate Risk Exposure Framework for Climate Risk Exposure Jump to: navigation, search Tool Summary Name: Global Framework for Climate Risk Exposure Agency/Company /Organization: United Nations Environment Programme Topics: Finance, Co-benefits assessment, Market analysis Resource Type: Publications, Guide/manual Website: www.unepfi.org/fileadmin/documents/global_framework.pdf Global Framework for Climate Risk Exposure Screenshot References: Global Framework for Climate Risk Exposure[1] Summary "A group of leading institutional investors from around the world released the Global Framework for Climate Risk Disclosure-a new statement on disclosure that investors expect from companies-in October 2006. Investors require this information in order to analyze a company's business risks and opportunities resulting from climate change, as well as

172

SUMMARY OF USSD EMERGING ISSUES WHITE PAPER ON DAM SAFETY RISK ASSESSMENT: WHAT IS IT? WHO'S USING IT  

E-Print Network (OSTI)

SUMMARY OF USSD EMERGING ISSUES WHITE PAPER ON DAM SAFETY RISK ASSESSMENT: WHAT IS IT? WHO'S USING White Paper on Dam Safety Risk Assessment. It also includes tables that summarize strengths and references that are summarized in the White Paper, technology transfer and training needs, and research

Bowles, David S.

173

The Criticality Safety Information Resource Center (CSIRC) at Los Alamos National Laboratory  

SciTech Connect

The Criticality Safety Information Resource Center (CSIRC) at Los Alamos National Laboratory (LANL) is a program jointly funded by the U.S. Department of Energy (DOE) and the U.S. Nuclear Regulatory Commission (NRC) in conjunction with the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 97-2. The goal of CSIRC is to preserve primary criticality safety documentation from U.S. critical experimental sites and to make this information available for the benefit of the technical community. Progress in archiving criticality safety primary documents at the LANL archives as well as efforts to make this information available to researchers are discussed. The CSIRC project has a natural linkage to the International Criticality Safety Benchmark Evaluation Project (ICSBEP). This paper raises the possibility that the CSIRC project will evolve in a fashion similar to the ICSBEP. Exploring the implications of linking the CSIRC to the international criticality safety community is the motivation for this paper.

Henderson, B.D.; Meade, R.A.; Pruvost, N.L.

1999-09-20T23:59:59.000Z

174

A security risk analysis model for information systems: Causal relationships of risk factors and vulnerability propagation analysis  

Science Conference Proceedings (OSTI)

With the increasing organizational dependence on information systems, information systems security has become a very critical issue in enterprise risk management. In information systems, security risks are caused by various interrelated internal and ... Keywords: Ant colony optimization, Bayesian networks, Information systems, Security risk, Vulnerability propagation

Nan Feng, Harry Jiannan Wang, Minqiang Li

2014-01-01T23:59:59.000Z

175

Program on Technology Innovation: Continued Technical Support to NEI on Risk-Informed Regulations  

Science Conference Proceedings (OSTI)

This report documents work performed in CY 2006 by EPRI in support of the Nuclear Energy Institute (NEI). Effective nuclear safety risk management can effectively address nuclear safety and economic risk concerns. While there is an increasing risk management culture at plants with many risk management activities embedded in most plant processes, there is a need to define what is effective risk management and to provide a means to assess the effectiveness. The objectives of this work are to 1) identify as...

2006-12-13T23:59:59.000Z

176

DOE handbook electrical safety  

SciTech Connect

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.

NONE

1998-01-01T23:59:59.000Z

177

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

NLE Websites -- All DOE Office Websites (Extended Search)

6/02/2005 6/02/2005 Assessing the changes in safety risk arising from the use of natural gas infrastructures for mixtures of hydrogen and natural gas NATURALHY G. Hankinson Loughborough University, UK 2 16/02/2005 Naturalhy project safety work package NATURALHY 3 16/02/2005 Outline NATURALHY To identify and quantify the major factors influencing safety in the transportation, distribution, and delivery of hydrogen/natural gas mixtures by means of existing natural gas infrastructures. 4 16/02/2005 Purpose NATURALHY To provide information to allow risk assessments to be performed to assist decisions concerning: * The amount of hydrogen that can be introduced into natural gas systems * The conditions under which such systems should be operated, and * The identification of vulnerable locations where

178

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

SciTech Connect

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

Meijing Wu; Guozhang Shen [Qinshan Nuclear power company (China)

2006-07-01T23:59:59.000Z

179

OK–FIRST: A Meteorological Information System for Public Safety  

Science Conference Proceedings (OSTI)

The Oklahoma Climatological Survey has supported local public safety agencies (fire departments, law enforcement agencies, and emergency management) through its OK–FIRST program since 1996. OK–FIRST provides real–time use of weather data to ...

Dale A. Morris; Kenneth C. Crawford; Kevin A. Kloesel; J. Michael Wolfinbarger

2001-09-01T23:59:59.000Z

180

Safety Basis Information System Now Available to DOE and Contractors  

NLE Websites -- All DOE Office Websites (Extended Search)

Get Heart Healthy Heart Health Brochure A Message From the Chief Health, Safety and Security Officer The health of Department of Energy employees has been one of the Office of...

Note: This page contains sample records for the topic "risk informed safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

Coal Mine Safety Act (Virginia) | Open Energy Information  

Open Energy Info (EERE)

Data Page Edit with form History Share this page on Facebook icon Twitter icon Coal Mine Safety Act (Virginia) This is the approved revision of this page, as well as being...

182

Criticality Safety Information Meeting for the Hanford Plutonium Finihsing Plant, May 2012  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

2-05-14 2-05-14 Site: DOE-Richland Operations Office Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Criticality Safety Information Meeting for the Plutonium Finishing Plant Dates of Activity : May 14, 2012 Report Preparer: Ivon Fergus Activity Description/Purpose: The U.S. Department of Energy's (DOE) Office of Enforcement and Oversight, within the Office of Health, Safety and Security (HSS), conducted a criticality safety information meeting with Hanford site criticality safety engineers on May 14, 2012, to discuss criticality safety issues and experiences principally with respect to the Decontamination and Decommissioning (D&D) activities at the Plutonium Finishing Plant (PFP). These discussions also included aspects of Non-

183

Criticality Safety Information Meeting for the Hanford Plutonium Finihsing Plant, May 2012  

NLE Websites -- All DOE Office Websites (Extended Search)

2-05-14 2-05-14 Site: DOE-Richland Operations Office Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Criticality Safety Information Meeting for the Plutonium Finishing Plant Dates of Activity : May 14, 2012 Report Preparer: Ivon Fergus Activity Description/Purpose: The U.S. Department of Energy's (DOE) Office of Enforcement and Oversight, within the Office of Health, Safety and Security (HSS), conducted a criticality safety information meeting with Hanford site criticality safety engineers on May 14, 2012, to discuss criticality safety issues and experiences principally with respect to the Decontamination and Decommissioning (D&D) activities at the Plutonium Finishing Plant (PFP). These discussions also included aspects of Non-

184

Nondestructive Evaluation: Risk-Informed Inservice Inspection Support - 2006  

Science Conference Proceedings (OSTI)

This report describes the results of the project entitled Risk-Informed Inservice Inspection (RI-ISI) Support 2006. The RI-ISI Support project provides for the coordination and participation of risk technology to various industry groups including the Materials Reliability Program (for example, Fatigue and Alloy 600/182/82 task groups), the Boiling Water Reactor Vessel and Internals Project, Equipment Reliability, the Nuclear Energy Institute RI-ISI working group, the Advisory Committee on Reactor Safegua...

2006-10-25T23:59:59.000Z

185

Safety Resources  

NLE Websites -- All DOE Office Websites (Extended Search)

Resources Print LBNLPub-3000: Health and Safety Manual Berkeley Lab safety guide, policies and procedures. Environment, Health, and Safety (EH&S) Staff Contact information for the...

186

Nuclear Safety  

Energy.gov (U.S. Department of Energy (DOE))

Nuclear Safety information site that provides assistance and resources to field elements in implementation of requirements and resolving nuclear safety, facility safety, and quality assurance issues.

187

Index of Energy Security Risk | Open Energy Information  

Open Energy Info (EERE)

Index of Energy Security Risk Index of Energy Security Risk Jump to: navigation, search Tool Summary Name: Index of Energy Security Risk Agency/Company /Organization: United States Chamber of Commerce, Institute for 21st Century Energy Sector: Energy Focus Area: Non-renewable Energy, Renewable Energy Topics: Co-benefits assessment, - Energy Security Resource Type: Publications Website: www.energyxxi.org/images/Energy_Index_2011_FINAL.pdf Cost: Free Index of Energy Security Risk Screenshot References: Index of Energy Security Risk[1] "This 2011 edition of the Index incorporates the most current energy data, including the Energy Information Administration's (EIA) Annual Energy Outlook 2011 (AEO 2011), to provide an up-to-date assessment of the trends having the greatest impact on energy security since the first Index was

188

Application of the risk-based strategy to the Hanford tank waste organic-nitrate safety issue  

Science Conference Proceedings (OSTI)

This report describes the results from application of the Risk-Based Decision Management Approach for Justifying Characterization of Hanford Tank Waste to the organic-nitrate safety issue in Hanford single-shell tanks (SSTs). Existing chemical and physical models were used, taking advantage of the most current (mid-1997) sampling and analysis data. The purpose of this study is to make specific recommendations for planning characterization to help ensure the safety of each SST as it relates to the organic-nitrate safety issue. An additional objective is to demonstrate the viability of the Risk-Based Strategy for addressing Hanford tank waste safety issues.

Hunter, V.L.; Colson, S.D.; Ferryman, T.; Gephart, R.E.; Heasler, P.; Scheele, R.D.

1997-12-01T23:59:59.000Z

189

ENVIRONMENTAL HEALTH & SAFETY EMPLOYEE SAFETY ORIENTATION  

E-Print Network (OSTI)

SERVICES ENVIRONMENTAL HEALTH & SAFETY Discovery 2 Building, Room 265 8888 University Drive BurnabyENVIRONMENTAL HEALTH & SAFETY EMPLOYEE SAFETY ORIENTATION SIMON FRASER UNIVERSITY SAFETY & RISK SIGNAGE 26740 INCIDENT INVESTIGATION Supervisors, Safety Committees, EHS LABORATORY SAFETY 27265

190

THE RADIATION SAFETY INFORMATION COMPUTATIONAL CENTER: A RESOURCE FOR REACTOR DOSIMETRY SOFTWARE AND NUCLEAR DATA  

Science Conference Proceedings (OSTI)

The Radiation Safety Information Computational Center (RSICC) was established in 1963 to collect and disseminate computational nuclear technology in the form of radiation transport, shielding and safety software and corresponding nuclear cross sections. Approximately 1700 nuclear software and data packages are in the RSICC collection, and the majority are applicable to reactor dosimetry.

Kirk, Bernadette Lugue [ORNL

2009-01-01T23:59:59.000Z

191

Certification process of safety analysis and risk management computer codes at the Savannah River Site  

Science Conference Proceedings (OSTI)

The commitment by Westinghouse Savannah River Company (WSRC) to bring safety analysis and risk management codes into compliance with national and sitewide quality assurance requirements necessitated a systematic, structured approach. As a part of this effort, WSRC, in cooperation with the Westinghouse Hanford Company, has developed and implemented a certification process for the development and control of computer software. Safety analysis and risk management computer codes pertinent to reactor analyses were selected for inclusion in the certification process. As a first step, documented plans were developed for implementing verification and validation of the codes, and establishing configuration control. User qualification guidelines were determined. The plans were followed with an extensive assessment of the codes with respect to certification status. Detailed schedules and work plans were thus determined for completing certification of the codes considered. Although the software certification process discussed is specific to the application described, it is sufficiently general to provide useful insights and guidance for certification of other software.

Ades, M.J. (Westinghouse Savannah River Co., Aiken, SC (United States)); Toffer, H.; Lewis, C.J.; Crowe, R.D. (Westinghouse Hanford Co., Richland, WA (United States))

1992-01-01T23:59:59.000Z

192

Certification process of safety analysis and risk management computer codes at the Savannah River Site  

Science Conference Proceedings (OSTI)

The commitment by Westinghouse Savannah River Company (WSRC) to bring safety analysis and risk management codes into compliance with national and sitewide quality assurance requirements necessitated a systematic, structured approach. As a part of this effort, WSRC, in cooperation with the Westinghouse Hanford Company, has developed and implemented a certification process for the development and control of computer software. Safety analysis and risk management computer codes pertinent to reactor analyses were selected for inclusion in the certification process. As a first step, documented plans were developed for implementing verification and validation of the codes, and establishing configuration control. User qualification guidelines were determined. The plans were followed with an extensive assessment of the codes with respect to certification status. Detailed schedules and work plans were thus determined for completing certification of the codes considered. Although the software certification process discussed is specific to the application described, it is sufficiently general to provide useful insights and guidance for certification of other software.

Ades, M.J. [Westinghouse Savannah River Co., Aiken, SC (United States); Toffer, H.; Lewis, C.J.; Crowe, R.D. [Westinghouse Hanford Co., Richland, WA (United States)

1992-05-01T23:59:59.000Z

193

Program on Technology Innovation: Comprehensive Risk Assessment Requirements for Passive Safety Systems  

Science Conference Proceedings (OSTI)

A key feature of the forthcoming generation of nuclear power reactors will be reliance on passive safety systems (PSSs)those that rely on natural physical laws and require minimal or no intervention by plant operators. In 2007, preliminary findings summarized the current state of research into tools and methods that are capable of supporting probabilistic risk assessments (PRAs) for PSSs. These results and a recommended research plan for addressing the identified issues are presented in the Electric Powe...

2008-12-23T23:59:59.000Z

194

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

DOE Green Energy (OSTI)

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

Not Available

1989-01-25T23:59:59.000Z

195

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

DOE Green Energy (OSTI)

It is the purpose of the NRAD to provide an analysis of the range of potential consequences of accidents which have been identified that are associated with the launching and deployment of the Galileo mission spacecraft. The specific consequences analyzed are those associated with the possible release of radioactive material (fuel) of the Radioisotope Thermoelectric Generators (RTGs). They are in terms of radiation doses to people and areas of deposition of radioactive material. These consequence analyses can be used in several ways. One way is to identify the potential range of consequences which might have to be dealt with if there were to be an accident with a release of fuel, so as to assure that, given such an accident, the health and safety of the public will be reasonably protected. Another use of the information, in conjunction with accident and release probabilities, is to estimate the risks associated with the mission. That is, most space launches occur without incident. Given an accident, the most probable result relative to the RTGs is complete containment of the radioactive material. Only a small fraction of accidents might result in a release of fuel and subsequent radiological consequences. The combination of probability with consequence is risk, which can be compared to other human and societal risks to assure that no undue risks are implied by undertaking the mission. 4 refs., 11 figs., 31 tabs.

Not Available

1989-01-13T23:59:59.000Z

196

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

Science Conference Proceedings (OSTI)

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

NONE

2000-08-01T23:59:59.000Z

197

Risk-Informed Snubber Inservice Testing Guidelines: Pilot Project Studies  

Science Conference Proceedings (OSTI)

Current industry practice of assuming nuclear power plant snubbers are a homogenous population requires more frequent examination and expanding the test samples if failures are encountered. This report proposes a risk-informed approach that would reduce snubber examination and testing scope and thereby reduce plant O&M costs, shorten plant outages, and reduce personnel radiation exposure.

1998-03-31T23:59:59.000Z

198

Light-Weight Radioisotope Heater Unit Final Safety Analysis Report (LWRHU FSAR): Volume 3, Nuclear Risk Analysis Document  

SciTech Connect

The Light-Weight Radioisotope Heater Unit (LWRHU) Final Safety Analysis Report (FSAR), Volume 2, Accident Model Document (AMD) describes potential accident scenarios during the Galileo mission and evaluates the response of the LWRHUs to the associated accident environments. Any resulting source terms, consisting of PuO2 (with Pu-238 the dominant radionuclide), are then described in terms of curies released, particle size distribution, release location, and probabilities. This volume (LWRHU-FSAR, Volume 3, Nuclear Risk Analysis Document (NRAD)) contains the radiological analyses which estimate the consequences of the accident scenarios described in the AMD. It also contains the quantification of mission risks resulting from the LWRHUs based on consideration of all accident scenarios and their probabilities. Estimates of source terms and their characteristics derived in the AMD are used as inputs to the analyses in the NRAD. The Failure Abort Sequence Trees (FASTs) presented in the AMD define events for which source terms occur and quantify them. Based on this information, three types of source term cases (most probable, maximum, and expectation) for each mission phase were developed for use in evaluating the radiological consequences and mission risks. 4 refs., 5 figs., 8 tabs.

Not Available

1988-11-30T23:59:59.000Z

199

Transactions of the twenty-fifth water reactor safety information meeting  

SciTech Connect

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.

Monteleone, S. [comp.

1997-09-01T23:59:59.000Z

200

Transactions of the Twenty-First Water Reactor Safety Information Meeting  

SciTech Connect

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.

Monteleone, S. [comp.

1993-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "risk informed safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

Thermal reactor safety  

SciTech Connect

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.

1980-06-01T23:59:59.000Z

202

Defining resilience within a risk-informed assessment framework  

Science Conference Proceedings (OSTI)

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

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

2011-08-01T23:59:59.000Z

203

Development of a pilot safety information document (PSID) for the replacement of radioactive liquid waste treatment facility at Los Alamos National Laboratory  

E-Print Network (OSTI)

Based on recent decisions made by Los Alamos National Laboratory concerning the development of site-wide National Environmental Policy Act documents, an effort was undertaken to develop a Pilot Safety Information Document (PSID) for the replacement Radioactive Liquid Waste Treatment Facility. The PSID documents risk analysis for the proposed facility and some of the alternatives, accident analysis, radioactive and hazardous material doses to off-site individuals, and the cumulative safety risk from adjacent facilities. In addition, this study also compared two methods for calculating the consequences of a radioactive spill. The methods compared were the Superfund model and the release fraction model. It was determined that the release fraction model gives a more realistic estimate of the doses incurred as the result of an accident, and that the Superfund model should be used for estimating the dose before and during the remediation effort. The cumulative safety risk was determined by calculating the exceedance probability if the individual dose from four geographically related facilities. The risk for cancer fatalities was determined to be within the DOE's Nuclear Safety Policy Goals.

Selvage, Ronald Derek

1995-01-01T23:59:59.000Z

204

Quantifying and managing the risk of information security breaches participants in a supply chain  

E-Print Network (OSTI)

Technical integration between companies can result in an increased risk of information security breaches. This thesis proposes a methodology for quantifying information security risk to a supply chain participant. Given a ...

Bellefeuille, Cynthia Lynn

2005-01-01T23:59:59.000Z

205

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

Science Conference Proceedings (OSTI)

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.

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.

1983-02-01T23:59:59.000Z

206

FURMAN NMR SAFETY INFORMATION Standard safety guidelines have been put in place for work around the high-field magnets, and all users  

E-Print Network (OSTI)

FURMAN NMR SAFETY INFORMATION Standard safety guidelines have been put in place for work around and serious personal injury, including death. NMR Magnetic Field Strength · Remember: The magnetic field is ALWAYS on. · Don't enter the NMR room if you have a pacemaker, implanted pacemaker leads or any other

207

Embrittlement Database from the Radiation Safety Information Computational Center  

DOE Data Explorer (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

208

The Radiation Safety Information Computational Center (RSICC): A Resource for Nuclear Science Applications  

Science Conference Proceedings (OSTI)

The Radiation Safety Information Computational Center (RSICC) has been in existence since 1963. RSICC collects, organizes, evaluates and disseminates technical information (software and nuclear data) involving the transport of neutral and charged particle radiation, and shielding and protection from the radiation associated with: nuclear weapons and materials, fission and fusion reactors, outer space, accelerators, medical facilities, and nuclear waste management. RSICC serves over 12,000 scientists and engineers from about 100 countries.

Kirk, Bernadette Lugue [ORNL

2009-01-01T23:59:59.000Z

209

The Human Bathtub: Safety and Risk Predictions Including the Dynamic Probability of Operator Errors  

SciTech Connect

Reactor safety and risk are dominated by the potential and major contribution for human error in the design, operation, control, management, regulation and maintenance of the plant, and hence to all accidents. Given the possibility of accidents and errors, now we need to determine the outcome (error) probability, or the chance of failure. Conventionally, reliability engineering is associated with the failure rate of components, or systems, or mechanisms, not of human beings in and interacting with a technological system. The probability of failure requires a prior knowledge of the total number of outcomes, which for any predictive purposes we do not know or have. Analysis of failure rates due to human error and the rate of learning allow a new determination of the dynamic human error rate in technological systems, consistent with and derived from the available world data. The basis for the analysis is the 'learning hypothesis' that humans learn from experience, and consequently the accumulated experience defines the failure rate. A new 'best' equation has been derived for the human error, outcome or failure rate, which allows for calculation and prediction of the probability of human error. We also provide comparisons to the empirical Weibull parameter fitting used in and by conventional reliability engineering and probabilistic safety analysis methods. These new analyses show that arbitrary Weibull fitting parameters and typical empirical hazard function techniques cannot be used to predict the dynamics of human errors and outcomes in the presence of learning. Comparisons of these new insights show agreement with human error data from the world's commercial airlines, the two shuttle failures, and from nuclear plant operator actions and transient control behavior observed in transients in both plants and simulators. The results demonstrate that the human error probability (HEP) is dynamic, and that it may be predicted using the learning hypothesis and the minimum failure rate, and can be utilized for probabilistic risk analysis purposes. (authors)

Duffey, Romney B. [Atomic Energy of Canada, Ltd., 2251 Speakman Drive, Mississauga, ON, L5K 1B2 (Canada); Saull, John W. [International Federation of Airwothiness, 14 Railway Approach, East Grinstead, West Sussex, RH19 1BP (United Kingdom)

2006-07-01T23:59:59.000Z

210

Safety at CERN  

NLE Websites -- All DOE Office Websites (Extended Search)

U.S. CMS Program U.S. CMS Program Last Updated: March 19, 2012 Safety at CERN Information for U. S. Personnel This information was developed by the U.S. Department of Energy, Office of Science. It is provided to assist you in preparing for your visit to CERN and to help you work safely. As at any U.S. laboratory, you are also responsible for your own safety at CERN. If you are in doubt as to whether your working conditions meet safety standards, you must ask for clarification from your supervisor, the CMS GLIMOS, the PH Department Safety Officer or, if necessary, the CERN Safety Commission. If you regard yourself or others as clearly at risk, you must interrupt the work to take corrective action. Your primary points of contact for safety related questions or

211

FIERAsystem: A Fire Risk Assessment Model for Light Industrial Building Fire Safety Evaluation  

E-Print Network (OSTI)

this report. The current report describes the framework for the new model, individual submodels used for calculations, and the information that the model provides to the design engineer or building official. The framework that FIERAsystem uses to conduct a hazard analysis and the process used to perform a risk analysis are also discussed in the report. 2. FRAMEWORK OF FIERAsystemMODEL The FIERAsystem model allows the user to perform a number of fire protection engineering calculations in order to evaluate fire protection systems in industrial buildings. At start-up, FIERAsystem provides several calculation options, which allow the user to: use standard engineering correlations, run individual submodels, conduct a hazard analysis, or conduct a risk analysis

N. Kashef; A. Torvi; G. Reid; Noureddine Benichou; Ahmed Kashef; David Torvi; George Hadjisophocleous; Irene Reid

2002-01-01T23:59:59.000Z

212

First Capitol Risk Management LLC | Open Energy Information  

Open Energy Info (EERE)

Search Page Edit with form History Facebook icon Twitter icon First Capitol Risk Management LLC Jump to: navigation, search Name First Capitol Risk Management, LLC Place...

213

NIST SP 800-39, Managing Information Security Risk ...  

Science Conference Proceedings (OSTI)

... Provide oversight for the risk management activities carried out ... a greater understanding of risk with regard ... serve as a focal point for communicating ...

2012-02-06T23:59:59.000Z

214

Flood Risk, Uncertainty, and Scientific Information for Decision Making: Lessons from an Interdisciplinary Project  

Science Conference Proceedings (OSTI)

The magnitude of flood damage in the United States, combined with the uncertainty in current estimates of flood risk, suggest that society could benefit from improved scientific information about flood risk. To help address this perceived need, a ...

Rebecca E. Morss; Olga V. Wilhelmi; Mary W. Downton; Eve Gruntfest

2005-11-01T23:59:59.000Z

215

Climate Risk and Financial Institutions | Open Energy Information  

Open Energy Info (EERE)

Climate Risk and Financial Institutions Climate Risk and Financial Institutions Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Climate Risk and Financial Institutions Agency/Company /Organization: International Finance Corporation Topics: Finance, Co-benefits assessment Website: www.ifc.org/ifcext/sustainability.nsf/AttachmentsByTitle/p_ClimateRisk Climate Risk and Financial Institutions Screenshot References: Climate Risk and Financial Institutions[1] Overview "This report demonstrates that climate change and its impacts are likely to alter a number of conditions that are material to the objectives of financial institutions. If changing conditions are not actively managed, investments and institutions may underperform." References ↑ "Climate Risk and Financial Institutions"

216

Risk-Informed Asset Management (RIAM): Method, Process, and Business Requirements  

Science Conference Proceedings (OSTI)

Risk-informed asset management (RIAM) is a composite financial/engineering method that uses risk management technology to support equipment long-term planning and investment decisions at the corporate, fleet, plant, system, or equipment levels of nuclear power enterprises. It gives decision makers improved quantitative information regarding investments in asset management at the levels of individual projects and a portfolio of projects. In a manner similar to use of probabilistic risk assessment and risk...

2005-05-09T23:59:59.000Z

217

Risk-informing decisions about high-level nuclear waste repositories  

E-Print Network (OSTI)

Performance assessments (PAs) are important sources of information for societal decisions in high-level radioactive waste (HLW) management, particularly in evaluating safety cases for proposed HLW repository development. ...

Ghosh, Suchandra Tina, 1973-

2004-01-01T23:59:59.000Z

218

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

SciTech Connect

Large-scale carbon dioxide capture and storage (CCS) offers the benefit of reducing CO{sub 2} emissions and thereby mitigating climate change risk, but it will also bring its own health, safety, and environmental risks. Curtis M. Oldenburg, Editor-in-Chief, considers these risks in the context of the broader picture of energy production. Over the last year, there have been major acute health, safety, and environmental (HSE) consequences related to accidents involving energy production from every major primary energy source. These are, in chronological order: (i) the Upper Big Branch (coal) Mine disaster, (ii) the Gulf of Mexico Macondo (oil) well blowout, (iii) the San Bruno (natural gas) pipeline leak and explosion, and (iv) the Fukushima (nuclear) reactor radioactivity releases. Briefly, the Upper Big Branch Mine disaster occurred in West Virginia on April 5, 2010, when natural methane in the mine ignited, causing the deaths of 29 miners, the worst coal mine disaster in the USA since 1970. Fifteen days later, the Macondo oil well in the Gulf of Mexico suffered a blowout, with a gas explosion and fire on the floating drilling platform that killed 11 people. The oil and gas continued to flow out of the well at the seafloor until July 15, 2010, spilling a total of approximately 5 million barrels of oil into the sea. On September 9, 2010, a 30-inch (76-cm) buried, steel, natural gas pipeline in San Bruno, California, leaked gas and exploded in a residential neighborhood, killing 8 people in their homes and burning a total of 38 homes. Flames were up to 1000 ft (300 m) high, and the initial explosion itself reportedly measured 1.1 on the Richter scale. Finally, on March 11, 2011, a magnitude 9.0 earthquake off the coast of Japan's main island, Honshu, caused a tsunami that crippled the backup power and associated cooling systems for six reactor cores and their spent fuel storage tanks at the Fukushima nuclear power plant. At time of writing, workers trying to bring the crisis under control have been exposed to dangerous levels of radiation, and radioactive water and particulates have been released to the sea and atmosphere. These four disasters, all of which occurred within the past 12 months, were not unprecedented; similar events differing only in detail have happened around the world before, and such events will occur again. Today, developed nations primarily use fossil fuels to create affordable energy for comforts such as lighting, heating and air-conditioning, refrigeration, transportation, education, and entertainment, as well as for powering manufacturing, which creates jobs and a wealth of material goods. In addition to the risks of the existing energy infrastructure that have become obvious through these recent disasters, there is also the ongoing risk of climate change that comes from the vast emissions of greenhouse gases, primarily CO{sub 2}, from the burning of fossil fuels. The implementation of CO{sub 2} capture and storage (CCS) will help mitigate CO{sub 2} emissions from fossil fuel energy, but it also carries with it HSE risks. In my personal interactions with the public and with students, the main concern voiced is whether CO{sub 2} could leak out of the deep reservoirs into which it is injected and rise up out of the ground, smothering people and animals at the ground surface. Another concern expressed is that CO{sub 2} pipelines could fail and cause similar gaseous plumes of CO{sub 2}. The widespread concerns about CO{sub 2} leaking out over the ground surface may be inspired by events that have happened within natural systems in equatorial Africa, in Indonesia, and in Italy. Researchers have been investigating a wide variety of HSE risks of geologic CO{sub 2} storage for some time and have determined that wells are the main potential pathways for significant leakage from the deep subsurface. I discuss the acute HSE risks of CO{sub 2} leakage through wells and from pipelines, and compare the behavior of failures in CO{sub 2} wells and pipelines with oil and gas analogues from which most of our experien

Oldenburg, C.M.

2011-04-01T23:59:59.000Z

219

HSS Safety Shares  

NLE Websites -- All DOE Office Websites (Extended Search)

Safety Shares Safety Shares HSS Safety Shares Home Health, Safety and Security Home HSS Safety Shares 2013 Safety Shares National Weather Service - Lightning Safety General Lightning Safety 7 Important Parts of a Cleaning Label Kitchen Knife Safety Lawn and Garden Tool Hazards Rabies Hearing Loss Winter Driving Tips 2012 Safety Shares Holiday Decoration Safety Tips Countdown to Thanksgiving Holiday Fall Season Safety Tips Slips, Trips and Fall Safety Back To School Safety Tips for Motorists Grills Safety and Cleaning Tips Glass Cookware Safety Water Heater Safety FAQs Root Out Lawn and Garden Tool Hazards First Aid for the Workplace Preventing Colon Cancer Yard Work Safety Yard Work Safety - Part 1 Yard Work Safety - Part 2 High Sodium Risks Heart Risk Stair Safety New Ways To Spot Dangerous Tires

220

Nondestructive Evaluation: Probabilistic Risk Assessment Technical Adequacy Guidance for Risk-Informed In-Service Inspection Programs  

Science Conference Proceedings (OSTI)

Risk-informed methodologies have been developed in order to establish alternative in-service inspection (ISI) requirements that are defined as risk-informed in-service inspection (RI ISI) programs. Plant-specific probabilistic risk assessments (PRAs) are typically used during the RI ISI development process. The ASME PRA Standard (for example, ASME RA Sb 2005) and the U.S. Nuclear Regulatory Commission (NRC) Regulatory Guide (RG) 1.200 R1 and R2 have been issued and provide guidance in determining PRA tec...

2011-07-29T23:59:59.000Z

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221

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

Science Conference Proceedings (OSTI)

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

Daling, P.M.; Rhoads, R.E.; Van Luick, A.E.; Fecht, B.A.; Nilson, S.A.; Sevigny, N.L. [Pacific Northwest Lab., Richland, WA (United States); Armstrong, G.R. [Westinghouse Hanford Co., Richland, WA (United States); Hill, D.H.; Rowe, M.; Stern, E. [Brookhaven National Lab., Upton, NY (United States)

1992-01-01T23:59:59.000Z

222

Group value and intention to use - A study of multi-agency disaster management information systems for public safety  

Science Conference Proceedings (OSTI)

This paper examines and extends the theory of information systems success in the context of large-scale disaster management (DM) for public safety. In the recent past, various evaluation reports on DM efforts have concluded that information quality and ... Keywords: Disaster management, Group value, Information systems success, Intention to use, Public sector, Task support, User satisfaction

JinKyu Lee; Nitesh Bharosa; Jing Yang; Marijn Janssen; H. R. Rao

2011-01-01T23:59:59.000Z

223

Computational Tools for the Safety Control of a Class of Piecewise Continuous Systems with Imperfect Information on a Partial Order  

E-Print Network (OSTI)

This paper addresses the two-agent safety control problem for piecewise continuous systems with disturbances and imperfect state information. In particular, we focus on a class of systems that evolve on a partial order and ...

Hafner, Michael R.

224

Risk-informed incident management for nuclear power plants  

E-Print Network (OSTI)

Decision making as a part of nuclear power plant operations is a critical, but common, task. Plant management is forced to make decisions that may have safety and economic consequences. Formal decision theory offers the ...

Smith, Curtis Lee, 1966-

2002-01-01T23:59:59.000Z

225

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

SciTech Connect

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.

Kirk, Bernadette Lugue [ORNL

2009-01-01T23:59:59.000Z

226

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

Science Conference Proceedings (OSTI)

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

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

2004-12-01T23:59:59.000Z

227

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

Open Energy Info (EERE)

Climate Change: Risk to Bank Loans Climate Change: Risk to Bank Loans Jump to: navigation, search Tool Summary Name: Global Climate Change: Risk to Bank Loans Agency/Company /Organization: United Nations Environment Programme Topics: Finance, Co-benefits assessment, Market analysis Resource Type: Publications, Guide/manual Website: www.unepfi.org/fileadmin/documents/global_climate_change_risk.pdf Global Climate Change: Risk to Bank Loans Screenshot References: Global Climate Change: Risk to Bank Loans[1] Summary "The purpose of this study is to evaluate the impact of climate change related risks on bank borrowers, utilizing as much data and analysis as possible. The first section of this report reviews the current climate change policies in place in Canada, Europe, and the US, in order to provide

228

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

SciTech Connect

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.

Curtis Smith; James Knudsen; Bentley Harwood

2013-08-01T23:59:59.000Z

229

A final report on the Great Plains Gasification Project's environmental, health, and safety information data system  

Science Conference Proceedings (OSTI)

This report describes Oak Ridge National Laboratory's (ORNLs) role in providing information to Department of Energy (DOE) on environmental data generated at the Great Plains Coal Gasification Project (GPCGP) in Beulah, North Dakota. An information system, the Fossil Energy (FE) Environmental, Health, and Safety Information System (EHSIS) was developed at ORNL to assist in tracking, analyzing, and making readily available significant environmental information derived from Great Plains. The Great Plains module with its numerous files (e.g., Gasification Bibliography, Gasification Tables, and Great Plains Gasification Project -- Permits, Standards, or Exceedences/Incidents) is a major technical area located within the information system. Over 1388 Great Plains documents have been reviewed, abstracted, and made available on-line in the information system. Also in the information system are 911 tables of selected environmental data including monitoring data from the following six subject areas: (1) air quality; (2) water quality; (3) solid wastes; (4) hazardous wastes; (5) industrial hygiene; and (6) surface mining. 14 refs., 4 figs.

Noghrei-Nikbakht, P.A.; Roseberry, L.M.

1989-12-01T23:59:59.000Z

230

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

Science Conference Proceedings (OSTI)

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

Ritterbusch, S.E.

2000-08-01T23:59:59.000Z

231

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

SciTech Connect

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.

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

1993-04-15T23:59:59.000Z

232

The Radiation Safety Information Computational Center (RSICC): A Resource for Nuclear Science Applications  

SciTech Connect

The Radiation Safety Information Computational Center (RSICC) has been in existence since 1963. RSICC collects, organizes, evaluates and disseminates technical information (software and nuclear data) involving the transport of neutral and charged particle radiation, and shielding and protection from the radiation associated with: nuclear weapons and materials, fission and fusion reactors, outer space, accelerators, medical facilities, and nuclear waste management. RSICC serves over 12,000 scientists and engineers from about 100 countries. An important activity of RSICC is its participation in international efforts on computational and experimental benchmarks. An example is the Shielding Integral Benchmarks Archival Database (SINBAD), which includes shielding benchmarks for fission, fusion and accelerators. RSICC is funded by the United States Department of Energy, Department of Homeland Security and Nuclear Regulatory Commission.

Kirk, Bernadette Lugue [ORNL

2009-01-01T23:59:59.000Z

233

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

SciTech Connect

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

Dickson, Terry L [ORNL; Kirk, Mark [NRC

2010-01-01T23:59:59.000Z

234

EVALUATING INTERNAL STAKEHOLDER PERSPECTIVES ON RISK-INFORMED REGULATORY PRACTICES FOR THE NUCLEAR REGULATORY COMMISSION  

SciTech Connect

The U.S. Nuclear Regulatory Commission's (NRC) Office of Nuclear Reactor Regulation has begun a program to create a risk-informed environment within the reactor program. The first step of the process is to evaluate the existing environment and internal NRC stakeholder perceptions of risk-informed regulatory practices. This paper reports on the results of the first phase of this evaluation: assessing the current environment, including the level of acceptance of risk-informed approaches throughout the reactor program, the level of integration, areas of success, and areas of difficulty. The other two phases of the evaluation will identify barriers to the integration of risk into NRC activities and gather input on how to move to a risk-informed environment.

Peterson, L.K.; Wight, E.H.; Caruso, M.A.

2003-02-27T23:59:59.000Z

235

A framework for dynamic safety and risk management modeling in complex engineering systems  

E-Print Network (OSTI)

Almost all traditional hazard analysis or risk assessment techniques, such as failure modes and effect analysis (FMEA), fault tree analysis (FTA), and probabilistic risk analysis (PRA) rely on a chain-of-event paradigm of ...

Dulac, Nicolas, 1978-

2007-01-01T23:59:59.000Z

236

Including model uncertainty in risk-informed decision-making  

E-Print Network (OSTI)

Model uncertainties can have a significant impact on decisions regarding licensing basis changes. We present a methodology to identify basic events in the risk assessment that have the potential to change the decision and ...

Reinert, Joshua M

2005-01-01T23:59:59.000Z

237

Management Oversight and Risk Tree (MORT): a new system safety program  

SciTech Connect

Experiences of Aerojet Nuclear Company (ANC), in the development and implementation of a system safety program for ANC and for the Energy Research and Development Administration (ERDA) are discussed. Aerojet Nuclear is the prime operating contractor for ERDA, formerly AEC, at the Idaho National Engineering Laboratory. The ERDA sponsored ''MORT'' system safety program is described along with the process whereby formal system safety methods are incorporated into a stable organization. Specifically, a discussion is given of initial development of MORT; pilot program trials conducted at ANC; implementation methodology; and reaction of the ANC organization. (auth)

Clark, J.L.

1976-04-30T23:59:59.000Z

238

Revised Risk-Informed Inservice Inspection Evaluation Procedure  

Science Conference Proceedings (OSTI)

Operating nuclear power plants currently rely on the implementation of ASME Section XI inservice inspection (ISI) programs for integrity management of Class 1, 2, and 3 systems and components. The evaluation procedure documented in this report provides a practical approach that can be consistently applied by nuclear plant personnel to identify risk-significant pipe segments, define the elements that are to be inspected within these risk-significant segments, and identify appropriate inspection methods.

2000-01-12T23:59:59.000Z

239

A VIKOR technique based on DEMATEL and ANP for information security risk control assessment  

Science Conference Proceedings (OSTI)

As companies and organizations have grown to rely on their computer systems and networks, the issue of information security management has become more significant. To maintain their competitiveness, enterprises should safeguard their information and ... Keywords: Analytic network process (ANP), DEMATEL, Information security, Multiple criteria decision making (MCDM), Risk control assessment, VIKOR

Yu-Ping Ou Yang; How-Ming Shieh; Gwo-Hshiung Tzeng

2013-05-01T23:59:59.000Z

240

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

DOE Green Energy (OSTI)

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.

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

1996-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "risk informed safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

Potential uses of phosphogypsum and associated risks. Background information document  

SciTech Connect

The report contains an introduction, a general description of the fertilizer industry, a discussion of the physical and radiological characteristics of phosphogypsum, a discussion of the uses of phosphogypsum, analyses of the radiological risks associated with various uses of phosphogypsum, and an analysis of the availability and costs of substitute materials.

Not Available

1992-05-01T23:59:59.000Z

242

Risk-informed applications and online maintenance in France and the United States  

E-Print Network (OSTI)

During the past twenty-five years, the US Nuclear Regulatory Commission has been progressing toward a more risk-informed, performance-based regulation. This regulatory framework has effectively supported the development ...

Verdier, Edouard (Edouard Pierre Emmanuel)

2012-01-01T23:59:59.000Z

243

Guidelines for Preparing Risk-Informed Graded Quality Assurance Program Implementation Request Submittals  

Science Conference Proceedings (OSTI)

EPRI has assessed the role of probabilistic risk assessment (PRA) in the regulation of nuclear power plant quality assurance programs. This report presents nuclear utilities with one example of a methodology and formatting guidance for developing submittals to the U.S. Nuclear Regulatory Commission (NRC) requesting implementation of risk-informed, performance-based "graded" quality assurance programs.

1998-10-28T23:59:59.000Z

244

Environment, Health and Safety (EH&S): Biosafety Manual: 3.0 Work and Risk  

NLE Websites -- All DOE Office Websites (Extended Search)

3.0 Work and Risk Assessment 3.0 Work and Risk Assessment The work scope must be defined and the hazards and risks must be assessed before work begins. These work-planning processes are the first two core ISM functions and required by biosafety standards. Biological work and risks at LBNL are defined using established institutional assessment and authorization processes, a structured approach as required by the Department of Energy (DOE), and the standard biosafety risk assessment process defined by the Centers for Disease Control and Prevention (CDC) and the National Institutes of Health (NIH). It is a primary responsibility of workers, work leads, and supervisors to ensure these processes are implemented before work begins. logos 3.1 LBNL Assessment and Authorization Processes

245

Sensemaking in a High-Risk Lifestyle: The Relationship Between Work and Family for Public Safety Families  

E-Print Network (OSTI)

Past research concerning work and family has largely been from traditional, white-collar settings and has only taken into consideration the perceptions of the employees' experiences with regard to the relationship between work and family. However, there is no doubt that employees' in non-traditional settings, particularly those employed in public safety professions (i.e. police and fire) experience the relationship between work and family differently than those in white-collar settings, especially since they put their lives on the line daily for the protection and betterment of the community, society and even the world. In addition, the experiences and perceptions of work and family will undoubtedly be different for the family members (i.e. children and spouses) of those employed in such "life-threatening" professions. This study sought to understand how public safety employees, as well as their families, make sense out of the relationship between work and family by first examining what metaphors they employ to articulate the relationship between work and family. In addition, this study sought to examine if male versus female public safety employees experience the relationship between work and family in similar or different ways, as well as if police officers and fire fighters experience the relationship similarly or differently. Using qualitative methods, the findings indicate that public safety employees and their families articulate and make sense of the relationship between work and family in both similar and different ways. Contrary to previous work-family research, dominant metaphors and constructs such as balance, conflict, segmentation, etc. did not appear at all within this study. Instead, participants likened the relationship between work and family to competition, nature, organism, change, integration, opposition, ambiguity, and destruction. Public safety employees and their families also experienced and made sense of the relationship between work and family through humor, emotion management, fear and risk assessment. Findings also indicate that both male and female public safety employees internalize risk in much the same way, as well as agree that parenthood in general, is devalued in the public safety profession. With regard to differences, findings indicate that females have a harder time negotiating a healthy relationship between work and family, have their competency levels always questioned by family or co-workers, and use different language and rhetoric from males when talking about work and family. Finally, results show that police officers and fire fighters make sense of work and family in much the same way with regard to "dirty work" and communication rules but differ in terms of coping mechanisms and job satisfaction. This study suggests a number of implications for both theory and practice. The findings also point to many necessary areas of future research which could further our understanding of the relationship between work and family, not only in professions characterized by high-risk, non-standard hours and stress, but also in standard white-collar professions as well.

Bochantin, Jaime Elizabeth

2010-08-01T23:59:59.000Z

246

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

DOE Green Energy (OSTI)

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)

Not Available

1990-07-01T23:59:59.000Z

247

The enactment of risk categories: The role of information systems in organizing and re-organizing risk management practices in the energy industry  

Science Conference Proceedings (OSTI)

This research explores the role of information systems in risk management during a twenty year period when new governance arrangements led to enterprise-wide change in the UK energy markets. We present a longitudinal case study documenting the role of ... Keywords: Energy transaction and risk management software, Organizational change, Qualitative IS research, Risk culture

Susan Scott; Nicholas Perry

2012-04-01T23:59:59.000Z

248

Proceedings of the US Nuclear Regulatory Commission twentieth water reactor safety information meeting; Volume 2, Severe accident research, Thermal hydraulics  

SciTech Connect

This three-volume report contains papers presented at the Twentieth Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 21--23, 1992. The papers describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included 10 different papers presented by researchersfrom CEC, China, Finland, France, Germany, Japan, Spain and Taiwan. Selected papers have been processed separately for inclusion in the Energy Science and Technology Database.

Weiss, A.J. [comp.] [Brookhaven National Lab., Upton, NY (United States)

1993-03-01T23:59:59.000Z

249

Nondestructive Evaluation: Risk-Informed In-Service Inspection Status, Extensions, and Resolution of Implementation Issues  

Science Conference Proceedings (OSTI)

This report describes the results of the project developed to provide industry risk-informed in-service inspection (RI-ISI) support. This project provides the coordination and participation of risk technology to various industry groupsin particular, the Materials Reliability Program (for example, fatigue and Alloy 600/182/82 task groups), Boiling Water Reactor Vessel Internals Project, Equipment Reliability, Nuclear Energy Institute RI-ISI Working Group, Advisory Committee on Reactor Safeguards, regulato...

2008-12-22T23:59:59.000Z

250

Nondestructive Evaluation: Risk-Informed Inservice Inspection Support, Extension and Resolution of Implementation Issues—2010  

Science Conference Proceedings (OSTI)

This report describes the results of a project developed to provide industry risk-informed inservice inspection (RI-ISI) support. This project provides coordination and participation in risk technology to various industry groupsin particular, the American Society of Mechanical Engineers, the Materials Reliability Program, the Boiling Water Reactor Vessel and Internals Project, Equipment Reliability, the Nuclear Energy Institute's RI-ISI working group, the Advisory Committee on Reactor Safeguards, regulat...

2010-09-22T23:59:59.000Z

251

Life Cycle Management Economic Tools Demonstration: Risk-Informed Long-Term Planning for Equipment  

Science Conference Proceedings (OSTI)

To date, the EPRI Life Cycle Management (LCM) process and economic evaluation software tools have used point-value deterministic calculations to identify the economically optimum long-term plan for a system, structure, or component (SSC). This collaborative project demonstrates the unique capabilities of four tools that use probabilistic techniques to risk-inform LCM planning (i.e., accounting for risk and uncertainty in long-term asset management resource allocation decisions).

2004-03-31T23:59:59.000Z

252

Coal Mine Safety Act (Virginia)  

Energy.gov (U.S. Department of Energy (DOE))

This Act is the primary legislation pertaining to coal mine safety in Virginia. It contains information on safety rules, safety standards and required certifications for mine workers, prohibited...

253

The use of PRA (Probabilistic Risk Assessment) in the management of safety issues at the High Flux Isotope Reactor  

Science Conference Proceedings (OSTI)

The High Flux Isotope reactor (HFIR) is a high performance isotope production and research reactor which has been in operation at Oak Ridge National Laboratory (ORNL) since 1965. In late 1986 the reactor was shut down as a result of discovery of unexpected neutron embrittlement of the reactor vessel. In January of 1988, a level 1 Probabilistic Risk Assessment (PRA) (excluding external events) was published as part of the response to the many reviews that followed the shutdown and for use by ORNL to prioritize action items intended to upgrade the safety of the reactor. A conservative estimate of the core damage frequency initiated by internal events for HFIR was 3.11 {times} 10{sup {minus}4}. In June 1989 a draft external events initiated PRA was published. The dominant contributions from external events came from seismic, wind, and fires. The overall external event contribution to core damage frequency is about 138% of the internal event initiated contribution and is dominated by wind initiators. The PRA has provided a basis for the management of a wide range of safety and operation issues at the HFIR. 3 refs., 4 figs., 2 tabs.

Flanagan, G.F.

1990-01-01T23:59:59.000Z

254

Normalization of Process Safety Metrics  

E-Print Network (OSTI)

This study is aimed at exploring new process safety metrics for measuring the process safety performance in processing industries. Following a series of catastrophic incidents such as the Bhopal chemical tragedy (1984) and Phillips 66 explosion (1989), process safety became a more important subject than ever. These incidents triggered the development and promulgation of the Process Safety Management (PSM) standard in 1992. While PSM enables management to optimize their process safety programs and organizational risks, there is an emerging need to evaluate the process safety implementation across an organization through measurements. Thus, the process safety metric is applied as a powerful tool that measures safety activities, status, and performance within PSM. In this study, process safety lagging metrics were introduced to describe the contribution of process related parameters in determining the safety performance of an organization. Lagging metrics take process safety incidents as the numerator and divide it by different process-related denominators. Currently a process lagging metric (uses work hours as denominator) introduced by the Center for Chemical Process Safety (CCPS) has been used to evaluate the safety performance in processing industries. However, this lagging metric doesn't include enough process safety information. Therefore, modified denominators are proposed in this study and compared with the existing time-based denominator to validate the effectiveness and applicability of the new metrics. Each proposed metric was validated using available industry data. Statistical unitization method has converted incident rates of different ranges for the convenience of comparison. Trend line analysis was the key indication for determining the appropriateness of new metrics. Results showed that some proposed process-related metrics have the potential as alternatives, along with the time-based metric, to evaluate process safety performance within organizations.

Wang, Mengtian

2012-08-01T23:59:59.000Z

255

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

SciTech Connect

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

Not Available

1990-12-31T23:59:59.000Z

256

Safety Communications  

NLE Websites -- All DOE Office Websites (Extended Search)

Communications Communications New Staff & Guests Safety Topics ISM Plan Safety Communications Questions about safety and environmental compliance should first be directed to your supervisor or work lead. The Life Sciences Division Safety Coordinator Scott Taylor at setaylor@lbl.gov , 486-6133 (office), or (925) 899-4355 (cell); and Facilities Manager Peter Marietta at PMarietta@lbl.gov, 486-6031 (office), or 967-6596 (cell), are also sources of information. Your work group has a representative to the Division Environment, Health, & Safety Committee. This representative can provide safety guidance and offer a conduit for you to pass on your concerns or ideas. A list of current representatives is provided below. Additional safety information can be obtained on-line from the Berkeley Lab

257

Mitigating the risk of information leakage in a two-level supply chain through optimal supplier selection  

Science Conference Proceedings (OSTI)

Information leakage in supply chains is drawing more and more attention in supply chain management. Unlike existing research, which usually focuses on the effect of information leakage on the supply chain's material and information flow, this paper aims ... Keywords: Inference, Information leakage, Information sharing, Optimal supplier selection, Risk mitigation

Da Yong Zhang; Xinlin Cao; Lingyu Wang; Yong Zeng

2012-08-01T23:59:59.000Z

258

Nuclear criticality safety guide  

Science Conference Proceedings (OSTI)

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.

Pruvost, N.L.; Paxton, H.C. [eds.] [eds.

1996-09-01T23:59:59.000Z

259

Analysis of cancer risk related to longitudinal information on smoking habits  

SciTech Connect

Radiation Effects Research Foundation (RERF) has followed the RERF Life Span Study (LSS) cohort consisting of atomic bomb survivors and unexposed subjects for more than 40 years. The information on their lifestyles, including smoking habits, has been collected in the past 25 years through two mail surveys of the entire LSS cohort and three interview surveys of a subcohort for the biennial medical examination program. In the present study an attempt was made to consolidate the information on smoking habits obtained from the five serial surveys, and then a risk analysis was conducted to evaluate the effect of updating the smoking information on the smoking-related risk estimates for lung cancer. The estimates of smoking-related risk became larger and estimates of dose response became sharper by updating smoking information using all of the data obtained from the five serial surveys. Analyses were also conducted for cancer sites other than lung. The differences in risk estimates between the two approaches were not as evident for the other cancer sites as for lung. 13 refs., 2 figs., 6 tabs.

Akiba, Suminori [Radiation Effects Research Foundation, Hiroshima (Japan)

1994-11-01T23:59:59.000Z

260

July 17, 2008; HSS/Union Working Group Meeting, Safety Standards, 10 CFR 851 - Information Package  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

10 CFR 851 / Safety Standards 10 CFR 851 / Safety Standards July 17, 2008 July 17, 2008 ds 06-24-08 Draft HSS/Union Working Group Meeting July 17, 2008 1:00 - 4:00 pm EST FORS 7E-069 Call-in: 301-903-9197 SUBJECT: SAFETY STANDARDS / 10 CFR 851 Core Union Working Groups Safety Standards: Metal Trades Department AFL-CIO - Lead International Brotherhood of Electrical Workers (IBEW) Operative Plasterers' & Cement Masons' International Association (OPCMIA) 10 CFR 851: United Steel, Paper and Forestry, Rubber, Manufacturing, Energy, Allied Industrial and Service Workers International Union (USW) - Lead Building &Construction Trades Department Center for Construction Research &Training (BCTD CPWR) International Guards Union of America (IGUA) International Union of Operating Engineers (IUOE)

Note: This page contains sample records for the topic "risk informed safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

Evaluating risk communication: Narrative vs. technical presentations of information about radon  

SciTech Connect

This paper reports on an experiment to test the hypothesis that people respond better to risk communication that reflects more closely the conditions of their social and cultural lives. The experiment used the case of radon to determine whether technical or narrative forms of risk communication were more effective at drawing people`s attention, imparting information, and modifying behavior. Two series of articles on radon were placed in the local newspapers of two Massachusetts communities. Homeowners attitudes, knowledge, and responses were monitored in baseline and follow-up telephone surveys. A third community was selected for comparison. The newspaper series were developed on the basis of previous research and six focus groups conducted with homeowners. The technical series presented authoritative, factual risk information, in the scientific style of the passive voice with generalized and impersonal language. The narrative series consisted of dramatized accounts of individuals making decisions about radon testing and mitigation, written in a more personal style. The findings from the focus groups confirm the results of previous studies, but the small size of the follow-up samples was a limiting factor in drawing definitive conclusions about the relative effectiveness of the two formats. The experiment demonstrates the difficulty of any risk communication effort on radon and underscores the need for good research design. The study illustrates the need for further research on the role of sociological and cultural factors in the public perception and response to risk. 30 refs., 2 figs., 1 tab.

Golding, D. [Center for Risk Management, Washington, DC (United States); Krimsky, S.; Plough, A. [Tufts Univ., Medford, MA (United States)

1992-03-01T23:59:59.000Z

262

Communication in Healthcare: Opportunities for information technology and concerns for patient safety.  

E-Print Network (OSTI)

??Understanding healthcare workflow is fundamental for design and implementation of information systems. Communication and information exchange between healthcare professionals plays a pivotal role in developing… (more)

Pirnejad, H.

2008-01-01T23:59:59.000Z

263

EPRI Probabilistic Risk Assessments (PRA) Computer Based Training (CBT) v1.0  

Science Conference Proceedings (OSTI)

This Computer Based Training (CBT) module provides a high level introduction to the fundamentals of Probabilistic Risk Assessment (PRA) and its use in Risk Informed (RI) Regulation. The EPRI Risk and Safety Management (RSM) Program is developing a series of CBT Modules to assist in the socialization of risk technology, more specifically the understanding of the plant specific Probabilistic Risk Assessments (PRA) and risk informed regulation. The series of PRA CBT modules are developed in a hierarchical o...

2010-01-22T23:59:59.000Z

264

Risk information in support of cost estimates for the Baseline Environmental Management Report (BEMR). Section 1  

SciTech Connect

The Pacific Northwest Laboratory (PNL)(1) effort on the overall Baseline Environmental Management Report (BEMR) project consists of four installation-specific work components performed in succession. These components include (1) development of source terms, 92) collection of data and preparation of environmental settings reports, (3) calculation of unit risk factors, and (4) utilization of the unit risk factors in Automated Remedial Action Methodology (ARAM) for computation of target concentrations and cost estimates. This report documents work completed for the Nevada Test Site, Nevada, for components 2 and 3. The product of this phase of the BEMR project is the development of unit factors (i.e., unit transport factors, unit exposure factors, and unit risk factors). Thousands of these unit factors are gene rated and fill approximately one megabyte of computer information per installation. The final unit risk factors (URF) are transmitted electronically to BEMR-Cost task personnel as input to a computer program (ARAM). Abstracted files and exhibits of the URF information are included in this report. These visual formats are intended to provide a sample of the final task deliverable (the URF files) which can be easily read without a computer.

Gelston, G.M.; Jarvis, M.F.; Warren, B.R. [Pacific Northwest Lab., Richland, WA (United States); Von Berg, R. [ICF Kaiser Engineers, Inc., Oakland, CA (United States)

1995-06-01T23:59:59.000Z

265

A Study of Interactions in the Risk Assessment of Complex Engineering Systems: An Application to Space PSA  

Science Conference Proceedings (OSTI)

Risk managers are often confronted with the evaluation of operational policies in which two or more system components are simultaneously affected by a change. In these instances, the decision-making process should be informed by the relevance of interactions. ... Keywords: importance measures, interactions, multilinearity, operational decision making, probabilistic safety assessment, risk analysis, safety, sensitivity analysis, system risk

E. Borgonovo; C. L. Smith

2011-11-01T23:59:59.000Z

266

DOE Draft Standard, Development and Use of Probabilistic Risk Assessments  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Draft Standard, Development and Use of Probabilistic Risk Draft Standard, Development and Use of Probabilistic Risk Assessments in Department of Energy Nuclear Safety Applications, 12/10 DOE Draft Standard, Development and Use of Probabilistic Risk Assessments in Department of Energy Nuclear Safety Applications, 12/10 The Department has taken several actions to provide an infrastructure for providing appropriate controls and support for use of risk assessments and risk informed decision making as it applies to nuclear safety including establishing a Risk Assessment Technical Experts Working Group, revising its Nuclear Safety Policy to explicitly address the use and control of risk assessments, and developing this DOE Technical Standard for Control and Use of Probabilistic Risk Assessment for interim use and comment.1

267

LANL | Nuclear Design and Risk Analysis, D-5 | Home Page  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Design and Risk Analysis, D-5 Nuclear Design and Risk Analysis, D-5 Home About Us CAPABILITIES Computational Fluid Dynamics International Nuclear Risk Analysis Nuclear Facility Safety Nuclear Reactor Safety/ Risk Analysis Nuclear Weapons Safety Programmatic Risk Analysis Radiation Transport Modeling (MCNPX) Risk Based Decision Support Seismic Risk Analysis Small Reactor Design CONTACTS Group Leader Pratap Sadasivan (505) 665-5853 Deputy Group Leader Jay Elson Office Administrator Amanda Braithwaite Innovative design and analysis of nuclear systems The Nuclear Design and Risk Analysis Group (D-5) is a multidisciplinary team of scientists and engineers. We provide modeling and analysis capabilities to design and evaluate the potential risks of complex systems, with a focus on nuclear systems. D-5 goes beyond just providing an answer: we provide answers in the context of the overall decision process. We ensure that decision makers have all of the knowledge available to make an informed regulatory, design, or risk decision.

268

Lisheng Safety Laboratory  

Science Conference Proceedings (OSTI)

Lisheng Safety Laboratory. NVLAP Lab Code: 200882-0. Address and Contact Information: Electronic & Lighting (Xiamen) Co. Ltd. No. ...

2013-09-27T23:59:59.000Z

269

Safety Environmental Laboratories & Consulting Inc.  

Science Conference Proceedings (OSTI)

Safety Environmental Laboratories & Consulting Inc. NVLAP Lab Code: 200873-0. Address and Contact Information: 989 ...

2013-09-27T23:59:59.000Z

270

Bayesian Networks and Geographical Information Systems for Environmental Risk Assessment for Oil and Gas Site Development  

E-Print Network (OSTI)

The objective of this work is to develop a Bayesian Network (BN) model to produce environmental risk maps for oil and gas site developments and to demonstrate the model’s scalability from a point to a collection of points. To reach this objective, a benchmark BN model was formulated as a “proof of concept” using Aquifers, Ecoregions and Land Use / Land Cover maps as local and independent input variables. This model was then used to evaluate the probabilistic geographical distribution of the Environmental Sensibility of Oil and Gas (O&G) developments for a given study area. A Risk index associated with the development of O&G operation activities based on the spatial environmental sensibility was also mapped. To facilitate the Risk assessment, these input variables (maps) were discretized into three hazard levels: high, moderate and low. A Geographical Information System (GIS) platform was used (ESRI ArcMap 10), to gather, modify and display the data for the analysis. Once the variables were defined and the hazard data was included on feature classes (layer shapefile format), Python 2.6 software was used as the computational platform to calculate the probabilistic state of all the Bayesian Network’s variables. This allowed to define Risk scenarios both on prognostic and diagnostic analysis and to measure the impact of changes or interventions in terms of uncertainty. The resulting Python – ESRI ArcMap computational script was called “BN+GIS, which populated maps describing the spatial variability of the states of the Environmental Sensibility and of the corresponding Risk index. The latter in particular, represents a tool for decision makers to choose the most suitable location for placing a drilling rig, since it integrates three fundamental environmental variables. Also, results show that is possible to back propagate the information from the Environmental Sensibility to define the inherent triggering scenarios (hazard variables). A case of study is presented to illustrate the applicability of the proposed methodology on a specific geographical setting. The Barnett Shale was chosen as a benchmark study area because sufficient information on this region was available, and the importance that it holds on the latest developments of unconventional plays in the country. The main contribution of this work relies in combining Bayesian Networks and GIS to define environmental Risk scenarios that can facilitate decision-making for O&G stakeholders such as land owners, industry operators, regulators and Non-Governmental Organizations (NGOs), before and during the development of a given site.

Varela Gonzalez, Patricia Ysolda

2013-05-01T23:59:59.000Z

271

Office of Nuclear Safety  

NLE Websites -- All DOE Office Websites (Extended Search)

Office of Nuclear Safety (HS-30) Office of Nuclear Safety (HS-30) Office of Nuclear Safety Home » Directives » Nuclear and Facility Safety Policy Rules » Nuclear Safety Workshops Technical Standards Program » Search » Approved Standards » Recently Approved » RevCom for TSP » Monthly Status Reports » Archive » Feedback DOE Nuclear Safety Research & Development Program Office of Nuclear Safety Basis & Facility Design (HS-31) Office of Nuclear Safety Basis & Facility Design - About Us » Nuclear Policy Technical Positions/Interpretations » Risk Assessment Working Group » Criticality Safety » DOE O 420.1C Facility Safety » Beyond Design Basis Events Office of Nuclear Facility Safety Programs (HS-32) Office of Nuclear Facility Safety Programs - About Us

272

Asset Management Toolkit Modules: An Approach for Risk-Informed Performance-Focused Asset Management in the Power Delivery Industry  

Science Conference Proceedings (OSTI)

With the growing emphasis on risk management, decision makers need both quantified estimates of the risk/uncertainty and actionable results for capital and operation and maintenance (O&M) investments in power delivery projects. This report describes the concepts and modular automation framework for an asset management toolkit that embodies the methods and processes of risk-informed, performance-focused asset management in the power delivery industry.

2005-06-30T23:59:59.000Z

273

Strategic Safety Goals | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Documents & Publications Occupational Safety Performance Trends Development of the Nuclear Safety Information Dashboard - September 2012 EA-1954: Draft Environmental Assessment...

274

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

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.

Monteleone, S. [comp.

1995-09-01T23:59:59.000Z

275

Nuclear waste transportation: Case studies of identifying stakeholder risk information needs  

E-Print Network (OSTI)

The U.S. Department of Energy (DOE) is responsible for the cleanup of our nation’s nuclear legacy, involving complex decisions about how and where to dispose of nuclear waste and how to transport it to its ultimate disposal site. It is widely recognized that a broad range of stakeholders and tribes should be involved in this kind of decision. All too frequently, however, stakeholders and tribes are only invited to participate by commenting on processes and activities that are near completion; they are not included in the problem formulation stages. Moreover, it is often assumed that high levels of complexity and uncertainty prevent meaningful participation by these groups. Considering the types of information that stakeholders and tribes need to be able to participate in the full life cycle of decision making is critical for improving participation and transparency of decision making. Toward this objective, the Consortium for Risk Evaluation with Stakeholder Participation (CRESP) participated in three public processes relating to nuclear waste transportation and disposal in 1997–1998. First, CRESP organized focus groups to identify concerns about nuclear waste transportation. Second, CRESP conducted exit surveys at regional public workshops held by DOE to get input from stakeholders on intersite waste transfer issues. Third, CRESP developed visual tools to synthesize technical information and allow stakeholders and tribes with varying levels of knowledge about nuclear waste to participate in meaningful discussion. In this article we share the results of the CRESP findings, discuss common themes arising from these interactions, and comment on special considerations needed to facilitate stakeholder and tribal participation in similar decision-making processes. Key words: environmental information, hazardous waste, risk communication, risk perception, stakeholders. Environ Health Perspect

Christina H. Drew; Deirdre A. Grace; Susan M. Silbernagel; Erin S. Hemmings; Alan Smith; William C. Griffith; Timothy K. Takaro; Elaine M. Faustman

2003-01-01T23:59:59.000Z

276

Occupational Safety Performance Trends | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Occupational Safety Trends More Documents & Publications Strategic Safety Goals EA-1954: Draft Environmental Assessment Development of the Nuclear Safety Information Dashboard...

277

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

Science Conference Proceedings (OSTI)

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.

Not Available

1980-01-01T23:59:59.000Z

278

Rulemaking Activities to Risk-Inform Requirements in 10 CFR Part 50  

SciTech Connect

This paper presents the status of NRC activities to revise requirements in Title 10 of the Code of Federal Regulations (10 CFR Part 50) to make them more risk-informed. The activities include proposed changes to treatment requirements (requirements such as quality assurance, testing, inspection, documentation that are imposed to add confidence in the capability of structures, systems and components (SSCs) to perform their intended functions) as well as changes to certain technical requirements. The technical requirements under consideration are those relating to combustible gas control and for emergency core cooling systems (including the evaluation models). (authors)

McKenna, Eileen M.; Reed, Timothy A. [U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001 (United States)

2002-07-01T23:59:59.000Z

279

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

Science Conference Proceedings (OSTI)

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

Berven, B.A.

1993-09-01T23:59:59.000Z

280

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

Science Conference Proceedings (OSTI)

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

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

2011-09-30T23:59:59.000Z

Note: This page contains sample records for the topic "risk informed safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

Safety Bulletin  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Bulletin Bulletin Offtce 01 Health. Safety and Sa<:urtty Events Beyond Design Safety Basis Analysis No. 2011-01 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 Japan was damaged by a magnitude 9.0 earthquake and the subsequent tsunami. While there is still a lot to be learned from the accident · about the adequacy of design specifications and the equipment failure modes, reports from the Nuclear Regulatory Commission (NRC) have identified some key aspects of the operational emergency at the Fukushima Daiichi nuclear power station.

282

Information- Chemical Safety Open Items CS-09, AP-02, AP-08, and AP-  

E-Print Network (OSTI)

This letter provides change pages to the Duke COGEMA Stone & Webster (DCS), LLC, Construction Authorization Request (CAR) concerning the Mixed Oxide (MOX) Fuel Fabrication Facility. The enclosed change pages replace pages in the CAR as updated through Reference 1. The changes incorporate the revisions discussed in Reference 2. The enclosed change pages do not contain information which is considered to be proprietary to DCS. Enclosure 1 provides instructions for updating the CAR with the change pages. Enclosure 2 provides twenty-five copies of the CAR change pages. If I can provide any additional information, please feel free to contact me at (980) 373-3787. Sincerely,

Duke Cogema; Stone Webster; Duke Cogema Stone; Richard L. Sweigart; Kenneth L. Ashe; Donald J. Silverman; David Brown; A. Smith

2005-01-01T23:59:59.000Z

283

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

SciTech Connect

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.

Not Available

1980-01-01T23:59:59.000Z

284

Savannah River Site K-Reactor Probabilistic Safety Assessment  

SciTech Connect

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

Brandyberry, M.D.; Bailey, R.T.; Baker, W.H.; Kearnaghan, D.P.; O`Kula, K.R.; Wittman, R.S.; Woody, N.D. [Westinghouse Savannah River Co., Aiken, SC (United States); Amos, C.N.; Weingardt, J.J. [Science Applications International Corp. (United States)

1992-12-01T23:59:59.000Z

285

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

SciTech Connect

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.

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.

2010-09-01T23:59:59.000Z

286

Subsurface safety valves: safety asset or safety liability  

SciTech Connect

This paper summarizes the methods used to compare the risk of a blowout for a well completed with a subsurface safety valve (SSSV) vs. a completion without an SSSV. These methods, which could be applied to any field, include a combination of SSSV reliability and conventional risk analyses. The Kuparuk River Unit Working Interest Owners recently formed a group to examine the risks associated with installing and maintaining SSSV's in the Kuparuk field. The group was charged with answering the question: ''Assuming Kuparuk field operating conditions, are SSSV's a safety asset, or do numerous operating and maintenance procedures make them a safety liability.'' The results indicate that for the Kuparuk River Unit, an SSSV becomes a safety liability when the mean time between SSSV failures is less than one year. Since current SSSV mean time to failure (MTTF) at Kuparuk is approximately 1000 days, they are considered a safety asset.

Busch, J.M.; Llewelyn, D.C.G.; Policky, B.J.

1983-10-01T23:59:59.000Z

287

Parametric Uncertainty Impacts on Option 2 Safety Significance Categorization  

Science Conference Proceedings (OSTI)

This report describes an assessment to determine the impact of parametric uncertainty on the safety significance categorization of structures, systems, and components (SSCs) using risk-importance measures. The study supports Risk-Informed Option 2, which allows elimination of special treatment requirements for low-risk-significant SSCs. The U.S. Nuclear Regulatory Commission (NRC) has proposed an Option 2 Rulemaking, 10 CFR 50.69. Industry, through the Nuclear Energy Institute (NEI) with EPRI technical s...

2003-06-30T23:59:59.000Z

288

Safety Modeling via Segmentation of Transportation Networks.  

E-Print Network (OSTI)

??This dissertation proposes a methodology to address a long-standing question in traffic safety relating to the evaluation of safety risk and the benefits associated with… (more)

Oh, Jun Seok

2010-01-01T23:59:59.000Z

289

Microsoft Word - Operationalizing Explosives Safety.docx  

NLE Websites -- All DOE Office Websites (Extended Search)

Operationalizing Explosives Safety Incorporating Explosives Safety and Munitions Risk Management into the Joint Operation Planning Process Department of Defense Issues and...

290

Generic safety documentation model  

SciTech Connect

This document is intended to be a resource for preparers of safety documentation for Sandia National Laboratories, New Mexico facilities. It provides standardized discussions of some topics that are generic to most, if not all, Sandia/NM facilities safety documents. The material provides a ``core`` upon which to develop facility-specific safety documentation. The use of the information in this document will reduce the cost of safety document preparation and improve consistency of information.

Mahn, J.A.

1994-04-01T23:59:59.000Z

291

Guideline for the Treatment of Uncertainty in Risk-Informed Applications: Technical Basis Document  

Science Conference Proceedings (OSTI)

This report provides the technical basis for a process to characterize the uncertainty distribution for risk metrics derived from probabilistic risk assessments (PRAs).

2004-12-21T23:59:59.000Z

292

Electrical safety guidelines  

SciTech Connect

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

Not Available

1993-09-01T23:59:59.000Z

293

Cryogenics safety  

DOE Green Energy (OSTI)

The safety hazards associated with handling cryogenic fluids are discussed in detail. These hazards include pressure buildup when a cryogenic fluid is heated and becomes a gas, potential damage to body tissues due to surface contact, toxic risk from breathing air altered by cryogenic fluids, dangers of air solidification, and hazards of combustible cryogens such as liquified oxygen, hydrogen, or natural gas or of combustible mixtures. Safe operating procedures and emergency planning are described. (LCL)

Reider, R.

1977-01-01T23:59:59.000Z

294

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

SciTech Connect

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.

Weiss, A. J. [comp.

1988-02-01T23:59:59.000Z

295

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

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.

Monteleone, S. [comp.

1995-04-01T23:59:59.000Z

296

Criticality Safety  

NLE Websites -- All DOE Office Websites (Extended Search)

Left Tab EVENTS Office of Nuclear Safety (HS-30) Office of Nuclear Safety Home Directives Nuclear and Facility Safety Policy Rules Nuclear Safety Workshops Technical...

297

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

SciTech Connect

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

Baxter, D.E.

1994-10-01T23:59:59.000Z

298

Modular HTGR Safety Basis and Approach  

SciTech Connect

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

Thomas Hicks

2011-08-01T23:59:59.000Z

299

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

Science Conference Proceedings (OSTI)

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

Peterson, V.L.

1993-12-23T23:59:59.000Z

300

Risk-based priority scoring for Brookhaven National Laboratory environmental restoration programs  

Science Conference Proceedings (OSTI)

This report describes the process of estimating the risk associated with environmental restoration programs under the Brookhaven National Laboratory Office of Environmental Restoration. The process was part of an effort across all Department of Energy facilities to provide a consistent framework to communicate risk information about the facilities to senior managers in the DOE Office of Environmental Management to foster understanding of risk activities across programs. the risk evaluation was a qualitative exercise. Categories considered included: Public health and safety; site personnel safety and health; compliance; mission impact; cost-effective risk management; environmental protection; inherent worker risk; environmental effects of clean-up; and social, cultural, political, and economic impacts.

Morris, S.C.; Meinhold, A.F.

1995-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "risk informed safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

Decommissioning Standard Review Plans and Risk-Informing Decommissioning Regulation: Selected 1999 Industry/NRC Decommissioning Lice nsing Interactions  

Science Conference Proceedings (OSTI)

This report describes the technical support EPRI provided the Nuclear Energy Institute (NEI) Decommissioning Working Group in 1999. This volume includes two initiatives that produced four draft Decommissioning Standard Review Plans (DSRPs). It also includes an evaluation entitled Spent Fuel Pool Seismic Failure Frequency in Support of Risk-Informed Decommissioning -- Emergency Planning.

1999-10-31T23:59:59.000Z

302

Technical Basis for Revision to ASME Code to Appendix G: Incorporate Risk Informed P-T Methodology  

Science Conference Proceedings (OSTI)

A risk-informed procedure has been developed to define an optional alternative to the current ASME Section XI, Appendix G deterministic method for determining leak test temperature and heat-up and cool-down pressure-temperature limits. This method is simple to understand and implement and remains consistent with the structure of the current ASME Section XI, Appendix G deterministic methodology.

2009-06-30T23:59:59.000Z

303

Subject: Integrated Safety Analysis: Why It Is Appropriate for Fuel  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Subject: Integrated Safety Analysis: Why It Is Appropriate for Fuel Subject: Integrated Safety Analysis: Why It Is Appropriate for Fuel Recycling Facilities Project Number: 689Nuclear Energy Institute (NEI) Letter, 9/10/10 Subject: Integrated Safety Analysis: Why It Is Appropriate for Fuel Recycling Facilities Project Number: 689Nuclear Energy Institute (NEI) Letter, 9/10/10 Enclosed for your review is a Nuclear Energy Institute white paper on the use of Integrated Safety Analysis (ISA) at U.S. Nuclear Regulatory Commission-licensed recycling facilities. This paper is intended as an information source for the NRC and should serve as a foundation for discussion with industry representatives on the issue. This paper concludes that an ISA is a risk-informed, performance-based way of achieving and maintaining safety at fuel recycling facilities. As

304

Selenide isotope generator for the Galileo Mission: safety test plan  

DOE Green Energy (OSTI)

The intent of this safety test plan is to outline particular kinds of safety tests designed to produce information which would be useful in the safety analysis process. The program deals primarily with the response of the RTG to accident environments; accordingly two criteria were established: (1) safety tests should be performed for environments which are the most critical in terms of risk contribution; and (2) tests should be formulated to determine failure conditions for critical heat source components rather than observe heat source response in reference accident environments. To satisfy criterion 1. results of a recent safety study were used to rank various accidents in terms of expected source terms. Six kinds of tests were then proposed which would provide information meeting the second criterion.

Not Available

1979-01-31T23:59:59.000Z

305

Quantification, Optimization and Uncertainty Modeling in Information Security Risks: A Matrix-Based Approach  

Science Conference Proceedings (OSTI)

In this paper, the authors present a quantitative model for estimating security risk exposure for a firm. The model includes a formulation for the optimization of controls as well as determining sensitivity of the exposure of assets to different threats. ... Keywords: Cost Benefit Analysis, Data Simulation, Decision Models, IS Risk Management, Investment Justification, Security Management, Security Risk

Sanjay Goel; Eitel J.M. Lauría

2010-04-01T23:59:59.000Z

306

Seismic Safety Margins Research Programs. Assessment of potential increases in risk due to degradation of steam generator and reactor coolant pump supports. [PWR  

Science Conference Proceedings (OSTI)

During the NRC licensing review for the North Anna Units 1 and 2 pressurized-water reactors (PWRs), questions were raised regarding the potential for low-fracture toughness of steam-generator and reactor-coolant-pump supports. Because other PWRs may face similar problems, this issue was incorporated into the NRC Program for Resolution of Generic Issues. The work described in this report was performed to provide the NRC with a quantitative evaluation of the value/impact implications of the various options of resolving the fracture-toughness question. This report presents an assessment of the probabilistic risk associated with nil-ductility failures of steam-generator and reactor-coolant-pump structural-support systems during seismic events, performed using the Seismic Safety Margins Research Program codes and data bases.

Bohn, M. P.; Wells, J. E.; Shieh, L. C.; Cover, L. E.; Streit, R. L.

1983-08-01T23:59:59.000Z

307

Feasibility of risk-informed regulation for Generation-IV reactors  

E-Print Network (OSTI)

With the advent of new and innovative Generation-IV reactor designs, new regulations must be developed to assure the safety of these plants. In the past a purely deterministic way of developing design basis accidents was ...

Matos, Craig H

2005-01-01T23:59:59.000Z

308

Nuclear Safety Information  

NLE Websites -- All DOE Office Websites (Extended Search)

National Laboratory Lawrence Livermore National Laboratory Nevada National Security Site New Brunswick Laboratory Oak Ridge National Laboratory Paducah ...

309

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Standard on Development and Use of Probabilistic Risk Standard on Development and Use of Probabilistic Risk Assessment in DOE Nuclear Safety Applications (draft), December 2010 DOE Standard on Development and Use of Probabilistic Risk Assessment in DOE Nuclear Safety Applications (draft), December 2010 There have been significant developments with regard to the risk assessment and risk informed decision making, as it applies to nuclear and other safety areas, since the Department of Energy (DOE) developed its approach to managing nuclear safety. The developments and associated technical insights may be of use to DOE in its efforts to continuously improve safety performance at its nuclear facilities. The Department has taken several actions to provide an infrastructure for providing appropriate controls and

310

Intermodal safety research needs report of the sixth workshop on national transportation problems  

DOE Green Energy (OSTI)

This conference brought together DOT policymakers, university principal investigators and other professionals to consider the intermodal safety research requirements of the Department of Transportation. The objectives of the conference were: (1) to highlight safety problems and needed transportation safety research identified by DOT modal safety managers and to stimulate university or university/industry teams to respond with research proposals which emphasize multi-modal applicability and a system view; and (2) to provide a forum for university research groups to inform DOT safety managers of promising new directions in transportation safety research and new tools with which to address safety related problems. The conference addressed the research requirements for safety as identified by the Statement of National Transportation Policy and by the modal safety managers in three principal contexts, each a workshop panel: I, Inter-Institutional Problems of Transportation Safety. Problems were described as: Federal-State, local; Federal-Industry; Federal-Public, Consumer groups. II, Goal Setting and Planning for Transportation Safety Programs. Issues were: modifying risk behavior, safety as a social value, and involving citizens in development of standards as a way of increasing probability of achieving program objectives. III, DOT Information, Management, and Evaluation Systems Requirements. Needs were: data requirements and analytic tools for management of safety programs.

Warshawer, A.J. (ed.)

1976-04-01T23:59:59.000Z

311

Attack Tree Based Information Security Risk Assessment Method Integrating Enterprise Objectives with Vulnerabilities IAJIT First Online Publication  

E-Print Network (OSTI)

Abstract: In order to perform the analysis and mitigation efforts related with the Information Security risks there exists quantitative and qualitative approaches, but the most critical shortcoming of these methods is the fact that the outcome mainly addresses the needs and priorities of the technical community rather than the management. For the enterprise management, this information is essentially required as a decision making aid for the asset allocation and the prioritization of mitigation efforts. So ideally the outcome of an information security risk method must be in synchronization with the enterprise objectives to act as a useful decision tool for the management. Also in the modelling of the threat domain, attack trees are frequently utilized. However the execution of attack tree modelling is costly from the effort and timing requirements and also has inherent scalability issues. So within this article our design-science research based work on an information security risk assessment method that addresses these two issues of enterprise objective inclusion and model scalability will be outlined.

Bugra Karabey; Nazife Baykal

2011-01-01T23:59:59.000Z

312

Safety Notices  

NLE Websites -- All DOE Office Websites (Extended Search)

Safety Notices Safety Notices Fatigue August 2011 Sleep deprivation and the resulting fatigue can adversely affect manual dexteri- ty, reaction time, alertness, and judgment, resulting in people putting themselves and their co-workers at risk. Liquid-Gas Cylinder Handtruck Awareness May 2011 Failure of a spring assembly can result in a loss of control, allowing the Dewar to become separated from the hand truck, leading to a very dangerous situation. Safe Transport of Hazardous Materials February 2011 APS users are reminded that hazardous materials, including samples, cannot be packed in personal luggage and brought on public transport. Electrical Incidents September 2010 Two minor electrical incidents in the past months at the APS resulted in a minor shock from inadequately grounded equipment, and a damaged stainless

313

Distributed risk management model and algorithm for virtual enterprise with private information  

Science Conference Proceedings (OSTI)

For the desired profit and anticipated goal, the virtual enterprise (VE) must avoid the risk successfully. In view of its characteristics, such as the diversity of partners and distribution of cooperative regions, the idea of distributed decision-making ... Keywords: distributed decision making, risk management, synthetic evaluation, taboo search, virtual enterprise

Xianli Sun; Min Huang; Xingwei Wang; Fuqiang Lu

2009-06-01T23:59:59.000Z

314

CRAD, Facility Safety - Nuclear Facility Safety Basis | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

CRAD, Facility Safety - Nuclear Facility Safety Basis CRAD, Facility Safety - Nuclear Facility Safety Basis CRAD, Facility Safety - Nuclear Facility Safety Basis A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) that can be used for assessment of a contractor's Nuclear Facility Safety Basis. CRADs provide a recommended approach and the types of information to gather to assess elements of a DOE contractor's programs. CRAD, Facility Safety - Nuclear Facility Safety Basis More Documents & Publications CRAD, Facility Safety - Unreviewed Safety Question Requirements Site Visit Report, Livermore Site Office - February 2011 FAQS Job Task Analyses - Nuclear Safety Specialist

315

Use of Level 3 PSA in Risk Informed, Performance Based Regulation of Nuclear Power Plants  

Science Conference Proceedings (OSTI)

At the request of the South Texas Electric Generating Station (STP), EPRI assessed the role of probabilistic safety assessment (PSA) Level 3 consequence analysis in the regulation of nuclear power plants. By surveying use of consequence analysis codes, their development, and current status, this report attempts to put Level 3 PSAs in perspective relative to their usefulness for making regulatory decisions.

1998-02-19T23:59:59.000Z

316

Airport risk assessment: a probabilistic approach  

Science Conference Proceedings (OSTI)

Risk reduction is one of the key objectives pursued by transport safety policies. Particularly, the formulation and implementation of transport safety policies needs the systematic assessment of the risks, the specification of residual risk targets and ... Keywords: risk assessment methodology, risk management, safety civil aviation

L. Guerra; T. Murino; E. Romano

2008-05-01T23:59:59.000Z

317

2013 DOE Safety and Security Enforcement Workshop  

NLE Websites -- All DOE Office Websites (Extended Search)

2013 DOE Safety and Security Workshop 2013 Workshop Home Registration Agendas Hotel and Training Center Information Enforcement Home 2013 DOE Safety and Security Enforcement...

318

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

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.

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

1994-04-01T23:59:59.000Z

319

MTDC Safety Sensor Technology  

NLE Websites -- All DOE Office Websites (Extended Search)

MTDC Safety Sensor Technology MTDC Safety Sensor Technology Background Beyond the standard duty cycle data collection system used in the Department of Energy's Medium Truck Duty Cycle program, additional sensors were installed on three test vehicles to collect several safety-related signals of interest to the Federal Motor Carrier Safety Administration. The real-time brake stroke, tire pressure, and weight information obtained from these sensors is expected to make possible a number of safety-related analyses such as determining the frequency and severity of braking events and tracking tire pressure changes over time. Because these signals are posted to the vehicle's databus, they also have the potential to be

320

Nuclear criticality safety  

SciTech Connect

Important facts of the nuclear criticality safety field are covered in this volume. Both theoretical and practical aspects of the subject are included, based on insights provided by criticality experts and published information from many sources. An overview of nuclear criticality safety theory and a variety of practical in-plant operation applications are presented. Underlying principles of nuclear criticality safety are introduced and the state of the art of this technical discipline is reviewed. Criticality safety theoretical concepts, accident experience, standards, experiments computer calculations, integration of safety methods into individual practices, and overall facility operations are all included.

Knief, R.A.

1985-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "risk informed safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

Information bias and lifetime mortality risks of radiation-induced cancer: Low LET radiation  

Science Conference Proceedings (OSTI)

Additive and multiplicative models of relative risk were used to measure the effect of cancer misclassification and DS86 random errors on lifetime risk projections in the Life Span Study (LSS) of Hiroshima and Nagasaki atomic bomb survivors. The true number of cancer deaths in each stratum of the cancer mortality cross-classification was estimated using sufficient statistics from the EM algorithm. Average survivor doses in the strata were corrected for DS86 random error ({sigma}=0.45) by use of reduction factors. Poisson regression was used to model the corrected and uncorrected mortality rates with risks in RERF Report 11 (Part 2) and the BEIR-V Report. Bias due to DS86 random error typically ranged from {minus}15% to {minus}30% for both sexes, and all sites and models. The total bias, including diagnostic misclassification, of excess risk of nonleukemia for exposure to 1 Sv from age 18 to 65 under the non-constant relative project model was {minus}37.1% for males and {minus}23.3% for females. Total excess risks of leukemia under the relative projection model were biased {minus}27.1% for males and {minus}43.4% for females. Thus, nonleukemia risks for 1 Sv from ages 18 to 65 (DRREF=2) increased from 1.91%/Sv to 2.68%/Sv among males and from 3.23%/Sv to 4.92%/Sv among females. Leukemia excess risk increased from 0.87%/Sv to 1.10/Sv among males and from 0.73%/Sv to 1.04/Sv among females. Bias was dependent on the gender, site, correction method, exposure profile and projection model considered. Future studies that use LSS data for US nuclear workers may be downwardly biased if lifetime risk projections are not adjusted for random and systematic errors.

Peterson, L.E.; Schull, W.J.; Davis, B.R. [Texas Univ., Houston, TX (United States). Health Science Center; Buffler, P.A. [California Univ., Berkeley, CA (United States). School of Public Health

1994-04-01T23:59:59.000Z

322

Risk-Informed Evaluation of Protective Action Strategies for Nuclear Plant Off-Site Emergency Planning  

Science Conference Proceedings (OSTI)

All commercial nuclear power plants have developed formal emergency preparedness programs, which are implemented if actions required to protect public health and safety are deemed a necessary response to accident conditions. However, in the United States, the basis for these programs and the associated protective action strategies that would be implemented have not been modified since the time of the Three Mile Island accident. Based on the significant advancements in the knowledge of potential nuclear a...

2007-09-18T23:59:59.000Z

323

Failure-driven software safety  

Science Conference Proceedings (OSTI)

Software safety and software risk management are two of the most important facets of modern software engineering. To understand safety requires that we understand first what is not safe. This paper examines the concept of failure in software engineering ... Keywords: derived requirements, failure, requirements, risk, stakeholder, testing

Richard Riehle

2007-09-01T23:59:59.000Z

324

VPP Safety Share  

NLE Websites -- All DOE Office Websites (Extended Search)

VPP Safety Share VPP Safety Share BlackBerry Safety Brice Cook, HS-1.3 July 22, 2010 2 BlackBerry Safety * Use only approved batteries with your BlackBerry device. * Use of batteries that have not been approved by Research In Motion might present a risk of fire or explosion, which could cause serious harm, death, or property loss. * Use only RIM approved chargers. * Use of chargers that have not been approved by RIM might present a risk of fire or explosion, which could cause serious harm, death, or property loss. 3 BlackBerry Safety * When you wear the BlackBerry device close to your body: * Use a RIM approved holster with an integrated belt clip or maintain a distance of 0.98 in. (25 mm) between your BlackBerry device and your body while the BlackBerry device is transmitting.

325

FACILITY SAFETY (FS)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

FACILITY SAFETY (FS) FACILITY SAFETY (FS) OBJECTIVE FS.1 - (Core Requirement 7) Facility safety documentation in support of SN process operations,is in place and has been implemented that describes the safety envelope of the facility. The, safety documentation should characterize the hazards/risks associated with the facility and should, identify preventive and mitigating measures (e.g., systems, procedures, and administrative, controls) that protect workers and the public from those hazards/risks. (Old Core Requirement 4) Criteria 1. A DSA has been prepared by FWENC, approved by DOE, and implemented to reflect the SN process operations in the WPF. (10 CFR 830.200, DOE-STD-3009-94) 2. A configuration control program is in place and functioning such that the DSA is

326

ENSURING ADEQUATE SAFETY WHEN USING HYDROGEN AS A FUEL  

DOE Green Energy (OSTI)

Demonstration projects using hydrogen as a fuel are becoming very common. Often these projects rely on project-specific risk evaluations to support project safety decisions. This is necessary because regulations, codes, and standards (hereafter referred to as standards) are just being developed. This paper will review some of the approaches being used in these evolving standards, and techniques which demonstration projects can implement to bridge the gap between current requirements and stakeholder desires. Many of the evolving standards for hydrogen-fuel use performance-based language, which establishes minimum performance and safety objectives, as compared with prescriptive-based language that prescribes specific design solutions. This is being done for several reasons including: (1) concern that establishing specific design solutions too early will stifle invention, (2) sparse performance data necessary to support selection of design approaches, and (3) a risk-adverse public which is unwilling to accept losses that were incurred in developing previous prescriptive design standards. The evolving standards often contain words such as: ''The manufacturer shall implement the measures and provide the information necessary to minimize the risk of endangering a person's safety or health''. This typically implies that the manufacturer or project manager must produce and document an acceptable level of risk. If accomplished using comprehensive and systematic process the demonstration project risk assessment can ease the transition to widespread commercialization. An approach to adequately evaluate and document the safety risk will be presented.

Coutts, D

2007-01-22T23:59:59.000Z

327

Safety and Security Enforcement Program  

NLE Websites -- All DOE Office Websites (Extended Search)

Enforcement Enforcement Enforcement Home Worker Safety and Health Enforcement Office of Nuclear Safety Enforcement Security Enforcement Notices of Violation Consent Orders / Settlement Agreements Compliance Orders Special Report Orders Enforcement Letters Regulatory Assistance Reviews Enforcement Program and Process Guidance and Information Non-Compliance Tracking System (NTS) Non-Compliance Reporting Thresholds Regulations and Directives Enforcement Staff Enforcement Coordinator Contact Information 2013 DOE Safety and Security Enforcement Workshop Request for Investigation or Inspection of Safety or Security Violations Archived Documents HSS Logo Safety and Security Enforcement Program Office of Enforcement and Oversight What's New: » Worker Safety and Health Enforcement Preliminary Notice of Violation issued to Brookhaven Science Associates, LLC

328

Safety System Oversight  

NLE Websites -- All DOE Office Websites (Extended Search)

Safety System Oversight Safety System Oversight Office of Nuclear Safety Home Safety System Oversight Home Annual SSO/FR Workshop DOE Safety Links › ORPS Info › Operating Experience Summary › DOE Lessons Learned › Accident Investigation Program Assessment Tools › SSO CRADS Subject Matter Links General Program Information › Program Mission Statement › SSO Program Description › SSO Annual Award Program › SSO Annual Award › SSO Steering Committee › SSO Program Assessment CRAD SSO Logo Items Site Leads and Steering Committee Archive Facility Representative Contact Us HSS Logo SSO SSO Program News Congratulations to Ronnie L. Alderson of Nevada Field Office, the Winner of the 2012 Safety System Oversight Annual Award! 2012 Safety System Oversight Annual Award Nominees SSO Staffing Analysis

329

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

Science Conference Proceedings (OSTI)

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

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

1996-06-01T23:59:59.000Z

330

Guideline for the Treatment of Uncertainty in Risk-Informed Applications  

Science Conference Proceedings (OSTI)

In all scientific and engineering endeavors, there exists some level of uncertainty about the outcome. The development and application of a probabilistic risk assessment (PRA) is no exception. The uncertainty in the PRA model and its results manifests itself in several forms, including parametric, modeling, and completeness uncertainty. Various methods exist to both account for uncertainty in the model and evaluate the impact of uncertainty on the outcome of the analysis. However, these methods have gene...

2006-10-09T23:59:59.000Z

331

The Zion integrated safety analysis for NUREG-1150  

SciTech Connect

The utility-funded Zion Probabilistic Safety Study provided not only a detailed and thorough assessment of the risk profile of Zion Unit 1, but also presented substantial advancement in the technology of probabilistic risk assessment (PRA). Since performance of that study, modifications of plant hardware, the introduction of new emergency procedures, operational experience gained, information generated by severe accident research programs and further evolution of PRA and uncertainty analysis methods have provided a basis for reevaluation of the Zion risk profile. This reevaluation is discussed in this report. 5 refs.

Unwin, S.D.; Park, C.K.

1988-01-01T23:59:59.000Z

332

Risk Assessment Technical Expert Working Group (RWG)Conference Call  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

May 6, 2010 May 6, 2010 Risk Assessment Technical Expert Working Group (RWG)Conference Call Minutes, May 6, 2010 Risk Assessment Information Notice (IN): HSS provided the draft IN to safety basis experts from SNL, Y-12 and PNNL for their review and comment. Their comments were addressed and the IN is back into concurrence. 2. DNFSB Brief: HSS is coordinated with the RWG and DNFSB to schedule a DNFSB brief in June. 3. Risk Assessment Training: The National Training Center is presenting its risk assessment overview course May 18-20 at DOE headquarters. HS-20 is planning to discuss DOE's nuclear safety risk assessment study and plans for policy and guidance development at the end of the course. 4. External Risk Study: Data collection has been completed at NASA, NEI, NASA, and FDA. HS-20

333

Lift truck safety review  

SciTech Connect

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.

Cadwallader, L.C.

1997-03-01T23:59:59.000Z

334

Pipeline Safety  

Science Conference Proceedings (OSTI)

Pipeline Safety. Summary: Our goal is to provide standard test methods and critical data to the pipeline industry to improve safety and reliability. ...

2012-11-13T23:59:59.000Z

335

Balancing radiation benefits and risks: The needs of an informed public  

Science Conference Proceedings (OSTI)

The American public`s perceptions regarding ionizing radiation do not always conform to or correlate with scientific evidence. The ultimate purpose of this coordinated Federal effort and report is to increase the public`s knowledge of the benefits and risks associated with ionizing radiation. This report is divided into five sections. The first section, Introduction, discusses the public`s knowledge of radiation, their perceptions of benefits versus risks, and the Federal government`s role in public education. The section also outlines the charge to the Subpanel. Radiation Issues and Public Reactions discusses several radiation issues important to Federal agencies for which public education programs need to be established or enhanced. Federal Programs describes Federal agencies with public education programs on radiation and the nature of the programs they support. Education Issues and Federal Strategies explores the elements identified by the Subpanel as critical to the development and implementation of an effective Federal program in the area of public education on radiation issues and nuclear technologies. An important issue repeatedly brought up during the public sector presentations to the Subpanel was the perceived lack of Federal credibility on radiation issues in the eyes of the public. To some degree, this concern was factored into all of the recommendations developed by the subpanel. The issues discussed in this section include the fragmented nature of Federal radiation programs and the need to improve credibility, promote agency responsiveness, and support the enhancement of scientific literacy. Finally, under Recommendations, the Subpanel discusses its overall findings and conclusions.

Not Available

1994-04-01T23:59:59.000Z

336

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

Energy.gov (U.S. Department of Energy (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.

337

Overview of DOE-NE Proliferation and Terrorism Risk Assessment  

SciTech Connect

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

Sadasivan, Pratap [Los Alamos National Laboratory

2012-08-24T23:59:59.000Z

338

Status of clinical gene sequencing data reporting and associated risks for information loss  

Science Conference Proceedings (OSTI)

Clinical gene sequencing is growing in importance and cost-effectiveness. In the past two years, the number of genes associated with disease has grown by roughly 25%. Knowledge of genetic variations will soon guide drug selection and dosages, predict ... Keywords: Algorithms, Automatic data processing, Computational biology, Computer-assisted, DNA/Analysis, Diagnosis, Diagnostic use, Genetics, Genome, Human, Information storage and retrieval, Variation (genetics)

Douglas R. Mitchell; Joyce A. Mitchell

2007-02-01T23:59:59.000Z

339

Safety and Performance Assessment of Ethanol/Diesel Blends (E-Diesel)  

DOE Green Energy (OSTI)

Subcontract report discussing safety concerns of ethanol-diesel blends and pathways to reducing risks.

Waterland, L. R.; Venkatesh, S.; Unnasch, S.

2003-09-01T23:59:59.000Z

340

INDUSTRIAL SAFETY & HEALTH (ISH)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

BASIS (SB) BASIS (SB) OBJECTIVE SB.1 Facility safety documentation is in place and has been implemented that describes the "safety envelope" of the facility. The safety documentation should characterize the hazards/risks associated with the facility and should identify preventive and mitigating measures (systems, procedures, administrative controls, etc.) that protect workers and the public form those hazards/risks. Safety structures, systems and components (SSCs) are defined and a system to maintain control over their designs and modification is established. (Core Requirement 7) Criteria 1. The TA-55 SST Facility safety basis and related documentation address the full spectrum of hazards/risks associated with operations. 2. Controls designed to mitigate the consequence of analyzed TA-55 SST Facility

Note: This page contains sample records for the topic "risk informed safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

inform  

Science Conference Proceedings (OSTI)

The monthly member publication of AOCS. inform Inform Magazine Membership Merchandise Subscriptions Journals Membership Merchandise 8C5A902BB64F1A5D499524EFF5918AE0 INFORM-NM 2008

342

Estimating Overall Risk of Dam Failure: Practical Considerations in Combining Failure Probabilities ANCOLD 2003 Risk Workshop Page 1  

E-Print Network (OSTI)

% 80% 90% 100% M N P Q R P AP ANP NP DAM: D E F G H - - - Flood Concrete Gravity Section Under drainDAM SAFETY DECISION-MAKING: COMBINING ENGINEERING ASSESSMENTS WITH RISK INFORMATION David S. Bowles breaching a dam; so drop the matter before a dispute breaks out. Proverbs 17:14 (NIV) ABSTRACT A decision

Bowles, David S.

343

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

SciTech Connect

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

Pete Jordan

2010-09-01T23:59:59.000Z

344

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

Science Conference Proceedings (OSTI)

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

Not Available

1992-11-01T23:59:59.000Z

345

Safety, Security  

NLE Websites -- All DOE Office Websites (Extended Search)

Safety, Security Safety, Security Safety, Security LANL'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 work Our commitments We conduct our work safely and responsibly to achieve our mission. We ensure a safe and healthful environment for workers, contractors, visitors, and other on-site personnel. We protect the health, safety, and welfare of the general public. We do not compromise safety for personal, programmatic, or

346

Reliability and Risk Significance: For Maintenance and Reliability Professionals at Nuclear Power Plants (Japanese Version)  

Science Conference Proceedings (OSTI)

This Japanese version of Report 1007079 explains the connections between the reliability and availability of commercial nuclear power plant components and their risk significance as measured by a probabilistic safety assessment (PSA). The scope covers the two most common measures of risk significance and how they can be used to inform plant decision makers about risk. It also provides guidance on achieving balance between reliability and availability when performing preventive maintenance (PM) and on est...

2012-06-19T23:59:59.000Z

347

Argonne CNM: Safety Training  

NLE Websites -- All DOE Office Websites (Extended Search)

Safety at Work Safety at Work (printable pdf version) In case of emergency or if you need help or assistance dial Argonne's Protective Force: 911 (from Argonne phones) or (630) 252-1911 (from cell phones) As a staff member or user at the Center for Nanoscale Materials (CNM), you need to be aware of safety regulations at Argonne National Laboratory. You are also required to have taken any safety, orientation, and training classes or courses specified by your User Work Authorization(s) and/or work planning and control documents prior to beginning your work. For safety and security reasons, it is necessary to know of all facility users present in the CNM (Buildings 440 and 441). Users are required to sign in and out in the visitors logbook located in Room A119. Some detailed emergency information is provided on the Argonne National Laboratory web site. Brief instructions and general guidelines follow.

348

Tank farm health and safety plan. Revision 2  

SciTech Connect

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

Mickle, G.D.

1995-03-29T23:59:59.000Z

349

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

Science Conference Proceedings (OSTI)

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

Blanchard, A.

1999-04-15T23:59:59.000Z

350

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

SciTech Connect

OAK-B135 Research under this project addresses the barriers to long term use of nuclear-generated electricity in the United States. It was agreed that a very basic and significant change to the current method of design and regulation was needed. That is, it was believed that the cost reduction goal could not be met by fixing the current system (i.e., an evolutionary approach) and a new, more advanced approach for this project would be needed. It is believed that a completely new design and regulatory process would have to be developed--a ''clean sheet of paper'' approach. This new approach would start with risk-based methods, would establish probabilistic design criteria, and would implement defense-in-depth only when necessary (1) to meet public policy issues (e.g., use of a containment building no matter how low the probability of a large release is) and (2) to address uncertainties in probabilistic methods and equipment performance. This new approach is significantly different from the Nuclear Regulatory Commission's (NRC) current risk-informed program for operating plants. For our new approach, risk-based methods are the primary means for assuring plant safety, whereas in the NRC's current approach, defense-in-depth remains the primary means of assuring safety. The primary accomplishments in the first year--Phase 1 were (1) the establishment of a new, highly risk-informed design and regulatory framework, (2) the establishment of the preliminary version of the new, highly risk-informed design process, (3) core damage frequency predictions showing that, based on new, lower pipe rupture probabilities, the design of the emergency core cooling system equipment can be simplified without reducing plant safety, and (4) the initial development of methods for including uncertainties in a new integrated structures-systems design model. Under the new regulatory framework, options for the use of ''design basis accidents'' were evaluated. It is expected that design basis accidents would be an inherent part of the Probabilistic Safety Assessment for the plant and their evaluation would be probabilistic. Other first year accomplishments include (1) the conversion of an NRC database for cross-referencing NRC criteria and industry codes and standards to Microsoft 2000 software, (2) an assessment of the NRC's hearing process which concluded that the normal cross-examination during public hearings is not actually required by the U.S. Administrative Procedures Act, (3) the identification and listing of reliability data sources, and (4) interfacing with other industry groups (e.g., NEI and IAEA) and NRC at workshops for risk-informing regulations. The major accomplishments during the second year consisted of (1) issuance of the final report for Subtask 1.1, ''Identify Current Applicable Regulatory Requirements [and Industry Standards],'' (2) issuance of the final report for Subtask 1.2,'' Identify Structures, Systems, and Components and Their Associate d Costs for a Typical Plant,'' (3) extension of the new, highly risk-informed design and regulatory framework to non-light-water-reactor technology, (4) completion of more detailed thermal-hydraulic and probabilistic analyses of advanced conceptual reactor system/component designs, (6) initial evaluation and recommendations for improvement of the NRC design review process, and (7) initial development of the software format, procedures and statistical routines needed to store, analyze and retrieve the available reliability data. Final reports for Subtasks 1.1 (regulatory and design criteria) and 1.2 (costs for structures, systems, and components) were prepared and issued. A final report for Subtask 1.3 (Regulatory Framework) was drafted with the aim to issue it in Phase 3 (Year 3). One technical report was produced for Subtask 1.4 (methods development) and two technical reports were produced for Subtask 1.6 (sample problem analysis). An interim report on the NRC design review process (Subtask 1.7) was prepared and issued. Finally, a report on Subtask 2.2 (database weaknesses) addressed the i

Stanley E. Ritterbusch, et. al.

2003-01-29T23:59:59.000Z

351

Safety Bulletins  

NLE Websites -- All DOE Office Websites (Extended Search)

2009-01: Sulfur Hexafluoride Awareness Safety Bulletin 2008-03: Reporting Work-Related Heart Attacks Safety Bulletin 2008-02: Quality Assurance Concern at Wright Industries, Inc....

352

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...

353

Alerting device and method for reminding a person of a risk  

DOE Patents (OSTI)

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

Runyon, Larry [Richland, WA; Gunter, Wayne M [West Richland, WA; Pratt, Richard M [Richland, WA

2001-11-27T23:59:59.000Z

354

Fuzzy-algebra uncertainty analysis for abnormal-environment safety assessment  

Science Conference Proceedings (OSTI)

Many safety (risk) analyses depend on uncertain inputs and on mathematical models chosen from various alternatives, but give fixed results (implying no uncertainty). Conventional uncertainty analyses help, but are also based on assumptions and models, the accuracy of which may be difficult to assure. Some of the models and assumptions that on cursory examination seem reasonable can be misleading. As a result, quantitative assessments, even those accompanied by uncertainty measures, can give unwarranted impressions of accuracy. Since analysis results can be a major contributor to a safety-measure decision process, risk management depends on relating uncertainty to only the information available. The uncertainties due to abnormal environments are even more challenging than those in normal-environment safety assessments, and therefore require an even more cautious approach. A fuzzy algebra analysis is proposed in this report that has the potential to appropriately reflect the information available and portray uncertainties well, especially for abnormal environments.

Cooper, J.A.

1994-01-01T23:59:59.000Z

355

Practical Guidance on the Use of Probabilistic Risk Assessment in Risk-Informed Applications with a Focus on the Treatment of Uncert ainty  

Science Conference Proceedings (OSTI)

BackgroundNeither the Nuclear Regulatory Commission (NRC) nor the industry intends to use probabilistic risk assessment (PRA) as a total replacement for traditional deterministic approaches. PRA is viewed as a complement to the deterministic method. In fact, probabilistic and deterministic methods are acknowledged as extensions of each other rather than as separate and distinct.Both the industry and the NRC are incorporating risk concepts and techniques into ...

2012-12-04T23:59:59.000Z

356

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

SciTech Connect

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

Sadasivan, Pratap [Los Alamos National Laboratory

2012-06-21T23:59:59.000Z

357

Relative risks of energy sources  

Science Conference Proceedings (OSTI)

This paper compares the risks associated with various energy sources in an attempt to demonstrate the relative safety of nuclear energy. (JEF)

Haire, M.J.

1990-01-01T23:59:59.000Z

358

Slideshow, National Safety Month- June 2013  

Energy.gov (U.S. Department of Energy (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.

359

Seismic Safety Guide  

SciTech Connect

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

Eagling, D.G. (ed.)

1983-09-01T23:59:59.000Z

360

Modeling object identification and tracking errors on automated spatial safety assessment of earthmoving operations.  

E-Print Network (OSTI)

??Recent research studies have been conducted for automating the safety assessment process in order to identify risks and safety hazards on a job site without… (more)

Chi, Seok Ho

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "risk informed safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

Safety Advisories  

NLE Websites -- All DOE Office Websites (Extended Search)

Safety Advisories Safety Advisories 2010 2010-08 Safety Advisory - Software Quality Assurance Firmware Defect in Programmable Logic Controller 2010-07 Safety Advisory - Revised Counterfeit Integrated Circuits Indictment 2010-06 Safety Advisory - Counterfeit Integrated Circuits Indictment 2010-05 Safety Advisory - Contact with Overhead Lines and Ground Step Potential 2010-04 Update - Leaking Acetylene Cylinder Shutoff Valves 2010-03 - Software Quality Assurance Microsoft Excel Software Issue 2010-02 - Leaking Acetylene Cylinder Shutoff Valves 2010-01 Update - Defective Frangible Ammunition 2009 2009-05 Software Quality Assurance - Errors in MACCS2 x/Q Calculations 2009-04 Update - SEELER Exothermic Torch 2009-03 - Defective Frangible Ammunition 2009-02 - Recall of Defense Technology Distraction Devices

362

Thermal Reactor Safety  

Science Conference Proceedings (OSTI)

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

Not Available

1980-06-01T23:59:59.000Z

363

Safety Standards  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

US DOE Workshop US DOE Workshop September 19-20, 2012 International perspective on Fukushima accident Miroslav Lipár Head, Operational Safety Section M.Lipar@iaea.org +43 1 2600 22691 2 Content * The IAEA before Fukushima -Severe accidents management * The IAEA actions after Fukushima * The IAEA Action plan on nuclear safety * Measures to improve operational safety * Conclusions THE IAEA BEFORE FUKUSHIMA 4 IAEA Safety Standards IAEA Safety Standards F undamental S afety Principles Safety Fundamentals f o r p ro te c ti n g p e o p l e a n d t h e e n v i ro n m e n t IAEA Safety Standards Regulations for the Safe Transport of Radioactive Material 2005 E dit ion Safety Requirements No. T S-R-1 f o r p ro te c ti n g p e o p l e a n d t h e e n v i ro n m e n t IAEA Safety Standards Design of the Reactor Core for Nuclear Power Plants

364

Safety - Cyclotron  

NLE Websites -- All DOE Office Websites (Extended Search)

Safety The Nuclear Sciences Division (NSD) is committed to providing a safe workplace for its employees, contractors, and guests and conducting its research and operations in a...

365

Winter Safety Information & Tips  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

7 7 1 WINTER TERMINOLOGY It' s important that you understand winter storm terms so that you can prepare adequately, whether you are walking to the store or driving across the state. * Winter Weather Advisory : Issued when snow, sleet, freezing rain, or combination of precipitation types is expected to cause a significant inconvenience but not serious enough to warrant a warning. * Snow Advisory: - 2-4 inches of snow in a 12 hour period * Freezing Rain Advisory: - Ice accumulations of less than 1/4 inch * Ice Storm Warning: - 1/4 inch or more of ice accumulation January 2007 2 WINTER TERMINOLOGY * Winter Storm Watch: Issued when there is the potential for significant and hazardous winter weather within 48 hours. It does not mean that significant and hazardous winter weather will occur...it only means it is possible. - Significant and hazardous winter weather is defined as: * Over 5

366

Safety Design Strategy RM  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Safety Design Strategy Review Module Safety Design Strategy Review Module March 2010 OFFICE OF ENVIRONMENTAL MANAGEMENT Standard Review Plan (SRP) Safety Design Strategy (SDS) Review Module Critical Decision (CD) Applicability CD-0 CD-1 CD-2 CD-3 CD-4 Post Operation March 2010 Standard Review Plan, March 2010 i FOREWORD The Standard Review Plan (SRP) 1 provides a consistent, predictable corporate review framework to ensure that issues and risks that could challenge the success of Office of Environmental Management (EM) projects are identified early and addressed proactively. The internal EM project review process encompasses key milestones established by DOE O 413.3A, Change 1, Program and Project Management for the Acquisition of Capital Assets, DOE-STD-1189-2008,

367

Preliminary Safety Design RM  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Preliminary Safety Design Review Module Preliminary Safety Design Review Module March 2010 CD-0 O 0 OFFICE OF Pr C CD-1 F ENVIRO Standard R reliminar Rev Critical Decis CD-2 M ONMENTAL Review Plan ry Safety view Module sion (CD) Ap CD March 2010 L MANAGE n (SRP) y Design e pplicability D-3 EMENT CD-4 Post Ope eration Standard Review Plan, 2 nd Edition, March 2010 i FOREWORD The Standard Review Plan (SRP) 1 provides a consistent, predictable corporate review framework to ensure that issues and risks that could challenge the success of Office of Environmental Management (EM) projects are identified early and addressed proactively. The internal EM project review process encompasses key milestones established by DOE O 413.3A, Change 1, Program and Project Management for the Acquisition of Capital Assets, DOE-STD-1189-2008,

368

Conceptual Safety Design RM  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Conceptual Safety Design Review Module Conceptual Safety Design Review Module March 2010 CD-0 O 0 OFFICE OF C C CD-1 F ENVIRO Standard R Conceptua Rev Critical Decis CD-2 M ONMENTAL Review Plan al Safety view Module sion (CD) Ap CD March 2010 L MANAGE n (SRP) y Design e pplicability D-3 EMENT CD-4 Post Ope eration Standard Review Plan, 2 nd Edition, March 2010 i FOREWORD The Standard Review Plan (SRP) 1 provides a consistent, predictable corporate review framework to ensure that issues and risks that could challenge the success of Office of Environmental Management (EM) projects are identified early and addressed proactively. The internal EM project review process encompasses key milestones established by DOE O 413.3A, Change 1, Program and Project Management for the Acquisition of Capital

369

Life Cycle Management of Chemicals: Conceptual Design for Information Management  

Science Conference Proceedings (OSTI)

Tracking the acquisition, use, and disposition of chemicals allows companies to reduce costs; manage risks to health, safety, and the environment; and improve compliance and reporting efficiency. This report provides a means of identifying and evaluating chemical life cycle information management needs. The conceptual design presented here will guide utilities through development of a custom system for managing chemical life cycle data.

1999-08-10T23:59:59.000Z

370

The Sixth Risk-Informed Inservice Inspection (RI-ISI) Workshop: Living Requirements, Lessons Learned, and New Initiatives Meeting No tes  

Science Conference Proceedings (OSTI)

The Sixth Risk-Informed Inservice Inspection (RI-ISI) Workshop was held in Hilton Head, South Carolina, USA, on July 29 and 30, 2004. It consisted of two days of training, presentations, a discussion forum, and evaluation of plant-specific results. Attendees included representatives from domestic and international utilities and support organizations. This workshop provided training to personnel investigating the feasibility of implementing RI-ISI methodologies, lessons learned in the development and impl...

2004-11-09T23:59:59.000Z

371

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

DOE Green Energy (OSTI)

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

Nelson, B.P.; Crandall, R.S. (National Renewable Energy Lab., Golden, CO (United States)); Moskowitz, P.D.; Fthenakis, V.M. (Brookhaven National Lab., Upton, NY (United States))

1992-01-01T23:59:59.000Z

372

Environment/Health/Safety (EHS): Safety Engineering  

NLE Websites -- All DOE Office Websites (Extended Search)

Safety Engineering Safety Engineering provides occupational safety services to support the Lab's mission. This includes injury and illness prevention and loss control systems for...

373

Integrated Safety Management (ISM) - Safety Culture Resources  

NLE Websites -- All DOE Office Websites (Extended Search)

Safety Culture Resources Integrated Safety Management (ISM) Safety from the Operator's Perspective: We are All in this Together (2005) - Jim Ellis, President and CEO, Institute of...

374

Safety System Oversight: 2010 Safety System Oversight Workshop  

NLE Websites -- All DOE Office Websites (Extended Search)

Safety System Oversight Office of Nuclear Safety Home Safety System Oversight Home Annual SSO/FR Workshop DOE Safety Links › ORPS Info › Operating Experience Summary › DOE Lessons Learned › Accident Investigation Program Assessment Tools › SSO CRADS Subject Matter Links General Program Information › Program Mission Statement › SSO Program Description › SSO Annual Award Program › SSO Annual Award › SSO Steering Committee › SSO Program Assessment CRAD SSO Logo Items Site Leads and Steering Committee Archive Facility Representative Contact Us HSS Logo SSO SSO 2012 SAFETY SYSTEM OVERSIGHT ANNUAL AWARD Congratulations to Ronnie Alderson, Nevada Field Office, the Winner of the 2012 DOE Safety System Oversight Annual Award! 2012 NOMINEES: Charles Maggart Idaho Operations Office

375

Facility Representative Program: Nuclear Safety Basis Fundamentals...  

NLE Websites -- All DOE Office Websites (Extended Search)

Qualification Information Qualification Standards DOE Order Self-Study Modules DOE Fundamentals Handbooks Nuclear Safety Basis Self-Study Guide Energy Online Courses Available...

376

Ferrocyanide Safety Project: FY 1991 annual report  

SciTech Connect

The Hanford Ferrocyanide Task Team is addressing issues involving ferrocyanide precipitates in the single-shell waste storage tanks (SSTs), in particular the risk of explosion. This Task Team, which is composed of researchers from Westinghouse Hanford Company (WHC), Pacific Northwest Laboratory (PNL), an outside consultants, was formed in response to the need for an updated analysis of safety questions on the Hanford SSTSs. The Ferrocyanide Safety Project, discussed in this report, is being conducted by PNL as part of the Waste Tank Safety Program led by WHC. The overall purpose of the WHC program, which is sponsored by the US Department of Energy`s Tank Safety Project Office, is to provide technical information on ferrocyanide chemistry and its interaction and reactive behavior with other tank constituents. Ultimately, this information will be used to maintain the tanks in a safe condition, implement interim stabilization strategies, and identify optimal disposal options. While by itself ferrocyanide is a stable complex of ferrous ion and cyanide, it can be made to explode in the laboratory in the presence of oxidizing materials such as nitrates and/or nitrites temperatures above 280{degree}C or by sufficient electrical spark. The specific goal of the PNL project is so determine the conditions necessary for the ferrocyanide-bearing wastes in Hanford SSTs to represent a hazard, to determine the conditions where these same wastes am not a hazard, or to determine the conditions which are necessary to assure the wastes are safe prior to treatment for permanent disposal. This annual report gives the results of the work conducted by PNL in FY 1991. The activities mainly focused on preparing and characterizing synthetic wastes and alkali nickel ferrocyanides produced using the In-Farm cesium scavenging flowsheet and pure potential nickel ferrocyanides that could be produced by all of the cesium scavenging flowsheets.

Hallen, R.T.; Burger, L.L.; Hockey, R.L.; Lilga, M.A.; Scheele, R.D.; Tingey, J.M.

1992-06-01T23:59:59.000Z

377

Ferrocyanide Safety Project: FY 1991 annual report  

SciTech Connect

The Hanford Ferrocyanide Task Team is addressing issues involving ferrocyanide precipitates in the single-shell waste storage tanks (SSTs), in particular the risk of explosion. This Task Team, which is composed of researchers from Westinghouse Hanford Company (WHC), Pacific Northwest Laboratory (PNL), an outside consultants, was formed in response to the need for an updated analysis of safety questions on the Hanford SSTSs. The Ferrocyanide Safety Project, discussed in this report, is being conducted by PNL as part of the Waste Tank Safety Program led by WHC. The overall purpose of the WHC program, which is sponsored by the US Department of Energy's Tank Safety Project Office, is to provide technical information on ferrocyanide chemistry and its interaction and reactive behavior with other tank constituents. Ultimately, this information will be used to maintain the tanks in a safe condition, implement interim stabilization strategies, and identify optimal disposal options. While by itself ferrocyanide is a stable complex of ferrous ion and cyanide, it can be made to explode in the laboratory in the presence of oxidizing materials such as nitrates and/or nitrites temperatures above 280{degree}C or by sufficient electrical spark. The specific goal of the PNL project is so determine the conditions necessary for the ferrocyanide-bearing wastes in Hanford SSTs to represent a hazard, to determine the conditions where these same wastes am not a hazard, or to determine the conditions which are necessary to assure the wastes are safe prior to treatment for permanent disposal. This annual report gives the results of the work conducted by PNL in FY 1991. The activities mainly focused on preparing and characterizing synthetic wastes and alkali nickel ferrocyanides produced using the In-Farm cesium scavenging flowsheet and pure potential nickel ferrocyanides that could be produced by all of the cesium scavenging flowsheets.

Hallen, R.T.; Burger, L.L.; Hockey, R.L.; Lilga, M.A.; Scheele, R.D.; Tingey, J.M.

1992-06-01T23:59:59.000Z

378

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

Science Conference Proceedings (OSTI)

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

Glantz, C.S.; DiMassa, F.V.; Pelto, P.J.; Brothers, A.J. [Pacific Northwest Lab., Richland, WA (United States); Roybal, A.L. [Western Area Power Administration, Golden, CO (United States)

1994-12-01T23:59:59.000Z

379

Safety_Tips_for_Christmas_Shopping-DEC-2011  

NLE Websites -- All DOE Office Websites (Extended Search)

Christmas Shopping The holiday shopping season can be a time of great joy safety risks. Below are some safety tips to keep in mind while shopping. * Carry a cell phone and program...

380

Nuclear Safety Research and Development Status Workshop Summary  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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

Note: This page contains sample records for the topic "risk informed safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

Carlsbad Industrial Safety and Health PIA, Carlsbad Field Offce...  

NLE Websites -- All DOE Office Websites (Extended Search)

Publications Integrated Safety Management Workshop Registration, PIA, Idaho National Laboratory MOX Services Unclassified Information System PIA, National Nuclear Services...

382

DOE | Office of Health, Safety and Security | Health and Safety  

NLE Websites -- All DOE Office Websites (Extended Search)

"Worker Safety and Health Program" FAQs "Worker Safety and Health Program" FAQs 10 CFR 851 “Worker Safety and Health Program" Frequently Asked Questions Updated October 19, 2010 Please Note: The responses to the following Frequently Asked Questions are not Official interpretations, only the Office of General Counsel may issue and interpretive ruling. Please see 10 CFR 851.7 and 851.8 for more information. Subpart A—General Provisions 851.1 Scope and purpose. 851.2 Exclusions. 851.3 Definitions. 851.4 Compliance order. 851.5 Enforcement. 851.6 Petitions for generally applicable rulemaking. 851.7 Request for a binding interpretive ruling. 851.8 Informal requests for information. Subpart B—Program Requirements 851.10 General requirements. 851.11 Development and approval of worker safety and health program.

383

Safety Bulletins  

NLE Websites -- All DOE Office Websites (Extended Search)

The Office of Health, Safety and Security HSS Logo Department of Energy Seal Left Tab SEARCH Right Tab TOOLS Right Tab Left Tab HOME Right Tab Left Tab ABOUT US Right Tab Left Tab...

384

Safety Advisories  

NLE Websites -- All DOE Office Websites (Extended Search)

The Office of Health, Safety and Security HSS Logo Department of Energy Seal Left Tab SEARCH Right Tab TOOLS Right Tab Left Tab HOME Right Tab Left Tab ABOUT US Right Tab Left Tab...

385

Safety Alerts  

NLE Websites -- All DOE Office Websites (Extended Search)

The Office of Health, Safety and Security HSS Logo Department of Energy Seal Left Tab SEARCH Right Tab TOOLS Right Tab Left Tab HOME Right Tab Left Tab ABOUT US Right Tab Left Tab...

386

Safety Bulletin  

NLE Websites -- All DOE Office Websites (Extended Search)

those analyzed in the documented safety analysis. BACKGROUND On March 11 , 2011 , the Fukushima Daiichi nuclear power station in Japan was damaged by a magnitude 9.0 earthquake and...

387

Biological Safety  

NLE Websites -- All DOE Office Websites (Extended Search)

The Office of Health, Safety and Security HSS Logo Department of Energy Seal Left Tab SEARCH Right Tab TOOLS Right Tab Left Tab HOME Right Tab Left Tab ABOUT US Right Tab Left Tab...

388

CHSP: Material Safety Data Sheets  

NLE Websites -- All DOE Office Websites (Extended Search)

HYGIENE HYGIENE AND SAFETY PLAN CHSP SITE MAP WHO TO CALL MATERIAL SAFETY DATA SHEETS ROLES AND RESPONSIBILITIES arrow image CHEMICAL PROCUREMENT, TRANSPORTATION AND INVENTORY arrow image CHEMICAL HAZARD: DEFINITION arrow image CHEMICAL HAZARD ASSESSMENTS arrow image HAZARD CONTROLS arrow image TRAINING AND HAZARD INFORMATION arrow image EXPOSURE MONITORING & MEDICAL CONSULTATION arrow image APPENDICES arrow image FAQs QUESTIONS Search the CHSP: > Go spacer image EH&S Home PUB 3000 LBNL Home LBNL A-Z Index LBNL Search LBNL Phone Book Privacy & Security Notice spacer spacer image spacer image Material Safety Data Sheets and Chemical Information Resources A Material Safety Data Sheet (MSDS) is a manufacturer/importer's informational document of a hazardous chemical that describes its physical and chemical properties, hazards, and recommended precautions for handling, storage and disposal. How to Read an MSDS

389

Nuclear Safety Management  

NLE Websites -- All DOE Office Websites (Extended Search)

[6450-01-P] [6450-01-P] DEPARTMENT OF ENERGY 10 CFR Part 830 Nuclear Safety Management AGENCY: Department of Energy (DOE). ACTION: Final Rule. SUMMARY: The Department of Energy (DOE) is issuing a final rule regarding Nuclear Safety Management. This Part establishes requirements for the safe management of DOE contractor and subcontractor work at the Department's nuclear facilities. Today's rule adopts the sections that will make up the generally applicable provisions for Part 830. It also adopts the specific section on provisions for developing and implementing a formalized quality assurance program. EFFECTIVE DATE: This regulation becomes effective [insert 30 days after publication in the Federal Register.] FOR FURTHER INFORMATION CONTACT: Frank Hawkins, U.S. Department of Energy, Nuclear Safety

390

Public Safety Communications  

Science Conference Proceedings (OSTI)

Public Safety Communication. Summary: ... the development of quantitative requirements for public safety communications. ...

2011-12-12T23:59:59.000Z

391

Applicability of trends in nuclear safety analysis to space nuclear power systems  

SciTech Connect

A survey is presented of some current trends in nuclear safety analysis that may be relevant to space nuclear power systems. This includes: lessons learned from operating power reactor safety and licensing; approaches to the safety design of advanced and novel reactors and facilities; the roles of risk assessment, extremely unlikely accidents, safety goals/targets; and risk-benefit analysis and communication.

Bari, R.A.

1992-10-01T23:59:59.000Z

392

CRAD, Safety Functions Assessment Plan | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Safety Functions Assessment Plan Safety Functions Assessment Plan CRAD, Safety Functions Assessment Plan Performance Objective: Management should be proactive in addressing safety-related issues. Management should have an established system to provide a ranking of safety considerations founded upon risk-based priorities. Criteria: A system is in place to provide a ranking of safety considerations founded upon risk-based priorities. (DOE/EH-0135) Procedures clearly define management's responsibility for safety-related decisions and provide for the escalation of matters in an appropriate time frame. (DOE/EH-0135) Management promotes safety programs and the organization's safety culture through sponsoring and attending safety meetings. (DOE/EH-0135) Management encourages and supports effective programs for reporting

393

Office of Nuclear Facility Safety Programs: Nuclear Facility Training  

NLE Websites -- All DOE Office Websites (Extended Search)

Safety (HS-30) Safety (HS-30) Office of Nuclear Safety Home » Directives » Nuclear and Facility Safety Policy Rules » Nuclear Safety Workshops Technical Standards Program » Search » Approved Standards » Recently Approved » RevCom for TSP » Monthly Status Reports » Archive » Feedback DOE Nuclear Safety Research & Development Program Office of Nuclear Safety Basis & Facility Design (HS-31) Office of Nuclear Safety Basis & Facility Design - About Us » Nuclear Policy Technical Positions/Interpretations » Risk Assessment Working Group » Criticality Safety » DOE O 420.1C Facility Safety » Beyond Design Basis Events Office of Nuclear Facility Safety Programs (HS-32) Office of Nuclear Facility Safety Programs - About Us » Facility Representative Program

394

Health and safety. Preliminary comparative assessment of the satellite power system (SPS) and other energy alternatives  

DOE Green Energy (OSTI)

Existing data on the health and safety risks of a satellite power system and four electrical generation systems are analyzed: a combined-cycle coal power system with a low-Btu gasifier and open-cycle gas turbine, a fission power system with fuel reprocessing, a central-station, terrestrial, solar-photovoltaic power system, and a first-generation design for a fusion power system. The systems are compared on the basis of expected deaths and person-days lost per year associated with 1000 MW of average electricity generation and the number of health and safety risks that are identified as potentially significant but unquantifiable. The appendices provide more detailed information on risks, uncertainties, additional research needed, and references for the identified impacts of each system.

Habegger, L.J.; Gasper, J.R.; Brown, C.D.

1980-04-01T23:59:59.000Z

395

Environmental, health, and safety issues of sodium-sulfur batteries for electric and hybrid vehicles. Volume 1, Cell and battery safety  

SciTech Connect

This report is the first of four volumes that identify and assess the environmental, health, and safety issues involved in using sodium-sulfur (Na/S) battery technology as the energy source in electric and hybrid vehicles that may affect the commercialization of Na/S batteries. This and the other reports on recycling, shipping, and vehicle safety are intended to help the Electric and Hybrid Propulsion Division of the Office of Transportation Technologies in the US Department of Energy (DOE/EHP) determine the direction of its research, development, and demonstration (RD&D) program for Na/S battery technology. The reports review the status of Na/S battery RD&D and identify potential hazards and risks that may require additional research or that may affect the design and use of Na/S batteries. This volume covers cell design and engineering as the basis of safety for Na/S batteries and describes and assesses the potential chemical, electrical, and thermal hazards and risks of Na/S cells and batteries as well as the RD&D performed, under way, or to address these hazards and risks. The report is based on a review of the literature and on discussions with experts at DOE, national laboratories and agencies, universities, and private industry. Subsequent volumes will address environmental, health, and safety issues involved in shipping cells and batteries, using batteries to propel electric vehicles, and recycling and disposing of spent batteries. The remainder of this volume is divided into two major sections on safety at the cell and battery levels. The section on Na/S cells describes major component and potential failure modes, design, life testing and failure testing, thermal cycling, and the safety status of Na/S cells. The section on batteries describes battery design, testing, and safety status. Additional EH&S information on Na/S batteries is provided in the appendices.

Ohi, J.M.

1992-09-01T23:59:59.000Z

396

Design for safety framework for offshore oil and gas platforms.  

E-Print Network (OSTI)

??This main aim of this work is to develop a “design for safety” based risk assessment technique for the offshore platforms in order to facilitate… (more)

Umar, Abubakar Attah

2010-01-01T23:59:59.000Z

397

October 21, 2003, Board Public Meeting Presentations - NNSA Safety...  

NLE Websites -- All DOE Office Websites (Extended Search)

of the Facility Representative program to focus our technical resources on high risk facilities. This program is an essential element of our nuclear safety oversight...

398

Radiation and Chemical Risk Management [EVS Program Area]  

NLE Websites -- All DOE Office Websites (Extended Search)

Radiation and Chemical Risk Management Radiation and Chemical Risk Management EVS helps meet the challenge of protecting human health and the environment through the management of risk associated with radiation and chemicals in the environment. Protecting human health, welfare, and the environment in a world affected by energy production and technology is a global challenge. EVS helps to meet this challenge through research and analysis on the management of risk associated with radiation and chemicals in the environment. To improve the management of risk associated with nuclear and chemical materials and wastes at contaminated sites, we develop information and tools that support decision making related to health, safety, environmental, economic, and social-cultural concerns. Nuclear Materials and Waste Disposition

399

Risk Assessment Technical Expert Working Group (RAWG) Conference Call Minutes  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Risk Assessment Technical Expert Working Group (RWG) Risk Assessment Technical Expert Working Group (RWG) Conference Call Minutes May 6, 2010 PARTICIPANTS Members: Don Nichols (CDNS), Jim O'Brien (HSS), Carol Sohn (SC), Rich Stark (NE), Bill Weaver (EM for Steve Krahn), Todd Lapointe (CNS for Chip Lagdon) Others: Kamiar Jamali (NE), Andy Wallo (DNFSB 2009-1 Responsible Manager), Rama Sastry (HSS), Samuel Rosenbloom (HSS) SUMMARY 1. Risk Assessment Information Notice (IN): HSS provided the draft IN to safety basis experts from SNL, Y-12 and PNNL for their review and comment. Their comments were addressed and the IN is back into concurrence. 2. DNFSB Brief: HSS is coordinated with the RWG and DNFSB to schedule a DNFSB brief in June. 3. Risk Assessment Training: The National Training Center is presenting its risk assessment overview

400

Profiling risk sensibility through association rules  

Science Conference Proceedings (OSTI)

In the last recent years several approaches to risk assessment and risk management have been adopted to reduce the potential for specific risks in working environments. A safety culture has also developed to let workers acquire knowledge and understanding ... Keywords: Association rules, Frequent patterns, Risk perception, Risk propensity

Beatrice Lazzerini; Francesco Pistolesi

2013-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "risk informed safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

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

Science Conference Proceedings (OSTI)

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

Kaye, S.V.

1992-03-01T23:59:59.000Z

402

Radiation Safety  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Brotherhood of Locomotive Brotherhood of Locomotive Engineers & Trainmen Scott Palmer BLET Radiation Safety Officer New Hire Training New Hire study topics * GCOR * ABTH * SSI * Employee Safety * HazMat * Railroad terminology * OJT * 15-week class * Final test Hazardous Materials * Initial new-hire training * Required by OSHA * No specified class length * Open book test * Triennial module Locomotive Engineer Training A little bit older...a little bit wiser... * Typically 2-4 years' seniority * Pass-or-get-fired promotion * Intensive program * Perpetually tested to a higher standard * 20 Weeks of training * 15 of that is OJT * General Code of Operating Rules * Air Brake & Train Handling * System Special Instructions * Safety Instructions * Federal Regulations * Locomotive Simulators * Test Ride * Pass test with 90% Engineer Recertification

403

Lessons Learned from Safety Events  

SciTech Connect

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.

Weiner, Steven C.; Fassbender, Linda L.

2012-11-01T23:59:59.000Z

404

Boulder Safety Reps Receive 2010 NIST Safety Award  

Science Conference Proceedings (OSTI)

NIST Safety Award. Award Winner: Boulder Division Safety Representatives. Description: The NIST Safety Award, first presented ...

2011-10-25T23:59:59.000Z

405

Technical Framework for Management of Safety Margins—Loss of Main Feedwater Pilot Application  

Science Conference Proceedings (OSTI)

This report presents the results of a trial application to assess safety margins using a risk informed approach. The trial application focused on a pressurized water reactor (PWR) loss of feedwater (LOFW) event with failure of auxiliary feedwater (AFW), for which feed and bleed cooling would be required to prevent core damage. For this trial application the main parameters which impact core damage for the scenario were identified and distributions were constructed to represent the uncertainties associate...

2011-11-23T23:59:59.000Z

406

Office of Nuclear Safety - Directives  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear and Facility Safety Directives Nuclear and Facility Safety Directives The HSS Office of Nuclear Safety is the responsible office for the development, interpretation, and revision of the following Department of Energy (DOE) directives. Go to DOE's Directives Web Page to view these directives. DOE Order (O) 252.1A, Technical Standards Program DOE O 252.1A promotes DOE's use of Voluntary Consensus Standards (VCS) as the primary method for application of technical standards and establishes and manages the DOE Technical Standards Program (TSP) including technical standards development, information, activities, issues, and interactions. HS-30 Contact: Jeff Feit DOE Policy (P) 420.1, Department of Energy Nuclear Safety Policy DOE P 420.1, documents the Department's nuclear safety policy to design, construct, operate, and decommission its nuclear facilities in a manner that ensures adequate protection of workers, the public, and the environment.

407

Occupational Safety and Health Program at the West Valley Demonstration Project  

Science Conference Proceedings (OSTI)

The West Valley Nuclear Services Co. LLC (WVNS) is committed to provide a safe, clean, working environment for employees, and to implement U.S. Department of Energy (DOE) requirements affecting worker safety. The West Valley Demonstration Project (WVDP) Occupational Safety and Health Program is designed to protect the safety, health, and well-being of WVDP employees by identifying, evaluating, and controlling biological, chemical, and physical hazards in the work place. Hazards are controlled within the requirements set forth in the reference section at the end of this report. It is the intent of the WVDP Occupational Safety and Health Program to assure that each employee is provided with a safe and healthy work environment. This report shows the logical path toward ensuring employee safety in planning work at the WVDP. In general, planning work to be performed safely includes: combining requirements from specific programs such as occupational safety, industrial hygiene, radiological control, nuclear safety, fire safety, environmental protection, etc.; including WVDP employees in the safety decision-making processes; pre-planning using safety support re-sources; and integrating the safety processes into the work instructions. Safety management principles help to define the path forward for the WVDP Occupational Safety and Health Program. Roles, responsibilities, and authority of personnel stem from these ideals. WVNS and its subcontractors are guided by the following fundamental safety management principles: ''Protection of the environment, workers, and the public is the highest priority. The safety and well-being of our employees, the public, and the environment must never be compromised in the aggressive pursuit of results and accomplishment of work product. A graded approach to environment, safety, and health in design, construction, operation, maintenance, and deactivation is incorporated to ensure the protection of the workers, the public, and the environment.'' These principles are demonstrated through: Conducting all activities in an atmosphere of trust and confidence based on open, honest, and responsive communication. Using innovative and effective approaches to risk identification and management. Applying a systematic approach to planning and execution of all activities that affect the environment, safety, and health through use of the Integrated Environment, Safety, and Health Management System. Holding line management fully accountable to effectively plan and integrate environment, safety, and health activities into field activities. Providing clear policy and direction on environment, safety, and health issues to guide field work. Encouraging and promoting the sharing of environment, safety, and health information and resources. Empowering employees through training, information, tools, and program involvement to effectively protect themselves and the environment. Ensuring it is every employees' responsibility to identify and report potential safety and health hazards and environmental noncompliance. Together, as a team, we accomplish our mission while protecting the environment and preserving the safety and health of each employee and the public.

L. M. Calderon

1999-04-30T23:59:59.000Z

408

Risk Measures Constituting Risk Metrics for Decision Making in the Chemical Process Industry  

E-Print Network (OSTI)

The occurrence of catastrophic incidents in the process industry leave a marked legacy of resulting in staggering economic and societal losses incurred by the company, the government and the society. The work described herein is a novel approach proposed to help predict and mitigate potential catastrophes from occurring and for understanding the stakes at risk for better risk informed decision making. The methodology includes societal impact as risk measures along with tangible asset damage monetization. Predicting incidents as leading metrics is pivotal to improving plant processes and, for individual and societal safety in the vicinity of the plant (portfolio). From this study it can be concluded that the comprehensive judgments of all the risks and losses should entail the analysis of the overall results of all possible incident scenarios. Value-at-Risk (VaR) is most suitable as an overall measure for many scenarios and for large number of portfolio assets. FN-curves and F$-curves can be correlated and this is very beneficial for understanding the trends of historical incidents in the U.S. chemical process industry. Analyzing historical databases can provide valuable information on the incident occurrences and their consequences as lagging metrics (or lagging indicators) for the mitigation of the portfolio risks. From this study it can be concluded that there is a strong statistical relationship between the different consequence tiers of the safety pyramid and Heinrich‘s safety pyramid is comparable to data mined from the HSEES database. Furthermore, any chemical plant operation is robust only when a strategic balance is struck between optimal plant operations and, maintaining health, safety and sustaining environment. The balance emerges from choosing the best option amidst several conflicting parameters. Strategies for normative decision making should be utilized for making choices under uncertainty. Hence, decision theory is utilized here for laying the framework for choice making of optimum portfolio option among several competing portfolios. For understanding the strategic interactions of the different contributing representative sets that play a key role in determining the most preferred action for optimum production and safety, the concepts of game theory are utilized and framework has been provided as novel application to chemical process industry.

Prem, Katherine

2010-12-01T23:59:59.000Z

409

Gas Pipeline Safety (Indiana)  

Energy.gov (U.S. Department of Energy (DOE))

This section establishes the Pipeline Safety Division within the Utility Regulatory Commission to administer federal pipeline safety standards and establish minimum state safety standards for...

410

Electrical Safety Committee Charter  

NLE Websites -- All DOE Office Websites (Extended Search)

safety and electrical safety awareness within the APS. The committee shall implement policies and practices adopted by the ANL Electrical Safety Committee and shall assist the ANL...

411

Environmental, health, and safety issues of sodium-sulfur batteries for electric and hybrid vehicles  

SciTech Connect

This report is the first of four volumes that identify and assess the environmental, health, and safety issues involved in using sodium-sulfur (Na/S) battery technology as the energy source in electric and hybrid vehicles that may affect the commercialization of Na/S batteries. This and the other reports on recycling, shipping, and vehicle safety are intended to help the Electric and Hybrid Propulsion Division of the Office of Transportation Technologies in the US Department of Energy (DOE/EHP) determine the direction of its research, development, and demonstration (RD D) program for Na/S battery technology. The reports review the status of Na/S battery RD D and identify potential hazards and risks that may require additional research or that may affect the design and use of Na/S batteries. This volume covers cell design and engineering as the basis of safety for Na/S batteries and describes and assesses the potential chemical, electrical, and thermal hazards and risks of Na/S cells and batteries as well as the RD D performed, under way, or to address these hazards and risks. The report is based on a review of the literature and on discussions with experts at DOE, national laboratories and agencies, universities, and private industry. Subsequent volumes will address environmental, health, and safety issues involved in shipping cells and batteries, using batteries to propel electric vehicles, and recycling and disposing of spent batteries. The remainder of this volume is divided into two major sections on safety at the cell and battery levels. The section on Na/S cells describes major component and potential failure modes, design, life testing and failure testing, thermal cycling, and the safety status of Na/S cells. The section on batteries describes battery design, testing, and safety status. Additional EH S information on Na/S batteries is provided in the appendices.

Ohi, J.M.

1992-09-01T23:59:59.000Z

412

Manpower analysis in transportation safety. Final report  

DOE Green Energy (OSTI)

The project described provides a manpower review of national, state and local needs for safety skills, and projects future manning levels for transportation safety personnel in both the public and private sectors. Survey information revealed that there are currently approximately 121,000 persons employed directly in transportation safety occupations within the air carrier, highway and traffic safety, motor carrier, pipeline, rail carrier, and marine carrier transportation industry groups. The projected need for 1980 is over 145,000 of which over 80 percent will be in highway safety. An analysis of transportation tasks is included, and shows ten general categories about which the majority of safety activities are focused. A skills analysis shows a generally high level of educational background and several years of experience are required for most transportation safety jobs. An overall review of safety programs in the transportation industry is included, together with chapters on the individual transportation modes.

Bauer, C.S.; Bowden, H.M.; Colford, C.A.; DeFilipps, P.J.; Dennis, J.D.; Ehlert, A.K.; Popkin, H.A.; Schrader, G.F.; Smith, Q.N.

1977-05-01T23:59:59.000Z

413

HTGR safety research program  

SciTech Connect

An HTGR safety research program is being performed supporting and guided in priorities by the AIPA Probabilistic Risk Study. Analytical and experimental studies have been conducted in four general areas where modeling or data assumptions contribute to large uncertainties in the consequence assessments and thus, in the risk assessment for key core heat-up accident scenarios. Experimental data have been obtained on time-dependent release of fission products from the fuel particles, and plateout characteristics of condensible fission products in the primary circuit. Potential failure modes of primarily top head PCRV components as well as concrete degradation processes have been analyzed using a series of newly developed models and interlinked computer programs. Containment phenomena, including fission product deposition and potential flammability of liberated combustible gases have been studied analytically.

Barsell, A.W.; Olsen, B.E.; Silady, F.A.

1980-08-01T23:59:59.000Z

414

Complete Experiment Safety Documentation  

NLE Websites -- All DOE Office Websites (Extended Search)

Complete Experiment Safety Documentation Print Complete Experiment Safety Documentation Print User Safety Overview The steps for authorization of your experiment are described below. The ALS Experiment Coordinators are available to support you through this process. Please This e-mail address is being protected from spambots. You need JavaScript enabled to view it at any stage if you have questions or need more information. Prior to Your Arrival at the ALS 1. Complete or Update and Experiment Safety Sheet If you did not submit a General User Proposal, you must submit an ESS one month prior to arrival at the ALS. 2. Biological, Radioactive, Hazardous, and Electrical Materials, and Lasers If your experiment involves the use of any of the above materials-no matter how small the quantities are or how innocuous the sample may be-additional authorization may be required. Please submit your ESS early and clearly identify your materials. Our staff will assess the hazards and contact you about any necessary supplementary documentation.

415

Complete Experiment Safety Documentation  

NLE Websites -- All DOE Office Websites (Extended Search)

Complete Experiment Safety Documentation Print Complete Experiment Safety Documentation Print User Safety Overview The steps for authorization of your experiment are described below. The ALS Experiment Coordinators are available to support you through this process. Please This e-mail address is being protected from spambots. You need JavaScript enabled to view it at any stage if you have questions or need more information. Prior to Your Arrival at the ALS 1. Complete or Update and Experiment Safety Sheet If you did not submit a General User Proposal, you must submit an ESS one month prior to arrival at the ALS. 2. Biological, Radioactive, Hazardous, and Electrical Materials, and Lasers If your experiment involves the use of any of the above materials-no matter how small the quantities are or how innocuous the sample may be-additional authorization may be required. Please submit your ESS early and clearly identify your materials. Our staff will assess the hazards and contact you about any necessary supplementary documentation.

416

Complete Experiment Safety Documentation  

NLE Websites -- All DOE Office Websites (Extended Search)

Complete Experiment Safety Documentation Print Complete Experiment Safety Documentation Print User Safety Overview The steps for authorization of your experiment are described below. The ALS Experiment Coordinators are available to support you through this process. Please This e-mail address is being protected from spambots. You need JavaScript enabled to view it at any stage if you have questions or need more information. Prior to Your Arrival at the ALS 1. Complete or Update and Experiment Safety Sheet If you did not submit a General User Proposal, you must submit an ESS one month prior to arrival at the ALS. 2. Biological, Radioactive, Hazardous, and Electrical Materials, and Lasers If your experiment involves the use of any of the above materials-no matter how small the quantities are or how innocuous the sample may be-additional authorization may be required. Please submit your ESS early and clearly identify your materials. Our staff will assess the hazards and contact you about any necessary supplementary documentation.

417

Complete Experiment Safety Documentation  

NLE Websites -- All DOE Office Websites (Extended Search)

Complete Experiment Safety Documentation Print Complete Experiment Safety Documentation Print User Safety Overview The steps for authorization of your experiment are described below. The ALS Experiment Coordinators are available to support you through this process. Please This e-mail address is being protected from spambots. You need JavaScript enabled to view it at any stage if you have questions or need more information. Prior to Your Arrival at the ALS 1. Complete or Update and Experiment Safety Sheet If you did not submit a General User Proposal, you must submit an ESS one month prior to arrival at the ALS. 2. Biological, Radioactive, Hazardous, and Electrical Materials, and Lasers If your experiment involves the use of any of the above materials-no matter how small the quantities are or how innocuous the sample may be-additional authorization may be required. Please submit your ESS early and clearly identify your materials. Our staff will assess the hazards and contact you about any necessary supplementary documentation.

418

Environment/Health/Safety (EHS): Safety Minute  

NLE Websites -- All DOE Office Websites (Extended Search)

(PDF, PPT) Badge Return (LBNL) (PDF, PPT) Battery Management (PDF, PPT) Bicycle Safety (PDF, PPT) Construction-Related Mercury Spills (PDF, PPT) Construction Vehicle Safety...

419

Stair Safety  

NLE Websites -- All DOE Office Websites (Extended Search)

Stair Safety: Causes and Prevention of Stair Safety: Causes and Prevention of Residential Stair Injuries Cornell Department of Design & Cornell University Cooperative Environmental Analysis Martha Van Rensselaer Hall Extension 607-255-2144 Ithaca, NY 14853 In the United States during 1997 about 27,000 people were killed by unintentional home injuries. 1 Figure 1 illustrates the causes of some of the injuries that resulted in death. As you can see, falls account for the majority of incidents. Also in 1997, 6.8 million people suffered home accidents that resulted in disabling injuries. 1 While data on the number of injuries related to stairs and steps are not available for 1997, data from 1996 show that 984,000 people experienced injuries related to home stairs or steps during

420

Safety harness  

DOE Patents (OSTI)

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.

Gunter, Larry W. (615 Sand Pit Rd., Leesville, SC 29070)

1993-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "risk informed safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

Electrical Safety  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NOT MEASUREMENT NOT MEASUREMENT SENSITIVE DOE HANDBOOK ELECTRICAL SAFETY DOE-HDBK-1092-2013 July 2013 Superseding DOE-HDBK-1092-2004 December 2004 U.S. Department of Energy AREA SAFT Washington, D.C.20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-HDBK-1092-2013 Available on the Department of Energy Technical Standards Program Web site at http://www.hss.doe.gov/nuclearsafety/techstds/ ii DOE-HDBK-1092-2013 FOREWORD 1. This Department of Energy (DOE) Handbook is approved for use by the Office of Health, Safety and Security and is available to all DOE components and their contractors. 2. Specific comments (recommendations, additions, deletions, and any pertinent data) to enhance this document should be sent to: Patrick Tran

422

Safety harness  

DOE Patents (OSTI)

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. The 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.

Gunter, L.W.

1991-04-08T23:59:59.000Z

423

Risk Analysis & Security Rule Compliance Activities  

Science Conference Proceedings (OSTI)

... Risk Analysis & Security Rule Compliance Activities Marissa Gordon- Nguyen, JD, MPH Health Information Privacy Specialist ...

2010-05-13T23:59:59.000Z

424

Explosives Safety  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

212-2012 212-2012 June 2012 DOE STANDARD EXPLOSIVES SAFETY U.S. Department of Energy AREA SAFT Washington, DC 20585 MEASUREMENT SENSITIVE DOE-STD-1212-2012 i TABLE OF CONTENTS CHAPTER I. PURPOSE, SCOPE and APPLICABILITY, EXEMPTIONS, WAIVERS, ABBREVIATIONS, ACRONYMS, AND DEFINITIONS .......... 1 1.0. PURPOSE ............................................................................................................. 1 1.1. Scope and Applicability.............................................................................. 1 2.0. STANDARD ADMINISTRATION AND MANAGEMENT ...................................... 3 3.0. EXEMPTIONS ....................................................................................................... 4

425

Safety valve  

SciTech Connect

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.

Bergman, Ulf C. (Malmoe, SE)

1984-01-01T23:59:59.000Z

426

Office of Health & Safety  

NLE Websites -- All DOE Office Websites (Extended Search)

Safety Beryllium Chemical Safety Biological Safety Radiation Safety Rules 10 CFR 707 10 CFR 835 10 CFR 850 10 CFR 851 OHS Document Collection Site Medical Clinics REACTS EEOICPA...

427

Disaster City Safety  

Science Conference Proceedings (OSTI)

Safety. What Personal Protective Equipment (PPE) is needed to participate in this event? Personal ... On Site Safety Comes First. Be ...

2012-08-21T23:59:59.000Z

428

Engineered Fire Safety Group  

Science Conference Proceedings (OSTI)

Engineered Fire Safety Group. Welcome. ... Employment/Research Opportunities. Contact. Jason Averill, Leader. Engineered Fire Safety Group. ...

2012-06-05T23:59:59.000Z

429

Current Safety Performance Trends  

NLE Websites -- All DOE Office Websites (Extended Search)

Environmental Protection, Sustainability Support & Corporate Safety Analysis HS-20 Home Mission & Functions Office of Sustainability, Environment, Safety and Anaylsis (SESA) ...

430

Safety & Emergency Management  

NLE Websites -- All DOE Office Websites (Extended Search)

Coordination Management andor Coordination of APS Site WorkServices Safety & Emergency Management Database Maintenance Personnel Safety & Emergency Management Area...

431

Tutorial on nuclear thermal propulsion safety for Mars  

DOE Green Energy (OSTI)

Safety is the prime design requirement for nuclear thermal propulsion (NTP). It must be built in at the initiation of the design process. An understanding of safety concerns is fundamental to the development of nuclear rockets for manned missions to Mars and many other applications that will be enabled or greatly enhanced by the use of nuclear propulsion. To provide an understanding of the basic issues, a tutorial has been prepared. This tutorial covers a range of topics including safety requirements and approaches to meet these requirements, risk and safety analysis methodology, NERVA reliability and safety approach, and life cycle risk assessments.

Buden, D.

1992-01-01T23:59:59.000Z

432

Tutorial on nuclear thermal propulsion safety for Mars  

DOE Green Energy (OSTI)

Safety is the prime design requirement for nuclear thermal propulsion (NTP). It must be built in at the initiation of the design process. An understanding of safety concerns is fundamental to the development of nuclear rockets for manned missions to Mars and many other applications that will be enabled or greatly enhanced by the use of nuclear propulsion. To provide an understanding of the basic issues, a tutorial has been prepared. This tutorial covers a range of topics including safety requirements and approaches to meet these requirements, risk and safety analysis methodology, NERVA reliability and safety approach, and life cycle risk assessments.

Buden, D.

1992-08-01T23:59:59.000Z

433

Improved assessment of aviation hazards to ground facilities using a geographical information system  

SciTech Connect

A computer based system for performing probabilistic safety assessments (PSAs) of aircraft crashes to ground structures is under development. The system called ACRA (aircraft crash risk assessment) employs a GIS (geographical information system) for locating, mapping, and characterizing ground structures; and a multiparameter data base system that supports the analytical PRA (probabilistic risk assessment) model for determining PSAs for aircraft crashes. The Salt Lake City International Airport (SLC) is being employed as the base case for study and application of ACRA and evaluation of the projected safety assessment.

Sandquist, G.M.; Slaughter, D.M. [Utah Univ., Salt Lake City, UT (United States); Kimura, C.Y.

1996-06-03T23:59:59.000Z

434

Formalizing information security knowledge  

Science Conference Proceedings (OSTI)

Unified and formal knowledge models of the information security domain are fundamental requirements for supporting and enhancing existing risk management approaches. This paper describes a security ontology which provides an ontological structure for ... Keywords: information security, risk management, security ontology

Stefan Fenz; Andreas Ekelhart

2009-03-01T23:59:59.000Z

435

Electrical Safety - Monthly Analyses of Electrical Safety Occurrences  

NLE Websites -- All DOE Office Websites (Extended Search)

Office of Analysis Office of Analysis Operating Experience Committee Safety Alerts Safety Bulletins Annual Reports Special Operations Reports Safety Advisories Special Reports Causal Analysis Reviews Contact Us HSS Logo Electrical Safety Monthly Analyses of Electrical Safety Occurrences 2013 September 2013 Electrical Safety Occurrences August 2013 Electrical Safety Occurrences July 2013 Electrical Safety Occurrences June 2013 Electrical Safety Occurrences May 2013 Electrical Safety Occurrences April 2013 Electrical Safety Occurrences March Electrical Safety Occurrence February Electrical Safety Occurrence January Electrical Safety Occurrence 2012 December Electrical Safety Occurrence November Electrical Safety Occurrence October Electrical Safety Occurrence September Electrical Safety Occurrence

436

Safety | Data.gov  

NLE Websites -- All DOE Office Websites (Extended Search)

Safety Safety Safety Data/Tools Apps Challenges Resources Blogs Let's Talk Safety Welcome to the Safety Community The Safety Community is where data and insight are combined to facilitate a discussion around and awareness of our Nation's public safety activities. Whether you are interested in crime, roadway safety, or safety in the workplace, we have something for you. Check out the data, browse and use the apps, and be part of the discussion. Check out talks from the White House Safety Datapalooza Previous Pause Next One year of public safety data at Safety.Data.gov! Safety NHTSA releases SaferCar APIs and mobile app NHTSA releases SaferCar APIs and mobile app View More Todd Park, U.S. Chief Technology Officer at the Safety Datapalooza View More New APIs New APIs FRA launches new safety data dashboard and APIs.

437

Using Hydrogen Safety Best Practices and Learning from Safety Events  

DOE Green Energy (OSTI)

A best practice is a technique or methodology that has reliably led to a desired result. A wealth of experience regarding the safe use and handling of hydrogen exists as a result of an extensive history in a wide variety of industrial and aerospace settings. Hydrogen Safety Best Practices (www.h2bestpractices.org) captures this vast knowledge base and makes it publically available to those working with hydrogen and related systems, including those just starting to work with hydrogen. This online manual is organized under a number of hierarchical technical content categories. References, including publications and other online links, that deal with the safety aspects of hydrogen are compiled for easy access. This paper discusses the development of Hydrogen Safety Best Practices as a safety knowledge tool, the nature of its technical content, and the steps taken to enhance its value and usefulness. Specific safety event examples are provided to illustrate the link between technical content in the online best practices manual and a companion safety knowledge tool, Hydrogen Incident Reporting and Lessons Learned (www.h2incidents.org), which encourages the sharing of lessons learned and other safety event information.

Weiner, Steven C.; Fassbender, Linda L.; Quick, Kathleen A.

2011-02-28T23:59:59.000Z

438

HTGR Safety Research Program progress report, July--September 1975  

SciTech Connect

Information on HTGR safety research is presented concerning fission product release under normal and accident conditions, primary coolant impurities, structural investigation, safety instrumentation and control systems, reactor accident analysis, and phenomena modeling and systems analysis. 72 references. (DCC)

Kirk, W.L.

1975-01-01T23:59:59.000Z

439

The International Criticality Safety Benchmark Evaluation Project  

SciTech Connect

Most safety concerns associated with operations at nuclear facilities are very similar to the safety concerns associated with operations at non-nuclear facilities. The potential for a nuclear criticality accident is one concern that is unique to the nuclear industry. However, if managed properly, the risk of a criticality accident can be reduced to an acceptable level. In fact, the risk of a criticality accident can generally be reduced to a level that is much lower than the risk associated with non-nuclear activities that have similar consequences.

Briggs, Joseph Blair; Dean, V. F.; Presic, M.

2002-10-01T23:59:59.000Z

440

NSLS ESH&Q | Experimental Review and Laboratory Use Information  

NLE Websites -- All DOE Office Websites (Extended Search)

Experimental Review and Laboratory Use Information Lab Requirements Lab Stewards Experimental Safety Review PASS...

Note: This page contains sample records for the topic "risk informed safety" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


441

Architecture and design of third Qinshan nuclear power plant risk monitor  

SciTech Connect

Risk monitor is a real-time analysis tool to determine the point-in-time risk based on actual plant configuration, which is an important application of PSA (Probabilistic Safety Assessment). In this study the status and development trend of risk monitor were investigated and a risk monitor named TQRM (Third Qinshan nuclear power plant Risk Monitor) was developed. The B/S architecture and the two key computing methods pre-solved and resolving PSA model method adopted in TQRM were introduced. The functions and technical features were also presented. Now TQRM has been on-line for more than one year and used in the operation and maintenance of TQNPP. The experience demonstrates that TQRM's results are accurate and real-time, the architecture is stable, and it could be extended and maintained conveniently for any other Risk-Informed Application. (authors)

Wang, F.; Li, Y.; Wang, J.; Wang, J.; Hu, L. [Inst. of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031 (China); School of Nuclear Science and Technology, Univ. of Science and Technology of China, No.350 Shushanhu Road, Shushan District, Hefei, Anhui, 230031 (China)

2012-07-01T23:59:59.000Z

442

Derivation of a chemical-specific adjustment factor (CSAF) for use in the assessment of risk from chronic exposure to ethylene glycol: Application of international programme for chemical safety guidelines  

SciTech Connect

The International Programme for Chemical Safety (IPCS) has developed a set of guidelines ('the Guidance') for the establishment of Chemical-Specific Adjustment Factors (CSAFs) for in the assessment of toxicity risk to the human population as a result of chemical exposure. The development of case studies is encouraged in the Guidance document and comments on them have been encouraged by the IPCS. One provision in the Guidance is for the determination of CSAFs based on human data. We present a case study of the use of the Guidance for the determination of the CSAF for ethylene glycol (EG) primarily utilizing clinically obtained data. The most relevant endpoint for this analysis was deemed to be acute renal injury. These data were applied based on an assessment of the known pharmaco/toxico-kinetic properties of EG. Because of the lack of both bioaccumulation of EG and reports of chronic or progressive renal injury from EG, it was concluded that the most appropriate model of chronic exposure is one of repeated acute episodes. The most relevant exposure metric was determined to be plasma glycolate concentration. Based on a prospective human study of EG-poisoned patients, the NOAEL for glycolate was found to be 10.1 mM. This value is similar to that obtained from animal data. The application of the Guidelines to this data resulted in a CSAF of 10.24, corresponding to a daily EG dose of 43.7 mg/kg/day. In 2000, Health Canada (HC) produced an animal data-based analysis of the maximum tolerated dose of EG. The results of our analysis are compared with those of HC, and the strengths and weaknesses of these two data types related to EG are discussed.

Palmer, Robert B. [University of Colorado Health Sciences Center, Denver, CO 80262 (United States)]. E-mail: RPalmer@Toxicologyassoc.com; Brent, Jeffrey [University of Colorado Health Sciences Center, Denver, CO 80262 (United States)

2005-09-01T23:59:59.000Z

443

Laboratory Safety Certificate Course Completion Form  

E-Print Network (OSTI)

) Carcinogen Safety (2330) Centrifuge Safety (2335) Compressed Gas Safety (3835) Corrosive Safety (3055

Pawlowski, Wojtek

444

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

Science Conference Proceedings (OSTI)

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

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

1996-12-01T23:59:59.000Z

445

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

SciTech Connect

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

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

1996-12-01T23:59:59.000Z

446

Nuclear Safety: Software Quality Assurance  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Safety: Software Quality Assurance Nuclear Safety: Software Quality Assurance cd Welcome to the Department of Energy's Office of Health, Safety and Security (HSS) Software Quality Assurance (SQA) homepage. The purpose of this Web site is to promote continuous improvement and the sharing of knowledge of safety software quality assurance among interested parties across the DOE complex. It consolidates information and contains links to subject matter experts, procedures, training material, program descriptions, good practices, lessons learned and the Central Registry Toolbox Codes. The Portal also provides capabilities for member collaboration in product development and threaded discussions. Central Registry: The Central Registry provides a library of DOE "Toolbox" Codes covering site boundary accident dose consequences, fire accident source terms, leakpath factors, chemical release/dispersion and consequence, and radiological dispersion and consequence.

447

2007 Integrated Safety Management Workshop  

NLE Websites -- All DOE Office Websites (Extended Search)

ISM ISM Workshop 2007 a vision for Integrated Safety Management in the Department of Energy complex ISM Workshop 2007 ® Sample of how the graphic may be used on documents where the "Good to Great" verbiage is not includ "Good to Great" is a registered trademark of Jim Collins and is being used with permission. November 27-30, 2007 Hosted by Brookhaven National Laboratory "Good to Great" is a registered trademark of Jim Collins and is being used with permission. 2 Special Thanks Brookhaven National Laboratory Safety, Emergency and Traffic Information Safety, Health and Security Environment, Safety & Health Hotline: 631-344-8800 Occupational Medicine Clinic: 631-344-3670 Security Badging Office: 631-344-5149 Computer Security: 631-344-5522

448

Criticality safety basics, a study guide  

SciTech Connect

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.

V. L. Putman

1999-09-01T23:59:59.000Z

449

Criticality safety basics, a study guide  

SciTech Connect

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.

V. L. Putman

1999-09-01T23:59:59.000Z

450

Nuclear safety as applied to space power reactor systems  

SciTech Connect

Current space nuclear power reactor safety issues are discussed with respect to the unique characteristics of these reactors. An approach to achieving adequate safety and a perception of safety is outlined. This approach calls for a carefully conceived safety program which makes uses of lessons learned from previous terrestrial power reactor development programs. This approach includes use of risk analyses, passive safety design features, and analyses/experiments to understand and control off-design conditions. The point is made that some recent accidents concerning terrestrial power reactors do not imply that space power reactors cannot be operated safety.

Cummings, G.E.

1987-01-01T23:59:59.000Z

451

Safety Share Elevators, Escalators and Moving Walkways  

NLE Websites -- All DOE Office Websites (Extended Search)

3, 2010 3, 2010 Safety Share Elevators, Escalators and Moving Walkways Dick Donovan, of HS-70, informed the HSS VPP Committee about a recent safety incident he experienced while at an airport in Las Vegas. Dick tripped as he was getting off of the escalator. The incident made him consider the day-to-day hazards we take for granted. With this in mind, Dick made an effort to look around to find safety information about using elevators, escalators and moving walkways. Dick came across some useful safety information provided by the Otis Elevator Company. The web site below provides links to two good one-page reminders for safety on elevators, escalators, and moving walkways. http://www.otis.com/site/us/Pages/SafetyforAll.aspx Dick also found more interactive presentations on the same material, see website below. These

452

Informed Traders  

E-Print Network (OSTI)

A model is introduced in which there is a small agent who is more susceptible to the flow of information in the market than the general market participant, and who tries to implement strategies based on the additional information. In this model market participants have access to a stream of noisy information concerning the future return of an asset, whereas the informed trader has access to a further information source which is obscured by an additional noise that may be correlated with the market noise. The informed trader uses the extraneous information source to seek statistical arbitrage opportunities, while at the same time accommodating the additional risk. The amount of information available to the general market participant concerning the asset return is measured by the mutual information of the asset price and the associated cash flow. The worth of the additional information source is then measured in terms of the difference of mutual information between the general market participant and the informe...

Brody, Dorje C; Friedman, Robyn L; Hughston, Lane P

2008-01-01T23:59:59.000Z

453

Tag: Safety  

NLE Websites -- All DOE Office Websites (Extended Search)

8/all en Red light, green light 8/all en Red light, green light http://www.y12.doe.gov/employees-retirees/y-12-times/red-light-green-light

Even in the face of a furlough, we were thorough, professional and kept an eye on safety and security.
  • Nuclear fuel cycle risk assessment: survey and computer compilation of risk-related literature. [Once-through Cycle and Plutonium Recycle  

    Science Conference Proceedings (OSTI)

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

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

    1982-10-01T23:59:59.000Z

    455

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

    SciTech Connect

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

    Unwin, Stephen D.; Seiple, Timothy E.

    2009-05-28T23:59:59.000Z

    456

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

    Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

    February 1996 February 1996 CHANGE NOTICE NO. 2 Date November 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 Services, U.S. Department of Energy, (800) 473-4375, Fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Adminis tration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000.

    457

    Field Operation Power Switching Safety  

    Science Conference Proceedings (OSTI)

    Safety is of paramount consideration in all aspects of utility operations. Power switching operations, due to their variable nature, are susceptible to errors that can place utility workers at risk, lower system reliability or ability to respond to contingencies, increase customer outages, lower customer satisfactions, and reduce revenue. This report summarizes the results of analysis of utility data collected on human error in power switching operations and describes industry techniques used to reduce t...

    1996-10-11T23:59:59.000Z

    458

    Nuclear Criticality Safety Application Guide: Safety Analysis Report Update Program  

    SciTech Connect

    Martin Marietta Energy Systems, Inc. (MMES) is committed to performing and documenting safety analyses for facilities it manages for the Department of Energy (DOE). Safety analyses are performed to identify hazards and potential accidents; to analyze the adequacy of measures taken to eliminate, control, or mitigate hazards; and to evaluate potential accidents and determine associated risks. Safety Analysis Reports (SARs) are prepared to document the safety analysis to ensure facilities can be operated safely and in accordance with regulations. Many of the facilities requiring a SAR process fissionable material creating the potential for a nuclear criticality accident. MMES has long had a nuclear criticality safety program that provides the technical support to fissionable material operations to ensure the safe processing and storage of fissionable materials. The guiding philosophy of the program has always been the application of the double-contingency principle, which states: {open_quotes}process designs shall incorporate sufficient factors of safety to require at least two unlikely, independent, and concurrent changes in process conditions before a criticality accident is possible.{close_quotes} At Energy Systems analyses have generally been maintained to document that no single normal or abnormal operating conditions that could reasonably be expected to occur can cause a nuclear criticality accident. This application guide provides a summary description of the MMES Nuclear Criticality Safety Program and the MMES Criticality Accident Alarm System requirements for inclusion in facility SARs. The guide also suggests a way to incorporate the analyses conducted pursuant to the double-contingency principle into the SAR. The prime objective is to minimize duplicative effort between the NCSA process and the SAR process and yet adequately describe the methodology utilized to prevent a nuclear criticality accident.

    1994-02-01T23:59:59.000Z

    459

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

    DOE Green Energy (OSTI)

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

    Not Available

    1987-05-01T23:59:59.000Z

    460

    APS Experiment Safety Review Board  

    NLE Websites -- All DOE Office Websites (Extended Search)

    Meeting Minutes * Laser Safety Notifications Charter for the APS Laser Safety Committee 1. Purpose The Laser Safety Committee advises APS Management on laser safety matters,...

    Note: This page contains sample records for the topic "risk informed safety" from the National Library of EnergyBeta (NLEBeta).
    While these samples are representative of the content of NLEBeta,
    they are not comprehensive nor are they the most current set.
    We encourage you to perform a real-time search of NLEBeta
    to obtain the most current and comprehensive results.


    461

    Using Information Technology to Reduce a Health Risk| Effect of a Mercury Calculator on Consumer Fish Choices and Test of a Model for Technology Acceptance by Fish Consumers.  

    E-Print Network (OSTI)

    ?? Research indicates consumers lack adequate information about the mercury content of fish to make informed choices about eating fish. Information technology can be used… (more)

    Wallace, Sharon D.

    2013-01-01T23:59:59.000Z

    462

    Safety for Users  

    NLE Websites -- All DOE Office Websites (Extended Search)

    Safety for Users Safety for Users Print Tuesday, 01 September 2009 08:01 Safety at the ALS The mission of the ALS is "Support users in doing outstanding science in a safe...

    463

    DUF6 Storage Safety  

    NLE Websites -- All DOE Office Websites (Extended Search)

    Storage Safety Depleted UF6 Storage line line How DUF6 is Stored Where DUF6 is Stored DUF6 Storage Safety Cylinder Leakage Depleted UF6 Storage Safety Continued cylinder storage is...

    464

    H. UNREVIEWED SAFETY QUESTIONS  

    Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

    all safety basis documents submitted to DOE and (2) preparation of a safety evaluation report concerning the safety basis for a facility. 2. DOE will maintain a public list on the...

    465

    Acceptable NSLS Safety Documentation  

    NLE Websites -- All DOE Office Websites (Extended Search)

    Acceptable NSLS Safety Documentation Print NSLS users who have completed NSLS Safety Module must present a copy of one of the following documents to receive ALS 1001: Safety at the...

    466

    Environment/Health/Safety (EHS): Laser Safety  

    NLE Websites -- All DOE Office Websites (Extended Search)

    Laser Safety Home Whom to Call Analysis of Laser Safety Occurrences: 2005-2011 Laser Bio-effects Laser Classification Laser Disposal Guide Laser Forms Laser Newsletter Laser Lab...

    467

    Y-12 PLANT NUCLEAR SAFETY HANDBOOK  

    SciTech Connect

    Information needed to solve nuclear safety problems is condensed into a reference book for use by persons familiar with the field. Included are a glossary of terms; useful tables; nuclear constants; criticality calculations; basic nuclear safety limits; solution geometries and critical values; metal critical values; criticality values for intermediate, heterogeneous, and interacting systems; miscellaneous and related information; and report number, author, and subject indexes. (C.H.)

    Wachter, J.W. ed.; Bailey, M.L.; Cagle, T.J.; Mee, W.T.; Pletz, R.H.; Welfare, F.G.; Youngblood, B.J. comps

    1963-03-27T23:59:59.000Z

    468

    Policy Statement 2, Transmittal of Trip Reports and Other Safety...  

    NLE Websites -- All DOE Office Websites (Extended Search)

    2 Date: December 31, 1992 Subject Board policy on transmittal of trip reports and other safety information to the Secretary of Energy Summary This policy statement establishes...

    469