National Library of Energy BETA

Sample records for design safety environment

  1. Environment/Health/Safety Concerns

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

    EHS Emergencies Report AccidentIncident Stop Work Policy Environment, Health & Safety Concerns hardhat Environment Health Safety Concerns construction workers If you have a...

  2. ORISE: Contact Environment, Safety & Health

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

    Star Status Environment Work Smart Standards Oak Ridge Institute for Science Education Contact Us Use the form below to contact Environment, Safety & Health. Other contact...

  3. Conceptual Safety Design RM

    Broader source: Energy.gov [DOE]

    The Conceptual Safety Design (CSD) Review Module (RM) is a tool that assists DOE federal project review teams in evaluating the adequacy of the Conceptual Safety Design work, processes and...

  4. Safety & Environment | Jefferson Lab

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

    Safety & Environment At Jefferson Lab, the health and safety of employees, users, contractors, visitors and the general public are our highest priorities. In concert with federal and state regulations, and based on years of experience and benchmarking, the lab has established rules and procedures that protect health and safety. It is lab policy to comply with all environmental regulations and laws. It is also the lab's policy to efficiently use energy resources, and to comply with all energy

  5. Environment, Safety and Health Reporting

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

    2012-01-01

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

  6. Environment, Safety, and Health Reporting

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

    2003-08-19

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

  7. Environment, Safety and Health Reporting

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

    2011-06-27

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

  8. Environment, Safety and Health Reporting

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

    2011-06-27

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

  9. Environment, Health, and Safety | NREL

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

    Environment, Health, Safety & Security Environmental Protection Agency Safer Choice Partner of the Year Awards Environmental Protection Agency Safer Choice Partner of the Year Awards DOE was recognized as part of the Federal Sustainable Acquisitions and Materials Management Practices (SAMM) Working Group under the Program Supporter category. Read more Climate Change Adaptation Training at HAMMER June 21-22, 2016 Climate Change Adaptation Training at HAMMER June 21-22, 2016 Executive Order

  10. Environment, Safety, and Health Reporting Manual

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

    1996-11-07

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

  11. Environment Safety and Health Reporting Manual

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

    1995-09-30

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

  12. Environment/Health/Safety (EHS)

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

    Safety Advisory Committee SAC Home Charter Sub-Committees Membership Minutes Annual Report ESH Peer Review Questions Welcome to the Safety Advisory Committee Web Site The Safety...

  13. Preliminary Safety Design RM | Department of Energy

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

    Safety Design RM Preliminary Safety Design RM The Preliminary Safety Design (PSD) Review Module (RM) is a tool that assists DOE federal project review teams in evaluating the ...

  14. Safety Design Strategy RM | Department of Energy

    Energy Savers [EERE]

    Safety Design Strategy RM Safety Design Strategy RM The SDS Review Module (RM) is a tool that assists DOE federal project review teams in evaluating the adequacy of the conceptual safety design strategy documentation package (Conceptual Safety Design Report) prior to CD-1 approval and the adequacy of the preliminary safety design strategy documentation packaged (Preliminary Safety Design Report) prior to CD- 2 approval. PDF icon Safety Design Strategy RM More Documents & Publications Safety

  15. Design of Roadside Safety Features

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

    Analysis and Design of the Roadside Safety Features for Safety Performance Texas Transportation Institute (TTI) researchers are investigating the performance of a crash wall design to determine its effectiveness in reducing the damage to mechanically supported earth (MSE) wall panels during a vehicular impact. The simulations are based on Test Level 4 impact conditions of the new AASHTO Manual for Assessing Safety Hardware (MASH). This involves a 10,000-kg single unit truck (SUT) impacting at 90

  16. Independent Oversight Inspection of Environment, Safety, and...

    Office of Environmental Management (EM)

    Inspection of Environment, Safety, and Health Programs at the Savannah River Operations Office and Savannah River Site, January 2010 Independent Oversight Inspection of ...

  17. Environment, Safety and Health (ESH) Goals

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

    2004-08-02

    The purpose of this Policy is to establish Environment, Safety and Health (ES&H) goals for Department of Energy (DOE) personnel and its contractors. These goals are designed to establish Departmental ES&H expectations for: 1) DOE and contractor personnel ES&H behaviors and attitudes in the conduct of their daily work activities, and 2) operational performance regarding worker injuries and illnesses, regulatory enforcement actions, and environmental releases. Cancels DOE P 450.1, DOE P 450.6. Canceled by DOE O 450.4A

  18. Environment/Health/Safety (EHS)

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

    Safety Minute Brief Introduction At Home Authorizations Laboratory Area Office Area Shop Area Reporting Ergonomics (general) Training Supervisor Responsibilities Site- Wide...

  19. Environment/Health/Safety (EHS)

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

    Training Whom to Call Databases Ergonomics References EHS Quick Links 1 Minute 4 Safety Accident Narratives Accident Statistics Accident Statistics Archive Activity Manager AHD...

  20. Integration of Safety into the Design Process

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

    2007-06-27

    The Standard provides guidance on a process of integration of Safety-in-Design intended to implement the applicable ISM core functions—define the work, analyze the hazards, establish the controls—necessary to provide protection of the public, workers, and the environment from harmful effects of radiation and other such toxic and hazardous aspects attendant to the work.

  1. Line Environment, Safety and Health Oversight

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

    1997-06-26

    Sets forth the Department's expectations line management environment, safety and health (ES&H) oversight and for the use of contractor self-assessment programs as the cornerstone for this oversight. Canceled by DOE O 226.1.

  2. Nuclear Reactor Safety Design Criteria

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

    1993-01-19

    The order establishes nuclear safety criteria applicable to the design, fabrication, construction, testing, and performance requirements of nuclear reactor facilities and safety class structures, systems, and components (SSCs) within these facilities. Cancels paragraphs 8a and 8b of DOE 5480.6. Cancels DOE O 5480.6 in part. Supersedes DOE 5480.1, dated 1-19-93. Certified 11-18-10.

  3. PNNL: About PNNL: Environment, Health and Safety

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

    Environment, Health and Safety The success of Pacific Northwest National Laboratory (PNNL) is, in part, dependent upon operational excellence. At PNNL, "operational excellence" means harnessing the energy and passion of every staff member to accomplish our mission: delivering outstanding research results in science and technology while cost effectively managing the Laboratory with the highest standards of good citizenship, safety, health, and environmental stewardship. The Environment,

  4. NREL: Environment, Health, and Safety - Construction Subcontractors

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

    Documents Environment, Health, and Safety Printable Version Construction Subcontractors Documents The purpose of this page is to ensure NREL Environment, Health and Safety (EH&S) requirements are understood by construction subcontractors and incorporated into their planning, procurement, and execution of construction work activities at NREL. It is important that all construction subcontractors and their lower-tiers subcontractors familiarize themselves with these requirements before

  5. Environment, Safety, and Health Reporting Manual

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

    2000-01-28

    This Manual provides detailed requirements to supplement DOE O 231.1, Environment, Safety and Health Reporting, which establishes management objectives and requirements for reporting environment, safety and health information. (Paragraphs 2a, 2a(1), 2a(2), 2b, 2b(1), 2b(2), and 2i(3)(a) through 2i(3)(d) of Chapter II, and Appendix A canceled by DOE N 231.1; Chapter IV canceled by DOE O 470.2A.)

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

    SciTech Connect (OSTI)

    Rosenthal, M.A.

    1988-04-01

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

  7. Office of Environment, Safety and Health Assessments Protocol...

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

    Office of Environment, Safety and Health Assessments Protocol for Required ... the Office of Environment, Safety and Health Assessments required reading program. ...

  8. Office of Environment, Safety and Health Assessments Protocol...

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

    Office of Environment, Safety and Health Assessments Protocol for the Development and ... (CRADs) used by the Office of Environment, Safety and Health Assessments (EA-30). ...

  9. Office of Environment, Safety and Health Assessments Protocol...

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

    Office of Environment, Safety and Health Assessments Protocol for Site Leads, April 2015 (Revision 1) - PROTOCOL - EA-31-01 April 2015 Office of Environment, Safety and Health ...

  10. Assistant Secretary for Environment, Safety and Health Endorses...

    Office of Environmental Management (EM)

    Assistant Secretary for Environment, Safety and Health Endorses VPP and VPPPA Annual Conference Assistant Secretary for Environment, Safety and Health Endorses VPP and VPPPA Annual...

  11. DOE Standard Integration Of Environment,Safety, and Health Into...

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

    Standard Integration Of Environment,Safety, and Health Into Facility Disposition Activities DOE Standard Integration Of Environment,Safety, and Health Into Facility Disposition ...

  12. Track 5: Integration of Safety Into Design

    Broader source: Energy.gov [DOE]

    ISM Workshop Presentations Knoxville Convention Center, Knoxville, TN August 2009 Track 5: Integration of Safety Into Design

  13. Jefferson Lab Environment, Safety, Health and Quality Division

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

    ESH&Q Privacy and Security Notice Skip over navigation Search the JLab Site Environment, Safety, Health and Quality Please upgrade your browser. This site's design is only visible in a graphical browser that supports web standards, but its content is accessible to any browser. Concerns? ESH&Q ESH&Q Home Contacts ES&H Manual print version Manual Table of Contents 1000 - Policy 2000 - Organization and Responsibilities 3000 - Planning for Safe Operations 3110 Facility Design and

  14. Environment, Safety, and Health Special Review, Department of...

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

    Centers Approach to Nanoscale Environment, Safety, and Health, and other applicable requirements including 10 C.F.R. Part 851 and DOE's integrated safety management policy. ...

  15. Environment, Safety, Health, and Assurance | The Ames Laboratory

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

    Environment, Safety, Health, and Assurance ESH&A is responsible for health and safety issues at Ames Laboratory and addresses those issues through training, integrated safety management, and oversight in compliance with appropriate federal and state safety requirements. Frequently Used Links: Readiness Review Chemical Inventory Waste Pick-up Guide Former Worker and EEOICP Beryllium Nanomaterial Safety Emergency Preparedness

  16. RNEDE: Resilient Network Design Environment

    SciTech Connect (OSTI)

    Venkat Venkatasubramanian, Tanu Malik, Arun Giridh; Craig Rieger; Keith Daum; Miles McQueen

    2010-08-01

    Modern living is more and more dependent on the intricate web of critical infrastructure systems. The failure or damage of such systems can cause huge disruptions. Traditional design of this web of critical infrastructure systems was based on the principles of functionality and reliability. However, it is increasingly being realized that such design objectives are not sufficient. Threats, disruptions and faults often compromise the network, taking away the benefits of an efficient and reliable design. Thus, traditional network design parameters must be combined with self-healing mechanisms to obtain a resilient design of the network. In this paper, we present RNEDEa resilient network design environment that that not only optimizes the network for performance but tolerates fluctuations in its structure that result from external threats and disruptions. The environment evaluates a set of remedial actions to bring a compromised network to an optimal level of functionality. The environment includes a visualizer that enables the network administrator to be aware of the current state of the network and the suggested remedial actions at all times.

  17. Environment, Safety and Health Assessments | Department of Energy

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

    Environment, Safety and Health Assessments Environment, Safety and Health Assessments The Department of Energy's Office of Environment, Safety and Health Assessments, within the Office of Enterprise Assessments, is responsible for conducting assessments to provide information on programs and performance in protecting our workers, the public, and environment from hazards present at Department sites and operations. This information provides assurance to our stakeholders and identifies areas for

  18. Environment, Safety, and Health Reporting Notice

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

    2002-01-15

    To set forth the requirements and responsibilities for Department of Energy (DOE) elements, including the National Nuclear Security Administration (NNSA), for preparation of annual summary reports to the Secretary of Energy on the results of environment, safety, and health (ES&H) assessments conducted in the previous year. To implement the revised requirements of Title 29 Code of Federal Regulations (CFR) Part 1904, "Recording and Reporting Occupational Injuries and Illnesses," within DOE, including NNSA. Cancels Paragraphs 2a, 2a(1), 2a(2), 2b, 2b(1), 2b(2), and 2i(3)(a) through 2i(3)(d) of Chapter II and Appendix A of DOE M 231.1-1. DOE N 231.2 extends this Notice until 1-15-2004. Cancels: DOE M 231.1-1. in part.

  19. Health, Safety & Environment System Description and Worker Safety...

    National Nuclear Security Administration (NNSA)

    ... facilities by staying below hazardous chemical usestorage threshold amounts as defined ... superior safety performance. Chemical Management Committee: This committee ...

  20. USW Health Safety and Environment Conference - HSS Workshop | Department of

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

    Energy USW Health Safety and Environment Conference - HSS Workshop USW Health Safety and Environment Conference - HSS Workshop Workshop Date: March 7, 2012 Documents Available for Download PDF icon Workshop Agenda PDF icon Presentation: Regulatory Enforcement PDF icon Presentation: Integrated Approach to Health, Safety and Security PDF icon Presentation: Improving Safety Culture at DOE Sites PDF icon Presentation: 851 Rule Implementation Improvement Efforts More Documents & Publications

  1. LCLS CDR Chapter 13 - Environment Safety and Health and QA

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

    3 3 Environment, Safety and Health and Quality Assurance It is SLAC's policy and objective to integrate safety and environmental protection into its management and work practices at all levels, so that its mission is accomplished while protecting the worker, the public, and the environment. To achieve this objective, SLAC has developed and implemented an Integrated Safety Management System plan (ISMS), required by DOE P450.4, Safety Management System Policy, which encourages and supports the use

  2. Environment, Safety and Health | Y-12 National Security Complex

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

    About / Environment, Safety and ... Environment, Safety and Health In performing Y-12's mission and in modernizing the Y-12 Complex, we are fully committed to ensuring the safety and health of our workers, the public, and the environment. Our commitment is described in our ES&H Policy Statement, which explains how Y-12's policy is integrated into our business processes and systems, day-to-day operations, modernization initiatives, and planning activities. Activities performed by Consolidated

  3. Office of Environment, Safety and Health Assessments Protocol...

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

    PDF icon Office of Environment, Safety and Health Assessments Protocol for Oversight Activities, December 2015 More Documents & Publications Enterprise Assessments Review of the ...

  4. Volume II, Environment, Safety, and Health Special Review of...

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

    Volume II, Environment, Safety, and Health Special Review of Work Practices for Nanoscale Material Activities at Department of Energy Laboratories, August 2008 Volume II, ...

  5. Environment, Safety, Health, & Security | Princeton Plasma Physics...

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

    supporting Lab-wide safety forums or safety-related events; reviewing information on lessons learned for possible application to the Lab and aiding in determining follow-up...

  6. Assessment of Offshore Wind System Design, Safety, and Operation...

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

    Assessment of Offshore Wind System Design, Safety, and Operation Standards Assessment of Offshore Wind System Design, Safety, and Operation Standards The U.S. Department of ...

  7. Office of Environment, Safety and Health Assessments | Department of Energy

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

    Assessments Office of Environment, Safety and Health Assessments MISSION The Office of Environment, Safety and Health Assessments conducts assessments to provide critical feedback and objective information on programs and performance in protecting our workers, the public and environment from the multiple hazards present at Department sites and operations.This information provides assurance to our stakeholders and identifies areas for improvement to our leadership to support the safe performance

  8. Radiation Safety - Protecting the Public and the Environment | Department

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

    of Energy Radiation Safety - Protecting the Public and the Environment Radiation Safety - Protecting the Public and the Environment The Department of Energy has a stringent program for protecting its workers, the public, and the environment from radiation. This web area has links to tools and aids for the radiation protection of the public. Some links apply to the clearance (i.e., radiological release) of property. "Clearance" permits real property (land and buildings) to be

  9. Environment/Health/Safety Division: News

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

    A-Z News Site Map Organization Chart EHS Internal Groups JHA Training Whom to Call Databases Ergonomics References EHS Quick Links 1 Minute 4 Safety Accident Narratives Accident...

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

    SciTech Connect (OSTI)

    Voelz, G.L.

    1985-05-01

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

  11. Environment, Safety, and Health Program for Department of Energy Operations

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

    1986-09-23

    To establish the Environment, Safety, and Health (ES&H) Program for Department of Energy (DOE) operations. Cancels DOE O 5480.1A. Canceled by DOE N 251.4.

  12. Morris named NPO assistant manager for Environment, Safety Health and

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

    Quality | Y-12 National Security Complex Morris named NPO assistant ... Morris named NPO assistant manager for Environment, Safety Health and Quality Posted: April 16, 2015 - 11:02am Susan Morris Susan Morris has been named Assistant Manager for Environment, Safety, Health and Quality for the National Nuclear Security Administration Production Office. Morris is responsible for oversight of contractor programs for health physics and radiological protection, industrial hygiene and occupational

  13. Los Alamos National Laboratory (LANL) Safety Conscious Work Environment

    Energy Savers [EERE]

    (SCWE) Self-Assessment | Department of Energy National Laboratory (LANL) Safety Conscious Work Environment (SCWE) Self-Assessment Los Alamos National Laboratory (LANL) Safety Conscious Work Environment (SCWE) Self-Assessment The documents included in this listing are additional references not included in the Phase 2 Radiological Release at the Waste Isolation Pilot Plant, Attachment F: Bibliography and References report. The documents were examined and used to develop the final report. PDF

  14. Independent Oversight Inspection of Environment, Safety, and Health

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

    Programs at the Savannah River Operations Office and Savannah River Site, January 2010 | Department of Energy Inspection of Environment, Safety, and Health Programs at the Savannah River Operations Office and Savannah River Site, January 2010 Independent Oversight Inspection of Environment, Safety, and Health Programs at the Savannah River Operations Office and Savannah River Site, January 2010 January 2010 The U.S. Department of Energy (DOE) Office of Independent Oversight, within the

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

    Energy Savers [EERE]

    Security | Department of Energy Environment, Health, Safety & Security FTCP Site Specific Information - Office of Environment, Health, Safety & Security FTCP Agent Organization Name Phone E-Mail EHSS HQ Pat Worthington Mark Blackburn 301-903-5926 301-903-8396 pat.worthington@hq.doe.gov mark.blackburn@hq.doe.gov Annual Workforce Analysis and Staffing Plan Reports Calendar Year 2015 Calendar Year 2014 Calendar Year 2013 Calendar Year 2012 Calendar Year 2011 Calendar Year 2010 TQP

  16. Office of Nuclear Safety Basis and Facility Design

    Broader source: Energy.gov [DOE]

    The Office of Nuclear Safety Basis & Facility Design establishes safety basis and facility design requirements and expectations related to analysis and design of nuclear facilities to ensure protection of workers and the public from the hazards associated with nuclear operations.

  17. Safety Design Strategy Standard Review Plan (SRP)

    Broader source: Energy.gov [DOE]

    This SRP on Safety Design Strategy (SDS) provides the starting point for a set of corporate Performance Objectives and Criteria contain in Appendix A. Review teams are expected to build on these and develop additional project-specific Lines of Inquiry, as needed. The criteria and the review process are intended to be used on an ongoing basis during the appropriate CD phase to ensure that issues are identified and resolved.

  18. Nuclear Safety Design Principles & the Concept of Independence: Insights from Nuclear Weapon Safety for Other High-Consequence Applications.

    SciTech Connect (OSTI)

    Brewer, Jeffrey D.

    2014-05-01

    Insights developed within the U.S. nuclear weapon system safety community may benefit system safety design, assessment, and management activities in other high consequence domains. The approach of assured nuclear weapon safety has been developed that uses the Nuclear Safety Design Principles (NSDPs) of incompatibility, isolation, and inoperability to design safety features, organized into subsystems such that each subsystem contributes to safe system responses in independent and predictable ways given a wide range of environmental contexts. The central aim of the approach is to provide a robust technical basis for asserting that a system can meet quantitative safety requirements in the widest context of possible adverse or accident environments, while using the most concise arrangement of safety design features and the fewest number of specific adverse or accident environment assumptions. Rigor in understanding and applying the concept of independence is crucial for the success of the approach. This paper provides a basic description of the assured nuclear weapon safety approach, in a manner that illustrates potential application to other domains. There is also a strong emphasis on describing the process for developing a defensible technical basis for the independence assertions between integrated safety subsystems.

  19. Health, Safety & Environment System Description and Worker Safety & Health Program

    National Nuclear Security Administration (NNSA)

    FY2015 HEALTH, SAFETY AND ENVIRONMENT MANAGEMENT SYSTEM DESCRIPTION and WORKER SAFETY & HEALTH PROGRAM Honeywell Federal Manufacturing & Technologies HS&E Management System Description 1 Honeywell Approval: KCFO Approval: Original Signed by Don Fitzpatrick 8/27/14 Original Signed by Sherry Kinsey-Cannon 8/27/14 Donald J. Fitzpatrick, Director Date Sherry Kinsey-Cannon, Date HSE&F Acting Assistant Manager Office of Operations KCFO Worker Safety & Health Program 2 Honeywell

  20. UPF: Safety in Design | Y-12 National Security Complex

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

    UPF: Safety in Design UPF: Safety in Design Posted: February 11, 2013 - 3:05pm | Y-12 Report | Volume 9, Issue 2 | 2013 Safety is a fundamental requirement in the design of the Uranium Processing Facility. Designing controls for uranium and other hazardous materials can be daunting. That's why the Uranium Processing Facility has a Safety-in-Design Integration Team. Lynn Harkey, who leads SDIT, admits it is a challenge to balance competing requirements, but the payoffs are significant.

  1. Events Beyond Design Safety Basis Analysis

    Broader source: Energy.gov [DOE]

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

  2. Integration of Environment, Safety, and Health into Facility Disposition Activities

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

    1998-05-01

    Volume One of this Standard has been revised to provide a Department of Energy (DOE) approved methodology for preparing a Documented Safety Analysis (DSA) for decommissioning of nuclear facilities, as well as environmental restoration activities that involve work not done within a permanent structure. Methodologies provided in this Standard are intended to be compliant with Title 10 of the Code of Federal Regulations (CFR) Part 830, Nuclear Safety Management, Subpart B, Safety Basis Requirements. Volume Two contains the appendices that provide additional environment, safety and health (ES&H) information to complement Volume 1 of this Standard. Volume 2 of the Standard is much broader in scope than Volume 1 and satisfies several purposes. Integrated safety management expectations are provided in accordance with facility disposition requirements contained in DOE O 430.1B, Real Property Asset Management.

  3. PETRO-SAFE '91 conference papers: Volume 3 (Drilling and production environment and safety), Volume 4 (Transportation and storage environment and safety) and Volume 5 (Processing and refining environment and safety)

    SciTech Connect (OSTI)

    Not Available

    1991-01-01

    This conference provided a forum for the oil, gas, and petrochemical industries to discuss state of the art knowledge in those fields. The following topics were addressed: drilling and production environment and safety; transportation and storage environment and safety; and processing and refining environment and safety. Separate papers are processed for inclusion in the appropriate data bases.

  4. Review and Approval of Nuclear Facility Safety Basis and Safety Design Basis Documents

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

    2014-12-19

    This Standard describes a framework and the criteria to be used for approval of (1) safety basis documents, as required by 10 Code of Federal Regulation (C.F.R.) 830, Nuclear Safety Management, and (2) safety design basis documents, as required by Department of Energy (DOE) Standard (STD)-1189-2008, Integration of Safety into the Design Process.

  5. CRAD, Integrated Safety Basis and Engineering Design Review ...

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

    Integrated Safety Basis and Engineering Design Review - August 20, 2014 (EA CRAD 31-4, Rev. 0) CRAD, Integrated Safety Basis and Engineering Design Review - August 20, 2014 (EA...

  6. CRAD, Engineering Design and Safety Basis- December 22, 2009

    Broader source: Energy.gov [DOE]

    Engineering Design and Safety Basis Inspection Criteria, Inspection Activities, and Lines of Inquiry (HSS CRAD 64-19, Rev. 0)

  7. Integration Of Safety Into The Design Process

    Energy Savers [EERE]

    STD-1189-2008 March 2008 DOE STANDARD INTEGRATION OF SAFETY INTO THE DESIGN PROCESS U.S. Department of Energy AREA SAFT Washington, DC 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1189-2008 Page ii This document is available on the Department of Energy Technical Standards Program Web Page at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-STD-1189-2008 Page iii PREFACE The U.S. Department of Energy (DOE) has approved this Standard for use

  8. Identifying, Implementing and Complying with Environment, Safety and Health Requirements

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

    1996-05-15

    This Policy sets forth the framework for identifying, implementing and complying with environment, safety and health (ES&H) requirements so that work is performed in the DOE complex in a manner that ensures adequate protection of workers, the public and the environment. Ownership of this policy is shared between GC and HS. Cancels DOE P 450.2. Canceled by DOE P 450.4A.

  9. Office of Environment, Safety and Health Assessments Protocol for Oversight Activities, December 2015

    Broader source: Energy.gov [DOE]

    Office of Environment, Safety and Health Assessments Protocol for Oversight Activities, December 2015

  10. Environment, Safety, and Health Program for Department of Energy Operations

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

    1986-09-23

    This Page Change transmits revised pages of DOE O 5480.1B to renew the authority fo the Assistant Secretary for Environment, Safety and Health to curtail or suspend operations at Department of Energy facilities. Chg 1 dated 5-10-93. Canceled by DOE N 251.4.

  11. Jefferson Lab Environment, Safety, Health and Quality Division

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

    ESHQ Please upgrade your browser. This site's design is only visible in a graphical browser that supports web standards, but its content is accessible to any browser. Concerns? ESH&Q ESH&Q Home Contacts ES&H Manual JLab Work Planning Tools print version GROUPS ESH&Q Committees Emergency Management Environmental Occupational Medicine Quality Assurance & Continuous Improvement Radiation Control Health & Safety Programs Integrated Safety Management Site Associate Director's

  12. Design of Safety Significant Safety Instrumented Systems Used...

    Office of Environmental Management (EM)

    (SIS) that include both analog and digital control systems are widely used in many industries, including in commercial nuclear power plants, for safety-related applications. ...

  13. Nonreactor Nuclear Safety Design Criteria and Explosive Safety Criteria Guide for Use with DOE O 420.1, Facility Safety

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

    2000-03-28

    This Guide provides guidance on the application of requirements for nonreactor nuclear facilities and explosives facilities of Department of Energy (DOE) O 420.1, Facility Safety, Section 4.1, Nuclear and Explosives Safety Design Criteria. No cancellation.

  14. Environment/Health/Safety (EHS): Personal Protective Equipment...

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

    EHS Occupational Safety Safety Group Home Electrical Safety Ergonomics ISM Occupational Safety Group Organization Personal Protective Equipment (PPE) Injury Review & Analysis...

  15. March 7, 2012, USW Health Safety and Environment Conference Presentati...

    Office of Environmental Management (EM)

    DOE Worker Safety and Health Regulatory Enforcement Kevin Dressman Director, Office of Worker Safety and Health Enforcement (HS-41) Office of Health, Safety and Security U.S....

  16. Mr. Anthony D. Pantaleoni Vice President Environment, Health & Safety

    Office of Legacy Management (LM)

    7=cr5rnP 7694 i+lJ Washington, DC 20585 Mr. Anthony D. Pantaleoni Vice President Environment, Health & Safety Crane Company 757 Third Avenue New York, New York 10017 Dear Mr. Pantaleoni: This letter is a followup to the radiological survey performed by the U.S. Department of Energy (DOE) in August at the former Chapman Valve Manufacturing Company in Indian Orchard, Massachusetts. The facility is presently owned by the Crane Company. The radiological survey identified areas of elevated

  17. Integration of Safety into the Design Process - DOE Directives...

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

    public, workers, and the environment from harmful effects of radiation and other such toxic and hazardous aspects attendant to the work. DOE-STD-1189-2008, Integration of Safety...

  18. Environment, Safety and Health Progress Assessment of the Hanford Site

    SciTech Connect (OSTI)

    Not Available

    1992-05-01

    This report documents the result of the US Department of Energy (DOE) Environment, Safety and Health (ES&H) Progress Assessment of the Hanford Site, in Richland, Washington. The assessment, which was conducted from May 11 through May 22, 1992, included a selective-review of the ES&H management systems and programs of the responsible DOE Headquarters Program Offices the DOE Richland Field Office, and the site contractors. The ES&H Progress Assessments are part of the Secretary of Energy`s continuing effort to institutionalize line management accountability and the self-assessment process throughout DOE and its contractor organizations. The purpose of the Hanford Site ES&H Progress Assessment is to provide the Secretary with an independent assessment of the adequacy and effectiveness of the DOE and contractor management structures, resources, and systems to address ES&H problems and requirements. They are not intended to be comprehensive compliance assessments of ES&H activities. The point of reference for assessing programs at the Hanford Site was, for the most part, the Tiger Team Assessment of the Hanford Site, which was conducted from May 21 through July 18, 1990. A summary of issues and progress in the areas of environment, safety and health, and management is included.

  19. Safety Design Strategy for the Advanced Test Reactor Emergency Firewater Injection System Replacement Project

    SciTech Connect (OSTI)

    Noel Duckwitz

    2011-06-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3B, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3B and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Advanced Test Reactor Reliability Sustainment Project. While this project does not introduce new hazards to the ATR, it has the potential for significant impacts to safety-related systems, structures, and components that are credited in the ATR safety basis and are being replaced. Thus the project has been determined to meet the definition of a major modification and is being managed accordingly.

  20. Safety Design Strategy for the Advanced Test Reactor Primary Coolant Pump and Motor Replacement Project

    SciTech Connect (OSTI)

    Noel Duckwitz

    2011-06-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3B, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3B and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Advanced Test Reactor Reliability Sustainment Project. While this project does not introduce new hazards to the ATR, it has the potential for significant impacts to safety-related systems, structures, and components that are credited in the ATR safety basis and are being replaced. Thus the project has been determined to meet the definition of a major modification and is being managed accordingly.

  1. Safety Design Strategy for the Advanced Test Reactor Diesel Bus (E-3) and Switchgear Replacement Project

    SciTech Connect (OSTI)

    Noel Duckwitz

    2011-06-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3B, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3B and DOE Order 420.1B, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Advanced Test Reactor Reliability Sustainment Project. While this project does not introduce new hazards to the ATR, it has the potential for significant impacts to safety-related systems, structures, and components that are credited in the ATR safety basis and are being replaced. Thus the project has been determined to meet the definition of a major modification and is being managed accordingly.

  2. DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 1: Technical standard

    SciTech Connect (OSTI)

    1998-05-01

    This Department of Energy (DOE) technical standard (referred to as the Standard) provides guidance for integrating and enhancing worker, public, and environmental protection during facility disposition activities. It provides environment, safety, and health (ES and H) guidance to supplement the project management requirements and associated guidelines contained within DOE O 430.1A, Life-Cycle Asset Management (LCAM), and amplified within the corresponding implementation guides. In addition, the Standard is designed to support an Integrated Safety Management System (ISMS), consistent with the guiding principles and core functions contained in DOE P 450.4, Safety Management System Policy, and discussed in DOE G 450.4-1, Integrated Safety Management System Guide. The ISMS guiding principles represent the fundamental policies that guide the safe accomplishment of work and include: (1) line management responsibility for safety; (2) clear roles and responsibilities; (3) competence commensurate with responsibilities; (4) balanced priorities; (5) identification of safety standards and requirements; (6) hazard controls tailored to work being performed; and (7) operations authorization. This Standard specifically addresses the implementation of the above ISMS principles four through seven, as applied to facility disposition activities.

  3. March 7, 2012, USW Health Safety and Environment Conference Presentati...

    Office of Environmental Management (EM)

    Lessons Learned from Similar Safety Culture Improvement Initiatives (INPO, NRC, NASA, OSHA, and IAEA) * Identified 3 Safety Culture Focus Areas and Associated Attributes: -...

  4. Y-12s Environment, Safety and Health history part 3

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

    control of occupational safety and health hazards and the development, implementation and continuous improvement of their safety and health management system." Y-12 achieved the...

  5. Safety problems of water-development works designed for land reclamation

    SciTech Connect (OSTI)

    Shchedrin, V. N.; Kosichenko, Yu. M.

    2011-11-15

    A safety declaration is a fundamental document assuring the safety of water-development works, their correspondence to safety criteria, the design, and active technical regulations and rules.

  6. Nonreactor Nuclear Safety Design Guide for use with DOE O 420.1C, Facility Safety

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

    2012-12-04

    This Guide provides an acceptable approach for safety design of DOE hazard category 1, 2 and 3 nuclear facilities for satisfying the requirements of DOE O 420.1C. Supersedes DOE G 420.1-1.

  7. Design an optimum safety policy for personnel safety management - A system dynamic approach

    SciTech Connect (OSTI)

    Balaji, P.

    2014-10-06

    Personnel safety management (PSM) ensures that employee's work conditions are healthy and safe by various proactive and reactive approaches. Nowadays it is a complex phenomenon because of increasing dynamic nature of organisations which results in an increase of accidents. An important part of accident prevention is to understand the existing system properly and make safety strategies for that system. System dynamics modelling appears to be an appropriate methodology to explore and make strategy for PSM. Many system dynamics models of industrial systems have been built entirely for specific host firms. This thesis illustrates an alternative approach. The generic system dynamics model of Personnel safety management was developed and tested in a host firm. The model was undergone various structural, behavioural and policy tests. The utility and effectiveness of model was further explored through modelling a safety scenario. In order to create effective safety policy under resource constraint, DOE (Design of experiment) was used. DOE uses classic designs, namely, fractional factorials and central composite designs. It used to make second order regression equation which serve as an objective function. That function was optimized under budget constraint and optimum value used for safety policy which shown greatest improvement in overall PSM. The outcome of this research indicates that personnel safety management model has the capability for acting as instruction tool to improve understanding of safety management and also as an aid to policy making.

  8. Safety in urban environment and emergency notice boards

    SciTech Connect (OSTI)

    Confortini, Claudia; Tira, Maurizio

    2008-07-08

    Reliable and safe urban system conditions have to be a crucial goal of ordinary planning activities. Among planning goals, priority must be given to indications relating to the safety levels to be achieved and to the amount of resources to be directed towards reducing the vulnerability of urban systems and therefore of the measures to be taken. Uban vulnerability cannot in fact be reduced to the sum of the vulnerability of single buildings or to the physical vulnerability of its various components. This research work consists of identifying those urban sub-areas that are important for safety in relation to natural risks, ambits that should be highlighted by means of permanent emergency notice boards/billboards. What are the hazard notices relating to all natural hazards and related risks? Where are they located? Are they clear and straightforward so that all residents and visitors are able to understand them, as it is already the case for road signs (or at least it should be)? What urban sub-areas are worth highlighting in relation to natural risks, acting for example as escape routes or meeting points? How is information for the public managed in order that people are immediately, easily and regularly notified? What is the relation of such signals to ordinary traffic signals? Research into the state of the art of permanent notice boards/billboards of this type, currently distinguished only by sporadic and local initiatives, aims at carrying out a census of and recognizing urban elements already considered as important for reducing the vulnerability of the urban system to different natural calamities and at providing new highlights as regards the identification of new ones. The next step is to work out a decision and common-language strategy for planning these elements and for their adequate signposting, so as to be able to live in the urban environment with awareness, safety and confidence, including with respect to more remote and therefore often neglected natural risks. The paper deals with literature in the field and shows the results of the few relevant case studies at work.

  9. Order Module--DOE O 231.1B, ENVIRONMENT, SAFETY, AND HEALTH REPORTING...

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

    analysis, and dissemination of data pertaining to environment, safety, and health issues as required by law, or regulations, or in support of United States political ...

  10. March 7, 2012, USW Health Safety and Environment Conference Presentati...

    Office of Environmental Management (EM)

    Implementation Improvement Efforts Bill McArthur Director, Office of Worker Safety and Health Policy Office of Health, Safety and Security U.S. Department of Energy USW Health,...

  11. Environment/Health/Safety: Sub-Contractor Construction Resource...

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

    EH&S Sub-Contractor Construction Resource Page 2015 Home EHS0470-GERT JHA Templates Tool Box Safety Topics Pub-3000 Ch. 10 - Construction Safety Manual Administrative Policies...

  12. CRAD, Facility Safety- Nuclear Facility Design

    Office of Energy Efficiency and Renewable Energy (EERE)

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) that can be used for assessment of a contractor's Nuclear Facility Design.

  13. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Boyd D. Chirstensen

    2012-04-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, Program and Project Management for the Acquisition of Capital Assets, safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, Facility Safety, and the expectations of DOE-STD-1189-2008, Integration of Safety into the Design Process, provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  14. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Boyd D. Chirstensen

    2012-08-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, Program and Project Management for the Acquisition of Capital Assets, safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, Facility Safety, and the expectations of DOE-STD-1189-2008, Integration of Safety into the Design Process, provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  15. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Gary Mecham

    2010-05-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, Program and Project Management for the Acquisition of Capital Assets, safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, Facility Safety, and the expectations of DOE-STD-1189-2008, Integration of Safety into the Design Process, provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  16. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Gary Mecham

    2010-10-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, Program and Project Management for the Acquisition of Capital Assets, safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1B, Facility Safety, and the expectations of DOE-STD-1189-2008, Integration of Safety into the Design Process, provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  17. Safety Design Strategy for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Boyd D. Chirstensen

    2015-03-01

    In accordance with the requirements of U.S. Department of Energy (DOE) Order 413.3A, “Program and Project Management for the Acquisition of Capital Assets,” safety must be integrated into the design process for new or major modifications to DOE Hazard Category 1, 2, and 3 nuclear facilities. The intended purpose of this requirement involves the handling of hazardous materials, both radiological and chemical, in a way that provides adequate protection to the public, workers, and the environment. Requirements provided in DOE Order 413.3A and DOE Order 420.1C, “Facility Safety,” and the expectations of DOE-STD-1189-2008, “Integration of Safety into the Design Process,” provide for identification of hazards early in the project and use of an integrated team approach to design safety into the facility. This safety design strategy provides the basic safety-in-design principles and concepts that will be used for the Remote-Handled Low-Level Waste Disposal Project.

  18. Design review report for modifications to RMCS safety class equipment

    SciTech Connect (OSTI)

    Corbett, J.E.

    1997-05-30

    This report documents the completion of the formal design review for modifications to the Rotary Mode Core Sampling (RMCS) safety class equipment. These modifications are intended to support core sampling operations in waste tanks requiring flammable gas controls. The objective of this review was to approve the Engineering Change Notices affecting safety class equipment used in the RMCS system. The conclusion reached by the review committee was that these changes are acceptable.

  19. Y-12s environment, safety and health history

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

    environmental sensitivity, safety culture and proactive health emphasis present at the Y-12 National Security Complex today has evolved over time. It can be seen in the...

  20. March 7, 2012, USW Health Safety and Environment Conference Presentati...

    Office of Environmental Management (EM)

    Integrated Approach to Health, Safety and Security Labor Union and Stakeholder Outreach and Collaboration William Eckroade Principal Deputy Chief for Mission Support Operations...

  1. Environment/Health/Safety (EHS): Monthly Accident Statistics

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

    Personal Protective Equipment (PPE) Injury Review & Analysis Worker Safety and Health Program: PUB-3851 Monthly Accident Statistics Latest Accident Statistics Accident...

  2. Environment/Health/Safety (EHS): JHA Help Center

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

    Training Whom to Call Databases Ergonomics References EHS Quick Links 1 Minute 4 Safety Accident Narratives Accident Statistics Accident Statistics Archive Activity Manager AHD...

  3. Inspection of Environment, Safety, and Health Programs at the Savannah River Site, February 2006

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy (DOE) Office of Independent Oversight (Independent Oversight) conducted an inspection of environment, safety, and health (ES&H) programs at the DOE Savannah River Site (SRS) during January and February 2006. The inspection was performed by Independent Oversight’s Office of Environment, Safety and Health Evaluations.

  4. Using partial safety factors in wind turbine design and testing

    SciTech Connect (OSTI)

    Musial, W.D.; Butterfield, C.

    1997-09-01

    This paper describes the relationship between wind turbine design and testing in terms of the certification process. An overview of the current status of international certification is given along with a description of limit-state design basics. Wind turbine rotor blades are used to illustrate the principles discussed. These concepts are related to both International Electrotechnical Commission and Germanischer Lloyd design standards, and are covered using schematic representations of statistical load and material strength distributions. Wherever possible, interpretations of the partial safety factors are given with descriptions of their intended meaning. Under some circumstances, the authors` interpretations may be subjective. Next, the test-load factors are described in concept and then related to the design factors. Using technical arguments, it is shown that some of the design factors for both load and materials must be used in the test loading, but some should not be used. In addition, some test factors not used in the design may be necessary for an accurate test of the design. The results show that if the design assumptions do not clearly state the effects and uncertainties that are covered by the design`s partial safety factors, outside parties such as test labs or certification agencies could impose their own meaning on these factors.

  5. Design Review Report for formal review of safety class features of exhauster system for rotary mode core sampling

    SciTech Connect (OSTI)

    JANICEK, G.P.

    2000-06-08

    Report documenting Formal Design Review conducted on portable exhausters used to support rotary mode core sampling of Hanford underground radioactive waste tanks with focus on Safety Class design features and control requirements for flammable gas environment operation and air discharge permitting compliance.

  6. Review and Approval of Nuclear Facility Safety Basis and Safety Design Basis Documents

    Energy Savers [EERE]

    SENSITIVE DOE-STD-1104-2009 May 2009 Superseding DOE-STD-1104-96 DOE STANDARD REVIEW AND APPROVAL OF NUCLEAR FACILITY SAFETY BASIS AND SAFETY DESIGN BASIS DOCUMENTS U.S. Department of Energy AREA SAFT Washington, DC 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1104-2009 ii Available on the Department of Energy Technical Standards web page at http://www.hss.energy.gov/nuclearsafety/ns/techstds/ DOE-STD-1104-2009 iii CONTENTS FOREWORD

  7. Inspection of Environment, Safety, and Health Management at the Hanford Site, March 2002

    Broader source: Energy.gov [DOE]

    The Secretary of Energy’s Office of Independent Oversight and Performance Assurance (OA) conducted an inspection of environment, safety, and health (ES&H) management at the Department of Energy (DOE) Hanford Site in January-February 2002.

  8. Volume II, Environment, Safety, and Health Special Review of Work Practices

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

    for Nanoscale Material Activities at Department of Energy Laboratories, August 2008 | Department of Energy Volume II, Environment, Safety, and Health Special Review of Work Practices for Nanoscale Material Activities at Department of Energy Laboratories, August 2008 Volume II, Environment, Safety, and Health Special Review of Work Practices for Nanoscale Material Activities at Department of Energy Laboratories, August 2008 At the request of the Secretary of Energy, the U.S. Department of

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

    SciTech Connect (OSTI)

    1981-01-01

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

  10. Y-12s environment, safety and health history part 2

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

    would provide protection from these airborne hazards. Areas began to be flagged off and buffer areas established. Over the ensuing years the environment at the Y-12 site has been...

  11. Environment, Safety and Health Self-Assessment Report Fiscal Year 2010

    SciTech Connect (OSTI)

    Robinson, Scott

    2011-03-23

    The Lawrence Berkeley National Laboratory (LBNL) Environment, Safety, and Health (ES&H) Self-Assessment Program was established to ensure that Integrated Safety Management (ISM) is implemented institutionally and by all divisions. The ES&H Self-Assessment Program, managed by the Office of Contractor Assurance (OCA), provides for an internal evaluation of all ES&H programs and systems at LBNL. The primary objective of the program is to ensure that work is conducted safely and with minimal negative impact to workers, the public, and the environment. Self-assessment follows the five core functions and guiding principles of ISM. Self-assessment is the mechanism used to promote the continuous improvement of the Laboratory's ES&H programs. The process is described in the Environment, Safety, and Health Assurance Plan (PUB-5344) and is composed of three types of self-assessments: Division ES&H Self-Assessment, ES&H Technical Assurance Program Assessment, and Division ES&H Peer Review. The Division ES&H Self-Assessment Manual (PUB-3105) provides the framework by which divisions conduct formal ES&H self-assessments to systematically identify program deficiencies. Issue-specific assessments are designed and implemented by the divisions and focus on areas of interest to division management. They may be conducted by teams and involve advance planning to ensure that appropriate resources are available. The ES&H Technical Assurance Program Manual (PUB-913E) provides the framework for systematic reviews of ES&H programs and processes. The ES&H Technical Assurance Program Assessment is designed to evaluate whether ES&H programs and processes are compliant with guiding regulations, are effective, and are properly implemented by LBNL divisions. The Division ES&H Peer Review Manual provides the framework by which division ISM systems are evaluated and improved. Peer Reviews are conducted by teams under the direction of senior division management and focus on higher-level management issues. Peer Review teams are selected on the basis of members knowledge and experience in the issues of interest to the division director. LBNL periodically requests in-depth independent assessments of selected ES&H programs. Such assessments augment LBNL's established assessment processes and provide an objective view of ES&H program effectiveness. Institutional Findings, Observations, and Noteworthy Practices identified during independent assessments are specifically intended to help LBNL identify opportunities for program improvement. This report includes the results of the Division ES&H Self-Assessment, ES&H Technical Assurance Program Assessment, and Division ES&H Peer Review, respectively.

  12. Jefferson Lab Environment, Safety, Health and Quality Division

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

    ... Jefferson Lab requires that all new pressure systems designed and fabricated after 22808 conform to the applicable: ASME Boiler and Pressure Vessel Code, Sections I through XII ...

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

    Broader source: Energy.gov [DOE]

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

  14. Resilient Design: Transitioning to the New Built Environment

    Broader source: Energy.gov [DOE]

    Alex Wilson, Founder, BuildingGreen Inc. and Resilient Design Institute, provides context for why we need to be considering resilience in looking at the built environment during the coming decades.

  15. Designing user models in a virtual cave environment

    SciTech Connect (OSTI)

    Brown-VanHoozer, S.; Hudson, R.; Gokhale, N.

    1995-12-31

    In this paper, the results of a first study into the use of virtual reality for human factor studies and design of simple and complex models of control systems, components, and processes are described. The objective was to design a model in a virtual environment that would reflect more characteristics of the user`s mental model of a system and fewer of the designer`s. The technology of a CAVE{trademark} virtual environment and the methodology of Neuro Linguistic Programming were employed in this study.

  16. Protection of Operators and Environment - the Safety Concept of the Karlsruhe Vitrification Plant VEK

    SciTech Connect (OSTI)

    Fleisch, J.; Kuttruf, H.; Lumpp, W.; Pfeifer, W.; Roth, G.; Weisenburger, S.

    2002-02-26

    The Karlsruhe Vitrification Plant (VEK) plant is a milestone in decommissioning and complete dismantling of the former Karlsruhe Reprocessing Plant WAK, which is in an advanced stage of disassembly. The VEK is scheduled to vitrify approx. 70 m3 of the highly radioactive liquid waste (HLW) resulting from reprocessing. Site preparation, civil work and component manufacturing began in 1999. The building will be finalized by mid of 2002, hot vitrification operation is currently scheduled for 2004/2005. Provisions against damages arising from construction and operation of the VEK had to be made in accordance with the state of the art as laid down in the German Atomic Law and the Radiation Protection Regulations. For this purpose, the appropriate analysis of accidents and their external and internal impacts were investigated. During the detailed design phase, a failure effects analysis was carried out, in which single events were studied with respect to the objectives of protection and ensuring activity containment, limiting radioactive discharges to the environment and protecting of the staff. Parallel to the planning phase of the VEK plant a cold prototype test facility (PVA) covering the main process steps was constructed and operated at the Institut fuer Nukleare Entsorgung (INE) of FZK. This pilot operation served to demonstrate the process technique and its operation with a simulated waste solution, and to test the main items of equipment, but was conducted also to use the experimental data and experience to back the safety concept of the radioactive VEK plant. This paper describes the basis of the safety concept of the VEK plant and results of the failure effect analysis. The experimental simulation of the failure scenarios, their effect on the process behavior, and the controllability of these events as well as the effect of the results on the safety concept of VEK are discussed. Additionally, an overview of the actual status of civil work and manufacturing of the technical equipment is given.

  17. ARIES-ACT1 Safety Design and Analysis

    SciTech Connect (OSTI)

    Humrickhouse, Paul W.; Merrill, Brad J.

    2014-01-01

    ARIES-ACT1 (Advanced and Conservative Tokamak) is a 1000-MW(electric) tokamak design featuring advanced plasma physics and divertor and blanket engineering. Some relevant features include an advanced SiC blanket with PbLi as coolant and breeder; a helium-cooled steel structural ring and tungsten divertors; a thin-walled, helium-cooled vacuum vessel; and a room-temperature, water-cooled shield outside the vacuum vessel. We consider here some safety aspects of the ARIES-ACT1 design and model a series of design-basis and beyond-design-basis accidents with the MELCOR code modified for fusion. The presence of multiple coolants (PbLi, helium, and water) makes possible a variety of such accidents. We consider here a loss-of-flow accident caused by a long-term station blackout (LTSBO), an ex-vessel helium break into the cryostat, and a beyond-design-basis accident in which a LTSBO is aggravated by a loss-of-coolant accident in ARIES-ACT1's ultimate decay heat removal system, the water-cooled shield. In the design-basis accidents, we find that the secondary confinement boundaries are not challenged, and the structural integrity of in-vessel components is not threatened by high temperatures or pressures; decay heat can be passively removed.

  18. Frequently Asked Questions Regarding DOE-STD-1195-2011, Design of Safety

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

    Significant Safety Instrumented Systems Used at DOE Non-Reactor Nuclear Facilities | Department of Energy Frequently Asked Questions Regarding DOE-STD-1195-2011, Design of Safety Significant Safety Instrumented Systems Used at DOE Non-Reactor Nuclear Facilities Frequently Asked Questions Regarding DOE-STD-1195-2011, Design of Safety Significant Safety Instrumented Systems Used at DOE Non-Reactor Nuclear Facilities January 7, 2015 Frequently Asked Questions regarding DOE-STD-1195-2011 which

  19. Integrating Safety, Operations, Security, and Safeguards (ISOSS) into the design of small modular reactors : a handbook.

    SciTech Connect (OSTI)

    Middleton, Bobby D.; Mendez, Carmen Margarita

    2013-10-01

    The existing regulatory environment for nuclear reactors impacts both the facility design and the cost of operations once the facility is built. Delaying the consideration of regulatory requirements until late in the facility design - or worse, until after construction has begun - can result in costly retrofitting as well as increased operational costs to fulfill safety, security, safeguards, and emergency readiness requirements. Considering the scale and scope, as well as the latest design trends in the next generation of nuclear facilities, there is an opportunity to evaluate the regulatory requirements and optimize the design process for Small Modular Reactors (SMRs), as compared to current Light Water Reactors (LWRs). To this end, Sandia has embarked on an initiative to evaluate the interactions of regulations and operations as an approach to optimizing the design of SMR facilities, supporting operational efficiencies, as well as regulatory requirements. The early stages of this initiative consider two focus areas. The first focus area, reported by LaChance, et al. (2007), identifies the regulatory requirements established for the current fleet of LWR facilities regarding Safety, Security, Operations, Safeguards, and Emergency Planning, and evaluates the technical bases for these requirements. The second focus area, developed in this report, documents the foundations for an innovative approach that supports a design framework for SMR facilities that incorporates the regulatory environment, as well as the continued operation of the facility, into the early design stages, eliminating the need for costly retrofitting and additional operating personnel to fulfill regulatory requirements. The work considers a technique known as Integrated Safety, Operations, Security and Safeguards (ISOSS) (Darby, et al., 2007). In coordination with the best practices of industrial operations, the goal of this effort is to develop a design framework that outlines how ISOSS requirements can be incorporated into the pre-conceptual through early facility design stages, seeking a cost-effective design that meets both operational efficiencies and the regulatory environment. The larger scope of the project, i.e., in future stages, includes the identification of potentially conflicting requirements identified by the ISOSS framework, including an analysis of how regulatory requirements may be changed to account for the intrinsic features of SMRs.

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

    Broader source: Energy.gov [DOE]

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

  1. Safeguard By Design Lessons Learned from DOE Experience Integrating Safety into Design

    SciTech Connect (OSTI)

    Hockert, John; Burbank, Roberta L.

    2010-04-13

    This paper identifies the lessons to be learned for the institutionalization of Safeguards by Design (SBD) from the Department of Energy (DOE) experience developing and implementing DOE-STD-1189-2008, Integration of Safety into the Design Process. The experience is valuable because of the similarity of the challenges of integrating safety and safeguards into the design process. The paper reviews the content and development of DOE-STD-1189-2008 from its initial concept in January 2006 to its issuance in March 2008. Lessons learned are identified in the areas of the development and structure of requirements for the SBD process; the target audience for SBD requirements and guidance, the need for a graded approach to SBD, and a possible strategy for development and implementation of SBD within DOE.

  2. New rocket propellant and motor design offer high-performance and safety

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

    New rocket propellant and motor design offer high-performance and safety New rocket propellant and motor design offer high-performance and safety Scientists recently flight tested a new rocket design that includes a high-energy fuel and a motor design that also delivers a high degree of safety December 22, 2014 Rocket flight test at the Energetic Materials Research and Testing Center launch site near Socorro, NM. Rocket flight test at the Energetic Materials Research and Testing Center launch

  3. Final safety analysis report for the Galileo Mission: Volume 1, Reference design document

    SciTech Connect (OSTI)

    Not Available

    1988-05-01

    The Galileo mission uses nuclear power sources called Radioisotope Thermoelectric Generators (RTGs) to provide the spacecraft's primary electrical power. Because these generators contain nuclear material, a Safety Analysis Report (SAR) is required. A preliminary SAR and an updated SAR were previously issued that provided an evolving status report on the safety analysis. As a result of the Challenger accident, the launch dates for both Galileo and Ulysses missions were later rescheduled for November 1989 and October 1990, respectively. The decision was made by agreement between the DOE and the NASA to have a revised safety evaluation and report (FSAR) prepared on the basis of these revised vehicle accidents and environments. The results of this latest revised safety evaluation are presented in this document (Galileo FSAR). Volume I, this document, provides the background design information required to understand the analyses presented in Volumes II and III. It contains descriptions of the RTGs, the Galileo spacecraft, the Space Shuttle, the Inertial Upper Stage (IUS), the trajectory and flight characteristics including flight contingency modes, and the launch site. There are two appendices in Volume I which provide detailed material properties for the RTG.

  4. Differing Professional Opinions for Technical Issues Involving Environment, Safety and Health

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

    2011-07-29

    The Order establishes the DOE Differing Professional Opinion process for employees to raise technical concerns related to environment, safety, and health which cannot be resolved using routine processes. Supersedes DOE P 442.1 and DOE M 442.1-1.

  5. Differing Professional Opinions Manual for Technical Issues Involving Environment, Safety, and Health

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

    2006-11-16

    This Manual establishes a differing professional opinion (DPO) policy to a Department of Energy (DOE) Differing Professional Opinion (DPO) Process to encourage and facilitate dialogue and resolution on DPOs from employees for technical issues involving environment, safety, and health. Does not cancel other directives. Canceled by DOE O 442.2.

  6. Environment, safety, and health considerations for a neutrino source based on a muon storage ring

    SciTech Connect (OSTI)

    J. Donald Cossairt

    2000-05-15

    The Neutrino Source presents a number of challenges in the general area of environment, safety, and health. It is the intent of this paper to identify these challenges and make a preliminary, but not detailed assessment of how they might be addressed and of their potential impact on the project. Some of the considerations which must be taken into account are very similar to those that have been encountered and solved during the construction and operation of other facilities at Fermilab and at similar laboratories elsewhere in the US and worldwide. Other considerations have not been encountered previously in connection with the construction and operation of accelerator laboratories. These novel issues will require particular attention as such a project proceeds to assure their timely resolution in a manner that is cost-effective and that meets the approval of the public. In this paper, both the conventional and the novel issues are discussed, with more emphasis on the latter. It is concluded here that with adequate planning in the design stages, these problems can be adequately addressed in a manner that merits the support of the Laboratory, the Department of Energy, and the public. An abbreviated version of this paper appears as Chapter 14 in the report of a recent feasibility study (Ho 00)and the figures have come from that work.

  7. Facility Safety

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

    1996-10-24

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

  8. Facility Safety

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

    1995-11-16

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

  9. Technology Development, Evaluation, and Application (TDEA) FY 2001 Progress Report Environment, Safety, and Health (ESH) Division

    SciTech Connect (OSTI)

    L.G. Hoffman; K. Alvar; T. Buhl; E. Foltyn; W. Hansen; B. Erdal; P. Fresquez; D. Lee; B. Reinert

    2002-05-01

    This progress report presents the results of 11 projects funded ($500K) in FY01 by the Technology Development, Evaluation, and Application (TDEA) Committee of the Environment, Safety, and Health Division (ESH). Five projects fit into the Health Physics discipline, 5 projects are environmental science and one is industrial hygiene/safety. As a result of their TDEA-funded projects, investigators have published sixteen papers in professional journals, proceedings, or Los Alamos reports and presented their work at professional meetings. Supplement funds and in-kind contributions, such as staff time, instrument use, and workspace, were also provided to TDEA-funded projects by organizations external to ESH Divisions.

  10. Pacific Northwest Laboratory annual report for 1990 to the Assistant Secretary for Environment, Safety, and Health

    SciTech Connect (OSTI)

    Faust, L.G.; Moraski, R.V.; Selby, J.M.

    1991-05-01

    Part 5 of the 1990 Annual Report to the US Department of Energy's Assistant Secretary for Environment, Safety, and Health presents Pacific Northwest Laboratory's progress on work performed for the Office of Environmental Guidance, the Office of Environmental Compliance, the Office of Environmental Audit, the Office of National Environmental Policy Act Project Assistance, the Office of Nuclear Safety, the Office of Safety Compliance, and the Office of Policy and Standards. For each project, as identified by the Field Work Proposal, there is an article describing progress made during fiscal year 1990. Authors of these articles represent a broad spectrum of capabilities derived from five of the seven technical centers of the Laboratory, reflecting the interdisciplinary nature of the work.

  11. DOE-STD-1120-2005; Integration of Environment, Safety, and Health into Facility Disposition Activities

    Office of Environmental Management (EM)

    120-2005 Volume 2 of 2 DOE STANDARD INTEGRATION OF ENVIRONMENT, SAFETY, AND HEALTH INTO FACILITY DISPOSITION ACTIVITIES Volume 2 of 2: Appendices U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from the Office of Scientific and Technical Information, P.O. Box 62, Oak

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

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

    documented safety analysis. BACKGROUND On March 11, 2011, the Fukushima Daiichi nuclear power station in Japan was ... of the operating reactors due to the earthquake, a ...

  13. Design of the NSLS-II Top-Off Safety System

    SciTech Connect (OSTI)

    Fliller, III R.; Doom, L.; Ganetis, G.; Hetzel, C.; Job, P. K.; Li, Y.; Shaftan, T.; Sharma, S.; Singh, O.; Wang, G. M.; Xia, Z.

    2015-05-03

    The NSLS-II accelerators finished commissioning in the fall of 2014, with beamline commissioning underway. Part of the design for the NSLS-II is to operate in top off mode. The Top Off Safety System (TOSS) is presently being installed. In this report we discuss the Top Off Safety System design and implementation, along with the necessary tracking results and radiological calculations.

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

    SciTech Connect (OSTI)

    Chernowski, John

    2009-02-27

    Lawrence Berkeley National Laboratory's Environment, Safety, and Health (ES&H) Self-Assessment Program ensures that Integrated Safety Management (ISM) is implemented institutionally and by all divisions. The Self-Assessment Program, managed by the Office of Contract Assurance (OCA), provides for an internal evaluation of all ES&H programs and systems at LBNL. The functions of the program are to ensure that work is conducted safely, and with minimal negative impact to workers, the public, and the environment. The Self-Assessment Program is also the mechanism used to institute continuous improvements to the Laboratory's ES&H programs. The program is described in LBNL/PUB 5344, Environment, Safety, and Health Self-Assessment Program and is composed of four distinct assessments: the Division Self-Assessment, the Management of Environment, Safety, and Health (MESH) review, ES&H Technical Assurance, and the Appendix B Self-Assessment. The Division Self-Assessment uses the five core functions and seven guiding principles of ISM as the basis of evaluation. Metrics are created to measure performance in fulfilling ISM core functions and guiding principles, as well as promoting compliance with applicable regulations. The five core functions of ISM are as follows: (1) Define the Scope of Work; (2) Identify and Analyze Hazards; (3) Control the Hazards; (4) Perform the Work; and (5) Feedback and Improvement. The seven guiding principles of ISM are as follows: (1) Line Management Responsibility for ES&H; (2) Clear Roles and Responsibilities; (3) Competence Commensurate with Responsibilities; (4) Balanced Priorities; (5) Identification of ES&H Standards and Requirements; (6) Hazard Controls Tailored to the Work Performed; and (7) Operations Authorization. Performance indicators are developed by consensus with OCA, representatives from each division, and Environment, Health, and Safety (EH&S) Division program managers. Line management of each division performs the Division Self-Assessment annually. The primary focus of the review is workplace safety. The MESH review is an evaluation of division management of ES&H in its research and operations, focusing on implementation and effectiveness of the division's ISM plan. It is a peer review performed by members of the LBNL Safety Review Committee (SRC), with staff support from OCA. Each division receives a MESH review every two to four years, depending on the results of the previous review. The ES&H Technical Assurance Program (TAP) provides the framework for systematic reviews of ES&H programs and processes. The intent of ES&H Technical Assurance assessments is to provide assurance that ES&H programs and processes comply with their guiding regulations, are effective, and are properly implemented by LBNL divisions. The Appendix B Performance Evaluation and Measurement Plan (PEMP) requires that LBNL sustain and enhance the effectiveness of integrated safety, health, and environmental protection through a strong and well-deployed system. Information required for Appendix B is provided by EH&S Division functional managers. The annual Appendix B report is submitted at the close of the fiscal year. This assessment is the Department of Energy's (DOE) primary mechanism for evaluating LBNL's contract performance in ISM.

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

    SciTech Connect (OSTI)

    Not Available

    1992-11-01

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

  16. Technology Development, Evaluation, and Application (TDEA) FY 1999 Progress Report, Environment, Safety, and Health (ESH) Division

    SciTech Connect (OSTI)

    Larry G. Hoffman

    2000-12-01

    This progress report presents the results of 10 projects funded ($500K) in FY99 by the Technology Development, Evaluation, and Application (TDEA) Committee of the Environment, Safety, and Health Division. Five are new projects for this year; seven projects have been completed in their third and final TDEA-funded year. As a result of their TDEA-funded projects, investigators have published thirty-four papers in professional journals, proceedings, or Los Alamos reports and presented their work at professional meetings. Supplemental funds and in-kind contributions, such as staff time, instrument use, and work space, were also provided to TDEA-funded projects by organizations external to ESH Division.

  17. Safety concerns and suggested design approaches to the HTGR Reformer process concept

    SciTech Connect (OSTI)

    Green, R.C.

    1981-09-01

    This report is a safety review of the High Temperature Gas-Cooled Reactor Reformer Application Study prepared by Gas-Cooled Reactor Associates (GCRA) of La Jolla, California. The objective of this review was to identify safety concerns and suggests design approaches to minimize risk in the High Temperature Gas-Cooled Reactor Reformer (HTGR-R) process concept.

  18. Safety

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

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

  19. Nuclear Safety | Department of Energy

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

    Nuclear Safety Nuclear Safety The Nuclear Safety Program mission is to support the design, construction, operation, and deactivation and decommissioning of the Paducah and Portsmouth nuclear facilities in a manner that ensures adequate protection of workers, the public, and the environment. Major Responsibilities: Establish and implement nuclear safety requirements that utilize national consensus (or other government) standards or applicable external agency regulations (Nuclear Regulatory

  20. Exascale Co-design for Modeling Materials in Extreme Environments

    SciTech Connect (OSTI)

    Germann, Timothy C.

    2014-07-08

    Computational materials science has provided great insight into the response of materials under extreme conditions that are difficult to probe experimentally. For example, shock-induced plasticity and phase transformation processes in single-crystal and nanocrystalline metals have been widely studied via large-scale molecular dynamics simulations, and many of these predictions are beginning to be tested at advanced 4th generation light sources such as the Advanced Photon Source (APS) and Linac Coherent Light Source (LCLS). I will describe our simulation predictions and their recent verification at LCLS, outstanding challenges in modeling the response of materials to extreme mechanical and radiation environments, and our efforts to tackle these as part of the multi-institutional, multi-disciplinary Exascale Co-design Center for Materials in Extreme Environments (ExMatEx). ExMatEx has initiated an early and deep collaboration between domain (computational materials) scientists, applied mathematicians, computer scientists, and hardware architects, in order to establish the relationships between algorithms, software stacks, and architectures needed to enable exascale-ready materials science application codes within the next decade. We anticipate that we will be able to exploit hierarchical, heterogeneous architectures to achieve more realistic large-scale simulations with adaptive physics refinement, and are using tractable application scale-bridging proxy application testbeds to assess new approaches and requirements. Such current scale-bridging strategies accumulate (or recompute) a distributed response database from fine-scale calculations, in a top-down rather than bottom-up multiscale approach.

  1. Success Through Safety, Security, and Safeguards by Design (3SBD): From

    Office of Scientific and Technical Information (OSTI)

    Concept to Application Workshop (Conference) | SciTech Connect Success Through Safety, Security, and Safeguards by Design (3SBD): From Concept to Application Workshop Citation Details In-Document Search Title: Success Through Safety, Security, and Safeguards by Design (3SBD): From Concept to Application Workshop Authors: Murphy, Chantell L. [1] ; Blandford, Edward [2] ; Arthur, Edward [2] + Show Author Affiliations Los Alamos National Laboratory University of New Mexico Publication Date:

  2. Automated design synthesis of robotic/human workcells for improved manufacturing system design in hazardous environments

    SciTech Connect (OSTI)

    Williams, Joshua M.

    2012-06-12

    Manufacturing tasks that are deemed too hazardous for workers require the use of automation, robotics, and/or other remote handling tools. The associated hazards may be radiological or nonradiological, and based on the characteristics of the environment and processing, a design may necessitate robotic labor, human labor, or both. There are also other factors such as cost, ergonomics, maintenance, and efficiency that also effect task allocation and other design choices. Handling the tradeoffs of these factors can be complex, and lack of experience can be an issue when trying to determine if and what feasible automation/robotics options exist. To address this problem, we utilize common engineering design approaches adapted more for manufacturing system design in hazardous environments. We limit our scope to the conceptual and embodiment design stages, specifically a computational algorithm for concept generation and early design evaluation. In regard to concept generation, we first develop the functional model or function structure for the process, using the common 'verb-noun' format for describing function. A common language or functional basis for manufacturing was developed and utilized to formalize function descriptions and guide rules for function decomposition. Potential components for embodiment are also grouped in terms of this functional language and are stored in a database. The properties of each component are given as quantitative and qualitative criteria. Operators are also rated for task-relevant criteria which are used to address task compatibility. Through the gathering of process requirements/constraints, construction of the component database, and development of the manufacturing basis and rule set, design knowledge is stored and available for computer use. Thus, once the higher level process functions are defined, the computer can automate the synthesis of new design concepts through alternating steps of embodiment and function structure updates/decomposition. In the process, criteria guide function allocation of components/operators and help ensure compatibility and feasibility. Through multiple function assignment options and varied function structures, multiple design concepts are created. All of the generated designs are then evaluated based on a number of relevant evaluation criteria: cost, dose, ergonomics, hazards, efficiency, etc. These criteria are computed using physical properties/parameters of each system based on the qualities an engineer would use to make evaluations. Nuclear processes such as oxide conversion and electrorefining are utilized to aid algorithm development and provide test cases for the completed program. Through our approach, we capture design knowledge related to manufacturing and other operations in hazardous environments to enable a computational program to automatically generate and evaluate system design concepts.

  3. Assessment of Offshore Wind System Design, Safety, and Operation Standards

    SciTech Connect (OSTI)

    Sirnivas, S.; Musial, W.; Bailey, B.; Filippelli, M.

    2014-01-01

    This report is a deliverable for a project sponsored by the U.S. Department of Energy (DOE) entitled National Offshore Wind Energy Resource and Design Data Campaign -- Analysis and Collaboration (contract number DE-EE0005372; prime contractor -- AWS Truepower). The project objective is to supplement, facilitate, and enhance ongoing multiagency efforts to develop an integrated national offshore wind energy data network. The results of this initiative are intended to 1) produce a comprehensive definition of relevant met-ocean resource assets and needs and design standards, and 2) provide a basis for recommendations for meeting offshore wind energy industry data and design certification requirements.

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

    SciTech Connect (OSTI)

    Holcomb, David Eugene

    2015-01-01

    Fluoride salt-cooled high-temperature reactors (FHRs) will rely more extensively on passive safety than earlier reactor classes. 10CFR50 Appendix A, General Design Criteria for Nuclear Power Plants, establishes minimum design requirements to provide reasonable assurance of adequate safety. 10CFR50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, provides guidance on how the safety significance of systems, structures, and components (SSCs) should be reflected in their regulatory treatment. The Nuclear Energy Institute (NEI) has provided 10 CFR 50.69 SSC Categorization Guideline (NEI-00-04) that factors in probabilistic risk assessment (PRA) model insights, as well as deterministic insights, through an integrated decision-making panel. Employing the PRA to inform deterministic requirements enables an appropriately balanced, technically sound categorization to be established. No FHR currently has an adequate PRA or set of design basis accidents to enable establishing the safety classification of its SSCs. While all SSCs used to comply with the general design criteria (GDCs) will be safety related, the intent is to limit the instrumentation risk significance through effective design and reliance on inherent passive safety characteristics. For example, FHRs have no safety-significant temperature threshold phenomena, thus, enabling the primary and reserve reactivity control systems required by GDC 26 to be passively, thermally triggered at temperatures well below those for which core or primary coolant boundary damage would occur. Moreover, the passive thermal triggering of the primary and reserve shutdown systems may relegate the control rod drive motors to the control system, substantially decreasing the amount of safety-significant wiring needed. Similarly, FHR decay heat removal systems are intended to be running continuously to minimize the amount of safety-significant instrumentation needed to initiate operation of systems and components important to safety as required in GDC 20. This paper provides an overview of the design process employed to develop a pre-conceptual FHR instrumentation architecture intended to lower plant capital and operational costs by minimizing reliance on expensive, safety related, safety-significant instrumentation through the use of inherent passive features of FHRs.

  5. Technology Development, Evaluation, and Application (TDEA) FY 1998 Progress Report Environment, Safety, and Health (ESH) Division

    SciTech Connect (OSTI)

    Larry G. Hoffman; Kenneth Alvar; Thomas Buhl; Bruce Erdal; Philip Fresquez; Elizabeth Foltyn; Wayne Hansen; Bruce Reinert

    1999-06-01

    This progress report presents the results of 10 projects funded ($504K) in FY98 by the Technology Development, Evaluation, and Application (TDEA) Committee of the Environment, Safety, and Health Division. Nine projects are new for this year; two projects were completed in their third and final TDEA-funded year. As a result of their TDEA-funded projects, investigators have published 19 papers in professional journals, proceedings, or Los Alamos reports and presented their work at professional meetings. Supplemental funds and in-kind contributions, such as staff time, instrument use, and work space were also provided to the TDEA-funded projects by organizations external to ESH Division. Products generated from the projects funded in FY98 included a new extremity dosimeter that replaced the previously used finger-ring dosimeters, a light and easy-to-use detector to measure energy deposited by neutron interactions, and a device that will allow workers to determine the severity of a hazard.

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

    SciTech Connect (OSTI)

    2007-09-30

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

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

    SciTech Connect (OSTI)

    Not Available

    1989-09-01

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

  8. DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 2: Appendices

    SciTech Connect (OSTI)

    1998-05-01

    This volume contains the appendices that provide additional environment, safety, and health (ES and H) information to complement Volume 1 of this Standard. Appendix A provides a set of candidate DOE ES and H directives and external regulations, organized by hazard types that may be used to identify potentially applicable directives to a specific facility disposition activity. Appendix B offers examples and lessons learned that illustrate implementation of ES and H approaches discussed in Section 3 of Volume 1. Appendix C contains ISMS performance expectations to guide a project team in developing and implementing an effective ISMS and in developing specific performance criteria for use in facility disposition. Appendix D provides guidance for identifying potential Applicable or Relevant and Appropriate Requirements (ARARs) when decommissioning facilities fall under the Comprehensive Environmental Response, Compensation, Liability Act (CERCLA) process. Appendix E discusses ES and H considerations for dispositioning facilities by privatization. Appendix F is an overview of the WSS process. Appendix G provides a copy of two DOE Office of Nuclear Safety Policy and Standards memoranda that form the bases for some of the guidance discussed within the Standard. Appendix H gives information on available hazard analysis techniques and references. Appendix I provides a supplemental discussion to Sections 3.3.4, Hazard Baseline Documentation, and 3.3.6, Environmental Permits. Appendix J presents a sample readiness evaluation checklist.

  9. safety

    National Nuclear Security Administration (NNSA)

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

  10. Independent Oversight Inspection of Environment, Safety, and Health Programs at the Argonne National Laboratory, Technical Appendices, Volume II, May 2005

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy (DOE) Office of Independent Oversight and Performance Assurance (OA) inspected environment, safety, and health (ES&H) programs at the DOE Argonne National Laboratory (ANL) during April and May 2005. The inspection was performed by the OA Office of Environment, Safety and Health Evaluations. This volume of the report provides four technical appendices (C through F) containing detailed results of the OA review. Appendix C provides the results of the review of the application of the core functions of ISM for ANL work activities. Appendix D presents the results of the review of SC, ASO, and ANL feedback and continuous improvement processes and management systems. Appendix E presents the results of the review of essential safety system functionality, and Appendix F presents the results of the review of safety management of the selected focus areas.

  11. Independent Oversight Inspection of Environment, Safety, and Health Programs at the Sandia National Laboratories, Technical Appendices, Volume II, May 2005

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy (DOE) Office of Independent Oversight and Performance Assurance (OA) inspected environment, safety, and health (ES&H) programs at DOE Sandia National Laboratories (SNL) during March and April 2005. The inspection was performed by the OA Office of Environment, Safety and Health Evaluations. This volume of the report provides four technical appendices (C through F) containing detailed results of the OA review. Appendix C provides the results of the review of the application of the core functions of ISM for SNL work activities. Appendix D presents the results of the review of NNSA, SSO, and SNL feedback and continuous improvement processes and management systems. Appendix E presents the results of the review of essential safety system functionality, and Appendix F presents the results of the review of safety management of the selected focus areas.

  12. LMFBR conceptual design study: an overview of environmental and safety concerns

    SciTech Connect (OSTI)

    Brenchley, D.L.

    1981-06-01

    The US Department of Energy (DOE) initiated the Liquid Metal Fast Breeder (LMFBR) Conceptual Design Study (CDS) with the objective of maintaining a viable breeder option. The project is scheduled to be completed in FY-1981 but decisions regarding plant construction will be delayed until at least 1985. This report provides a review of the potential environmental and safety engineering concerns for the CDS and recommends specific action for the Environmental and Safety Engineering Division of DOE.

  13. Office of Environment, Safety and Health Assessments Protocol for Site Leads, April 2015 (Revision 1) – PROTOCOL – EA-31-01

    Broader source: Energy.gov [DOE]

    Office of Environment, Safety and Health Assessments Protocol for Site Leads, April 2015 (Revision 1) – PROTOCOL – EA-31-01

  14. Inspection of Environment, Safety, and Health and Emergency Management at the Nevada Test Site- Summary Report, October 2002

    Broader source: Energy.gov [DOE]

    The Secretary of Energy’s Office of Independent Oversight and Performance Assurance (OA) conducted an inspection of environment, safety, and health (ES&H) and emergency management programs at the National Nuclear Security Administration (NNSA) Nevada Test Site (NTS) in September and October

  15. Program desk manual for occupational safety and health -- U.S. Department of Energy Richland Operations, Office of Environment Safety and Health

    SciTech Connect (OSTI)

    Musen, L.G.

    1998-08-27

    The format of this manual is designed to make this valuable information easily accessible to the user as well as enjoyable to read. Each chapter contains common information such as Purpose, Scope, Policy and References, as well as information unique to the topic at hand. This manual can also be provided on a CD or Hanford Internet. Major topics include: Organization and program for operational safety; Occupational medicine; Construction and demolition; Material handling and storage; Hoisting and rigging; Explosives; Chemical hazards; Gas cylinders; Electrical; Boiler and pressure vessels; Industrial fire protection; Industrial hygiene; and Safety inspection checklist.

  16. Site Environmental Report for 2004. Volume 1, Environment, Health, and Safety Division

    SciTech Connect (OSTI)

    2005-09-30

    Each year, Ernest Orlando Lawrence Berkeley National Laboratory prepares an integrated report on its environmental programs to satisfy the requirements of United States Department of Energy Order 231.1A, Environment, Safety, and Health Reporting.1 The Site Environmental Report for 2004 summarizes Berkeley Labs environmental management performance, presents environmental monitoring results, and describes significant programs for calendar year 2004. (Throughout this report, Ernest Orlando Lawrence Berkeley National Laboratory is referred to as Berkeley Lab, the Laboratory, Lawrence Berkeley National Laboratory, and LBNL.) The report is separated into two volumes. Volume I contains an overview of the Laboratory, the status of environmental programs, and summarized results from surveillance and monitoring activities. Volume II contains individual data results from these activities. This year, the Site Environmental Report was distributed by releasing it on the Web from the Berkeley Lab Environmental Services Group (ESG) home page, which is located at http://www.lbl.gov/ehs/esg/. Many of the documents cited in this report also are accessible from the ESG Web page. CD and printed copies of this Site Environmental Report are available upon request.

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

    SciTech Connect (OSTI)

    Not Available

    1993-11-01

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

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

    SciTech Connect (OSTI)

    Not Available

    1993-05-01

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

  19. K Basin sludge packaging design criteria (PDC) and safety analysis report for packaging (SARP) approval plan

    SciTech Connect (OSTI)

    Brisbin, S.A.

    1996-03-06

    This document delineates the plan for preparation, review, and approval of the Packaging Design Crieteria for the K Basin Sludge Transportation System and the Associated on-site Safety Analysis Report for Packaging. The transportation system addressed in the subject documents will be used to transport sludge from the K Basins using bulk packaging.

  20. Independent Oversight Inspection of Environment, Safety, and Health Programs at the Pantex Plant, Technical Appendices, Volume II, February 2005

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy (DOE) Office of Independent Oversight and Performance Assurance (OA) conducted an inspection of environment, safety, and health (ES&H) programs at the DOE Pantex Plant during January and February 2005. The inspection was performed by the OA Office of Environment, Safety and Health Evaluations. OA reports to the Director of the Office of Security and Safety Performance Assurance, who reports directly to the Secretary of Energy. This volume of the report provides four technical appendices (C through F) containing detailed results of the OA review. Appendix C provides the results of the review of the application of the core functions of ISM for Pantex Plant work activities. Appendix D presents the results of the review of NNSA, PXSO, and BWXT feedback and continuous improvement processes and management systems. Appendix E presents the results of the review of essential safety system functionality, and Appendix F presents the results of the review of safety management of the selected focus areas.

  1. Criticality Safety Lessons Learned in a Deactivation and Decommissioning Environment [A Guide for Facility and Project Managers

    SciTech Connect (OSTI)

    NIRIDER, L.T.

    2003-08-06

    This document was designed as a reference and a primer for facility and project managers responsible for Deactivation and Decommissioning (D&D) processes in facilities containing significant inventories of fissionable materials. The document contains lessons learned and guidance for the development and management of criticality safety programs. It also contains information gleaned from occurrence reports, assessment reports, facility operations and management, NDA program reviews, criticality safety experts, and criticality safety evaluations. This information is designed to assist in the planning process and operational activities. Sufficient details are provided to allow the reader to understand the events, the lessons learned, and how to apply the information to present or planned D&D processes. Information is also provided on general lessons learned including criticality safety evaluations and criticality safety program requirements during D&D activities. The document also explores recent and past criticality accidents in operating facilities, and it extracts lessons learned pertinent to D&D activities. A reference section is included to provide additional information. This document does not address D&D lessons learned that are not pertinent to criticality safety.

  2. DOE-STD-1120-2005; Integration of Environment, Safety, and Health...

    Energy Savers [EERE]

    A-1 Appendix B Examples of Applying DOE-STD-1120 ... C-1 Appendix D Inactive Waste Site Criteria......Integrated safety management expectations are provided ...

  3. Safety

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

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

  4. Design Environment for Low-Amplitude Thermoacoustic Engines

    Energy Science and Technology Software Center (OSTI)

    2002-01-07

    DeltaE is a computer program that can preduct how a given thermoacoustic apparatus will perform, or can allow the user to design an apparatus to achieve desired performance. It is substantially menu-oriented. Input data can be modified or entered bia DeltaE's menu or using any text editor. Results can be examined via the menus, the operating systems text utilities, or any spreadsheet or graphics software.

  5. Hanford Site Environment Safety and Health (ES and H) FY 1999 and FY 2000 Execution Commitment Summary

    SciTech Connect (OSTI)

    REEP, I.E.

    1999-12-01

    All sites in the U.S. Department of Energy (DOE) Complex prepare this report annually for the DOE Office of Environment, Safety and Health (EH). The purpose of this report is to provide a summary of the previous and current year's Environment, Safety and Health (ES&H) execution commitments and the S&H resources that support these activities. The fiscal year (FY) 1999 and 2000 information (Sieracki 1999) and data contained in the ''Hanford Site Environment, Safety and Health Fiscal Year 2001 Budget-Risk Management Summary'' (RL 1999) were the basis for preparing this report. Fiscal year 2000 finding of Office of Environmental Management (EM) and Office of Nuclear Energy, Science and Technology (NE) activities is based on the President's budget of $1,065.1 million and $28.0 million, plus $2.7 million carryover finding, respectively, as of October 31, 1999. Any funding changes as a result of the Congressional appropriation process will be reflected in the Fiscal Year 2002 ES&H Budget-Risk Management Summary to be issued in May 2000. This report provides the end-of-year status of FY 1999 ES&H execution commitments, including actual S&H expenditures, and describes planned FY 2000 ES&H execution commitments and the S&H resources needed to support those activities. This requirement is included in the ES&H ''Guidance for FY200l Budget Formulations and Execution'' (DOE 1999).

  6. DOE Standard Integration Of Environment,Safety, and Health Into Facility Disposition Activities

    Broader source: Energy.gov [DOE]

    The original release of DOE-STD-1120-98 provided integrated safety management guidance for enhancing worker, public, and environmental protection during all facility disposition activities.

  7. Environment, Safety, and Health Policy for the Department of Energy Complex

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

    1995-06-15

    The Vision and Principles for the Protection of the Worker, Public, and Environment. Canceled by DOE P 450.7.

  8. Facility Safety Policy, Guidance & Reports | Department of Energy

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

    Facility Safety Policy, Guidance & Reports Facility Safety Policy, Guidance & Reports The Office of Nuclear Facility Safety Programs within the U.S. Department of Energy's (DOE) Environment, Health, Safety and Security organization, establishes nuclear safety requirements related to safety management programs that are essential to the safety of DOE nuclear facilities. In addition, establishes requirements for facility design and operation for facility-wide hazards that are not unique to

  9. MODULAR AND FULL SIZE SIMPLIFIED BOILING WATER REACTOR DESIGN WITH FULLY PASSIVE SAFETY SYSTEMS

    SciTech Connect (OSTI)

    M. Ishii; S. T. Revankar; T. Downar; Y. Xu, H. J. Yoon; D. Tinkler; U. S. Rohatgi

    2003-06-16

    OAK B204 The overall goal of this three-year research project was to develop a new scientific design of a compact modular 200 MWe and a full size 1200 MWe simplified boiling water reactors (SBWR). Specific objectives of this research were: (1) to perform scientific designs of the core neutronics and core thermal-hydraulics for a small capacity and full size simplified boiling water reactor, (2) to develop a passive safety system design, (3) improve and validate safety analysis code, (4) demonstrate experimentally and analytically all design functions of the safety systems for the design basis accidents (DBA) and (5) to develop the final scientific design of both SBWR systems, 200 MWe (SBWR-200) and 1200 MWe (SBWR-1200). The SBWR combines the advantages of design simplicity and completely passive safety systems. These advantages fit well within the objectives of NERI and the Department of Energy's focus on the development of Generation III and IV nuclear power. The 3-year research program was structured around seven tasks. Task 1 was to perform the preliminary thermal-hydraulic design. Task 2 was to perform the core neutronic design analysis. Task 3 was to perform a detailed scaling study and obtain corresponding PUMA conditions from an integral test. Task 4 was to perform integral tests and code evaluation for the DBA. Task 5 was to perform a safety analysis for the DBA. Task 6 was to perform a BWR stability analysis. Task 7 was to perform a final scientific design of the compact modular SBWR-200 and the full size SBWR-1200. A no cost extension for the third year was requested and the request was granted and all the project tasks were completed by April 2003. The design activities in tasks 1, 2, and 3 were completed as planned. The existing thermal-hydraulic information, core physics, and fuel lattice information was collected on the existing design of the simplified boiling water reactor. The thermal-hydraulic design were developed. Based on a detailed integral system scaling analysis, design parameters were obtained and designs of the compact modular 200 MWe SBWR and the full size 1200 MWe SBWR were developed. These reactors are provided with passive safety systems. A new passive vacuum breaker check valve was designed to replace the mechanical vacuum beaker check valve. The new vacuum breaker check valve was based on a hydrostatic head, and was fail safe. The performance of this new valve was evaluated both by the thermal-hydraulic code RELAP5 and by the experiments in a scaled SBWR facility, PUMA. In the core neutronic design a core depletion model was implemented to PARCS code. A lattice design for the SBWR fuel assemblies was performed. Design improvements were made to the neutronics/thermal-hydraulics models of SBWR-200 and SBWR-1200, and design analyses of these reactors were performed. The design base accident analysis and evaluation of all the passive safety systems were completed as scheduled in tasks 4 and 5. Initial conditions for the small break loss of coolant accidents (LOCA) and large break LOCA using REALP5 code were obtained. Small and large break LOCA tests were performed and the data was analyzed. An anticipated transient with scram was simulated using the RELAP5 code for SBWR-200. The transient considered was an accidental closure of the main steam isolation valve (MSIV), which was considered to be the most significant transient. The evaluation of the RELAP5 code against experimental data for SBWR-1200 was completed. In task 6, the instability analysis for the three SBWR designs (SBWR-1200, SBWR-600 and SBWR-200) were simulated for start-up transients and the results were similar. Neither the geysering instability, nor the loop type instability was predicted by RAMONA-4B in the startup simulation following the recommended procedure by GE. The density wave oscillation was not observed at all because the power level used in the simulation was not high enough. A study was made of the potential instabilities by imposing an unrealistically high power ramp in a short time period, as suggested by GE. RAMON

  10. Preliminary safety calculations to improve the design of Molten Salt Fast Reactor

    SciTech Connect (OSTI)

    Brovchenko, M.; Heuer, D.; Merle-Lucotte, E.; Allibert, M.; Capellan, N.; Ghetta, V.; Laureau, A.

    2012-07-01

    Molten salt reactors are liquid fuel reactors so that they are flexible in operation but very different in the safety approach from solid fuel reactors. This study bears on the specific concept named Molten Salt Fast Reactor (MSFR). Since this new nuclear technology is in development, safety is an essential point to be considered all along the R and D studies. This paper presents the first step of the safety approach: the systematic description of the MSFR, limited here to the main systems surrounding the core. This systematic description is the basis on which we will be able to devise accidental scenarios. Thanks to the negative reactivity feedback coefficient, most accidental scenarios lead to reactor shut down. Because of the decay heat generated in the fuel salt, it must be cooled. After the description of the tools developed to calculate the residual heat, the different contributions are discussed in this study. The decay heat of fission products in the MSFR is evaluated to be low (3% of nominal power), mainly due to the reprocessing that transfers the fission products to the gas reprocessing unit. As a result, the contribution of the actinides is significant (0.5% of nominal power). The unprotected loss of heat sink transients are studied in this paper. It appears that slow transients are favorable (> 1 min) to minimize the temperature increase of the fuel salt. This work will be the basis of further safety studies as well as an essential parameter for the design of the draining system. (authors)

  11. DELTAE. Design Environment for Low-Amplitude Thermoacoustic Engines

    SciTech Connect (OSTI)

    Ward, W.C.

    1993-10-10

    In thermoacoustic engines and refrigerators, and in many simple acoustic systems, a one dimensional wave equation determines the spatial dependence of the acoustic pressure and velocity. DELTAE numerically integrates such wave equations in the acoustic approximation, in gases or liquids, in user-defined geometries. Boundary conditions can include conventional acoustic boundary conditions of geometry and impedance, as well as temperature and thermal power in thermoacoustic systems. DELTAE can be used easily for apparatus ranging from simple duct networks and resonators to thermoacoustic engines refrigerators and combinations thereof. It can predict how a given apparatus will perform, or can allow the user to design an apparatus to achieve desired performance. DELTAE views systems as a series of segments; twenty segment types are supported. The purely acoustic segments include ducts and cones, and lumped impedances including compliances, series impedances, and endcaps. Electroacoustics tranducer segments can be defined using either frequency-independent coefficients or the conventional parameters of loudspeaker-style drivers: mass, spring constant, magnetic field strength, etc. Tranducers can be current driven, voltage driven, or connected to an electrical load impedance. Thermoacoustic segment geometries include parallel plates, circular and rectangular pores, and pin arrays. Side branches can be defined with fixed impedances, frequency-dependent radiation impedances, or as an auxiliary series of segments of any types. The user can select working fluids from among air, helium, neon, argon, hydrogen, deuterium, carbon dioxide, nitrogen, helium-argon mixtures, helium-xenon mixtures, liquid sodium, and eutectic sodium-potassium. Additional fluids and solids can be defined by the user.

  12. DELTAE. Design Environment for Low-Amplitude Thermoacoustic Engines

    SciTech Connect (OSTI)

    Ward, W.C.; Swift, G.W.

    1993-10-01

    In thermoacoustic engines and refrigerators, and in many simple acoustic systems, a one dimensional wave equation determines the spatial dependence of the acoustic pressure and velocity. DELTAE numerically integrates such wave equations in the acoustic approximation, in gases or liquids, in user-defined geometries. Boundary conditions can include conventional acoustic boundary conditions of geometry and impedance, as well as temperature and thermal power in thermoacoustic systems. DELTAE can be used easily for apparatus ranging from simple duct networks and resonators to thermoacoustic engines refrigerators and combinations thereof. It can predict how a given apparatus will perform, or can allow the user to design an apparatus to achieve desired performance. DELTAE views systems as a series of segments; twenty segment types are supported. The purely acoustic segments include ducts and cones, and lumped impedances including compliances, series impedances, and endcaps. Electroacoustics tranducer segments can be defined using either frequency-independent coefficients or the conventional parameters of loudspeaker-style drivers: mass, spring constant, magnetic field strength, etc. Tranducers can be current driven, voltage driven, or connected to an electrical load impedance. Thermoacoustic segment geometries include parallel plates, circular and rectangular pores, and pin arrays. Side branches can be defined with fixed impedances, frequency-dependent radiation impedances, or as an auxiliary series of segments of any types. The user can select working fluids from among air, helium, neon, argon, hydrogen, deuterium, carbon dioxide, nitrogen, helium-argon mixtures, helium-xenon mixtures, liquid sodium, and eutectic sodium-potassium. Additional fluids and solids can be defined by the user.

  13. DELTAE+. Design Environment for Low-Amplitude Thermoacoustic Engines

    SciTech Connect (OSTI)

    Ward, W.C; Swift, G.W.

    1993-10-01

    In thermoacoustic engines and refrigerators, and in many simple acoustic systems, a one dimensional wave equation determines the spatial dependence of the acoustic pressure and velocity. DELTAE numerically integrates such wave equations in the acoustic approximation, in gases or liquids, in user-defined geometries. Boundary conditions can include conventional acoustic boundary conditions of geometry and impedance, as well as temperature and thermal power in thermoacoustic systems. DELTAE can be used easily for apparatus ranging from simple duct networks and resonators to thermoacoustic engines refrigerators and combinations thereof. It can predict how a given apparatus will perform, or can allow the user to design an apparatus to achieve desired performance. DELTAE views systems as a series of segments; twenty segment types are supported. The purely acoustic segments include ducts and cones, and lumped impedances including compliances, series impedances, and endcaps. Electroacoustics tranducer segments can be defined using either frequency-independent coefficients or the conventional parameters of loudspeaker-style drivers: mass, spring constant, magnetic field strength, etc. Tranducers can be current driven, voltage driven, or connected to an electrical load impedance. Thermoacoustic segment geometries include parallel plates, circular and rectangular pores, and pin arrays. Side branches can be defined with fixed impedances, frequency-dependent radiation impedances, or as an auxiliary series of segments of any types. The user can select working fluids from among air, helium, neon, argon, hydrogen, deuterium, carbon dioxide, nitrogen, helium-argon mixtures, helium-xenon mixtures, liquid sodium, and eutectic sodium-potassium. Additional fluids and solids can be defined by the user.

  14. DOE-STD-1120-2005; Integration of Environment Safety and Health into Facility Disposition Activities

    Office of Environmental Management (EM)

    7-92 DOE-STD-1027-92 December 12, 1997 Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports Change Notice No. 1 (September 1997) The purpose of this DOE Standard is to establish guidance for the preparation and review of hazard categorization and accident analyses techniques as required in DOE Order 5480.23, Nuclear Safety Analysis Reports. PDF icon DOE-STD-1027-92, Hazard Categorization and Accident Analysis Techniques For

  15. Inspection of Environment, Safety, and Health and Emergency Management at the Oak Ridge Operations Office and East Tennessee Technology Park, Summary Report, May 2003

    Broader source: Energy.gov [DOE]

    This report provides the results of an inspection of environment, safety, and health and emergency management programs at the U.S. Department of Energy's (DOE) East Tennessee Technology Park (ETTP).

  16. Preliminary Safety Design Report for Remote Handled Low-Level Waste Disposal Facility

    SciTech Connect (OSTI)

    Timothy Solack; Carol Mason

    2012-03-01

    A new onsite, remote-handled low-level waste disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled low-level waste disposal for remote-handled low-level waste from the Idaho National Laboratory and for nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled low-level waste in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This preliminary safety design report supports the design of a proposed onsite remote-handled low-level waste disposal facility by providing an initial nuclear facility hazard categorization, by discussing site characteristics that impact accident analysis, by providing the facility and process information necessary to support the hazard analysis, by identifying and evaluating potential hazards for processes associated with onsite handling and disposal of remote-handled low-level waste, and by discussing the need for safety features that will become part of the facility design.

  17. Conceptual Safety Design Report for the Remote Handled Low-Level Waste Disposal Facility

    SciTech Connect (OSTI)

    Boyd D. Christensen

    2010-02-01

    A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal for remote-handled LLW from the Idaho National Laboratory and for spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This conceptual safety design report supports the design of a proposed onsite remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization, by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW, by evaluating consequences of postulated accidents, and by discussing the need for safety features that will become part of the facility design.

  18. Conceptual Safety Design Report for the Remote Handled Low-Level Waste Disposal Facility

    SciTech Connect (OSTI)

    Boyd D. Christensen

    2010-05-01

    A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal for remote-handled LLW from the Idaho National Laboratory and for spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This conceptual safety design report supports the design of a proposed onsite remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization, by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW, by evaluating consequences of postulated accidents, and by discussing the need for safety features that will become part of the facility design.

  19. Office of Environment, Safety and Health Evaluations Appraisal Process Guide, July 29, 2009

    Broader source: Energy.gov [DOE]

    This guide is a subordinate document to the Independent Oversight Appraisal Process Protocols. While the protocols provide general guidance common to all appraisal activities, this document provides additional detail and guidance regarding procedures and methods specific to ES&H appraisals conducted by Independent Oversight. DOE Order 470.2B is an important reference document that defines program requirements and, in particular, defines processes for sites to respond to identified vulnerabilities and to develop corrective action plans. The processes described in this guide are used for all ES&H appraisals, including periodic inspections, special reviews, targeted nuclear safety inspections, or other appraisal activities, because the reviews differ only in detail.

  20. Assessment of the safety of spent fuel transportation in urban environs

    SciTech Connect (OSTI)

    Sandoval, R.P.; Weber, J.P.; Levine, H.S.; Romig, A.D.; Johnson, J.D.; Luna, R.E.; Newton, G.J.; Wong, B.A.; Marshall, R.W. Jr.; Alvarez, J.L.

    1983-06-01

    The results of a program to provide an experimental data base for estimating the radiological consequences from a hypothetical sabotage attack on a light-water-reactor spent fuel shipping cask in a densely populated area are presented. The results of subscale and full-scale experiments in conjunction with an analytical modeling study are described. The experimental data were used as input to a reactor-safety consequence model to predict radiological health consequences resulting from a hypothetical sabotage attack on a spent-fuel shipping cask in the Manhattan borough of New York City. The results of these calculations are presented.

  1. Inspection of Environment, Safety, and Health Management at the Waste Isolation Pilot Plant- Volume I, August 2002

    Office of Energy Efficiency and Renewable Energy (EERE)

    The Secretary of Energy’s Office of Independent Oversight and Performance Assurance (OA) conducted an inspection of environment, safety, and health (ES&H) and emergency management programs at the Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) in July and August 2002. The inspection was performed as a joint effort by the OA Office of Environment, Safety and Health Evaluations and the Office of Emergency Management Oversight. This volume discusses the results of the review of the WIPP ES&H programs. The results of the review of the WIPP emergency management program are discussed in Volume II of this report, and the combined results are discussed in a summary report. As discussed throughout this report, the ISM program at WIPP is generally effective. Although improvements are warranted in some areas, the current programs have contributed to overall effective ES&H performance and a good safety record at WIPP. Section 2 of this volume provides an overall discussion of the results of the review of the WIPP ES&H programs, including positive aspects and weaknesses. Section 3 provides OA’s conclusions regarding the overall effectiveness of CBFO and WTS management of the ES&H programs. Section 4 presents the ratings assigned as a result of this review. Appendix A provides supplemental information, including team composition. Appendix B identifies the specific finding that requires corrective action and follow-up. Appendix C presents the results of the review of selected guiding principles of ISM. Appendix D presents the results of the review of the CBFO and WTS feedback and continuous improvement processes. The results of the review of the application of the core functions of ISM for the selected WIPP activities are discussed in Appendix E.

  2. Inspection of Environment, Safety, and Health Management at the Argonne National Laboratory- East, Volume I, May 2002

    Broader source: Energy.gov [DOE]

    The Secretary of Energy’s Office of Independent Oversight and Performance Assurance (OA) conducted an inspection of environment, safety, and health (ES&H) programs and emergency management programs at the U. S. Department of Energy (DOE) Argonne National Laboratory (ANL) in April and May 2002. The inspection was performed as a joint effort by the OA Office of Environment, Safety and Health Evaluations and the Office of Emergency Management Oversight. This volume discusses the results of the review of ANL ES&H programs. The results of the review of the ANL emergency management programs are discussed in Volume II of this report and the combined results are discussed in a summary report. As discussed in this report, some aspects of ISM are effectively implemented at ANL, including institutional roles and responsibilities, training and qualification programs, and processes for incorporating ES&H needs into the planning and budgeting processes. In addition, CH/AAO and ANL have been effective in establishing rigorous processes for reviewing experiment safety. However, performance weaknesses are evident in several areas, including work planning and control processes, radiation protection, and some aspects of management of the AGHCF (including nuclear safety requirements). Weaknesses in management systems, such as CH/AAO and ANL feedback and continuous improvement systems and requirements management systems, contribute to the observed performance deficiencies. Section 2 of this volume provides an overall discussion of the results of the review of the ANL ISM program, including positive aspects, findings, and other items requiring management attention. Section 3 provides OA’s conclusions regarding the overall effectiveness of CH and ANL management of the ES&H programs. Section 4 presents the ratings assigned as a result of this review. Appendix A provides supplemental information, including team member composition. Appendix B identifies the specific findings that require corrective actions and follow-up. Appendix C presents the results of the review of the guiding principles of ISM. Appendix D presents the results of the review of the CH and ANL feedback and continuous improvement processes. The results of the review of the application of the core functions of ISM at the selected ANL facilities are discussed in Appendix E.

  3. Environment

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

    Environment Environment Events Learn about our science, listen to lectures on environment and climate change at the Bradbury Science Museum or at Cafe Scientific events in your community. Oct 14 Wed 4:00 PM Laboratory's Electronic Public Reading room training J. Robert Oppenheimer Study Center, Room JRO 1&2 - West Jemez Road at Casa Grande The Department of Energy (DOE) and the Los Alamos National Security, LLC (LANS), are holding training on the contents and use of the Los Alamos National

  4. Environment

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

    Video News Room » News Releases » Environment /newsroom/_assets/images/envi-icon.png Earth, Environment Climate impacts, including global temperatures, drought and forest fires as well as Ocean and Sea Ice Modeling Health Space Computing Energy Environment Materials Science Technology The Lab Wildfire fuel being burned in the fire laboratory as the aerosols from the top are being sucked into inlets and sampled at the Missoula Fire Sciences Laboratory in Missoula, Montana by Los Alamos and

  5. Environment

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

    Environment Environment A repository for images showing environmental cleanup and protection efforts around the Lab. News Releases Science Briefs Photos Picture of the Week Publications Social Media Videos Fact Sheets PHOTOS BY TOPIC Careers Community Visitors Environment History Science The Lab Click thumbnails to enlarge. Photos arranged by most recent first, horizontal formats before vertical. See Flickr for more sizes and details. Workers sample contents of LANL's Material Disposal Area B

  6. Major results from safety-related integral effect tests with VISTA-ITL for the SMART design

    SciTech Connect (OSTI)

    Park, H. S.; Min, B. Y.; Shin, Y. C.; Yi, S. J.

    2012-07-01

    A series of integral effect tests (IETs) was performed by the Korea Atomic Energy Research Inst. (KAERI) using the VISTA integral test loop (VISTA-ITL) as a small-scale IET program. Among them this paper presents major results acquired from the safety-related IETs with the VISTA-ITL facility for the SMART design. Three small-break loss-of-coolant accident (SBLOCA) tests of safety injection system (SIS) line break, shutdown cooling system (SCS) line break and pressurizer safety valve (PSV) line break were successfully performed and the transient characteristics of a complete loss of flowrate (CLOF) was simulated properly with the VISTA-ITL facility. (authors)

  7. Inventory of Federal energy-related environment and safety research for FY 1979. Volume II. Project listings and indexes

    SciTech Connect (OSTI)

    1980-12-01

    This volume contains summaries of FY 1979 government-sponsored environment and safety research related to energy arranged by log number, which groups the projects by reporting agency. The log number is a unique number assigned to each project from a block of numbers set aside for each contributing agency. Information elements included in the summary listings are project title, principal investigators, research organization, project number, contract number, supporting organization, funding level, related energy sources with numbers indicating percentages of effort devoted to each, and R and D categories. A brief description of each project is given, and this is followed by subject index terms that were assigned for computer searching and for generating the printed subject index in the back of this volume.

  8. Independent Oversight Inspection of Environment, Safety, and Health Management at the Lawrence Livermore National Laboratory, Technical Appendices, Volume II, December 2004

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy (DOE) Office of Independent Oversight and Performance Assurance (OA), within the Office of Security and Safety Performance Assurance (SSA), conducted an inspection of environment, safety, and health (ES&H) at the DOE Lawrence Livermore National Laboratory (LLNL) during October and November 2004. The inspection was performed by the OA Office of Environment, Safety and Health Evaluations. Volume II of this report provides four technical appendices (C through F) containing detailed results of the OA review. Appendix C provides the results of the review of the application of the core functions of ISM for LLNL work activities. Appendix D presents the results of the review of NNSA, LSO, and contractor feedback and continuous improvement processes. Appendix E presents the results of the review of Plutonium Building essential safety system functionality, and Appendix F presents the results of the review of management of the selected focus areas.

  9. Pacific Northwest Laboratory annual report for 1980 to the DOE Assistant Secretary for Environment. Part 5. Environmental assessment, control, health and safety

    SciTech Connect (OSTI)

    Baalman, R.W.; Hays, I.D.

    1981-02-01

    Pacific Northwest Laboratory's (PNL) 1980 annual report to the DOE Assistant Secretary for Environment describes research in environment, health, and safety conducted during fiscal year 1980. Part 5 includes technology assessments for natural gas, enhanced oil recovery, oil shale, uranium mining, magnetic fusion energy, solar energy, uranium enrichment and industrial energy utilization; regional analysis studies of environmental transport and community impacts; environmental and safety engineering for LNG, oil spills, LPG, shale oil waste waters, geothermal liquid waste disposal, compressed air energy storage, and nuclear/fusion fuel cycles; operational and environmental safety studies of decommissioning, environmental monitoring, personnel dosimetry, and analysis of criticality safety; health physics studies; and epidemiological studies. Also included are an author index, organization of PNL charts and distribution lists of the annual report, along with lists of presentations and publications. (DLS)

  10. Environment

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

    Lab has a strategy to clean up the past, control current operations, and move toward a sustainable future in which waste is minimized and other effects on the environment are...

  11. The Gas-Cooled Fast Reactor: Report on Safety System Design for Decay Heat Removal

    SciTech Connect (OSTI)

    K. D. Weaver; T. Marshall; T. Y. C. Wei; E. E. Feldman; M. J. Driscoll; H. Ludewig

    2003-09-01

    The gas-cooled fast reactor (GFR) was chosen as one of the Generation IV nuclear reactor systems to be developed based on its excellent potential for sustainability through reduction of the volume and radiotoxicity of both its own fuel and other spent nuclear fuel, and for extending/utilizing uranium resources orders of magnitude beyond what the current open fuel cycle can realize. In addition, energy conversion at high thermal efficiency is possible with the current designs being considered, thus increasing the economic benefit of the GFR. However, research and development challenges include the ability to use passive decay heat removal systems during accident conditions, survivability of fuels and in-core materials under extreme temperatures and radiation, and economical and efficient fuel cycle processes. This report addresses/discusses the decay heat removal options available to the GFR, and the current solutions. While it is possible to design a GFR with complete passive safety (i.e., reliance solely on conductive and radiative heat transfer for decay heat removal), it has been shown that the low power density results in unacceptable fuel cycle costs for the GFR. However, increasing power density results in higher decay heat rates, and the attendant temperature increase in the fuel and core. Use of active movers, or blowers/fans, is possible during accident conditions, which only requires 3% of nominal flow to remove the decay heat. Unfortunately, this requires reliance on active systems. In order to incorporate passive systems, innovative designs have been studied, and a mix of passive and active systems appears to meet the requirements for decay heat removal during accident conditions.

  12. Facility Safety

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

    2000-11-20

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

  13. Facility Safety

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

    2005-12-22

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

  14. Facility Safety

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

    2012-12-04

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

  15. Initial Requirements for Gas-Cooled Fast Reactor (GFR) System Design, Performance, and Safety Analysis Models

    SciTech Connect (OSTI)

    Kevan D. Weaver; Thomas Y. C. Wei

    2004-08-01

    The gas-cooled fast reactor (GFR) was chosen as one of the Generation IV nuclear reactor systems to be developed based on its excellent potential for sustainability through reduction of the volume and radio toxicity of both its own fuel and other spent nuclear fuel, and for extending/utilizing uranium resources orders of magnitude beyond what the current open fuel cycle can realize. In addition, energy conversion at high thermal efficiency is possible with the current designs being considered, thus increasing the economic benefit of the GFR. However, research and development challenges include the ability to use passive decay heat removal systems during accident conditions, survivability of fuels and in-core materials under extreme temperatures and radiation, and economical and efficient fuel cycle processes. Nevertheless, the GFR was chosen as one of only six Generation IV systems to be pursued based on its ability to meet the Generation IV goals in sustainability, economics, safety and reliability, proliferation resistance and physical protection.

  16. Final safety evaluation report related to the certification of the advanced boiling water reactor design. Volume 1: Main report

    SciTech Connect (OSTI)

    Not Available

    1994-07-01

    This safety evaluation report (SER) documents the technical review of the US Advanced Boiling Water Reactor (ABWR) standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the ABWR design was initially submitted by the General Electric Company, now GE Nuclear Energy (GE), in accordance with the procedures of Appendix O of Part 50 of Title 10 of the Code of Federal Regulations (10 CFR Part 50). Later GE requested that its application be considered as an application for design approval and subsequent design certification pursuant to 10 CFR {section} 52.45. The ABWR is a single-cycle, forced-circulation, boiling water reactor (BWR) with a rated power of 3,926 megawatts thermal (MWt) and a design power of 4,005 MWt. To the extent feasible and appropriate, the staff relied on earlier reviews for those ABWR design features that are substantially the same as those previously considered. Unique features of the ABWR design include internal recirculation pumps, fine-motion control rod drives, microprocessor-based digital logic and control systems, and digital safety systems. On the basis of its evaluation and independent analyses, the NRC staff concludes that, subject to satisfactory resolution of the confirmatory items identified in Section 1.8 of this SER, GE`s application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the US ABWR standard design.

  17. Final safety evaluation report related to the certification of the advanced boiling water reactor design. Volume 2: Appendices

    SciTech Connect (OSTI)

    Not Available

    1994-07-01

    This safety evaluation report (SER) documents the technical review of the US Advanced Boiling Water Reactor (ABWR) standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the ABWR design was initially submitted by the General Electric Company, now GE Nuclear Energy (GE), in accordance with the procedures of Appendix O of Part 50 of Title 10 of the code of Federal Regulations (10 CFR Part 50). Later GE requested that its application be considered as an application for design approval and subsequent design certification pursuant to 10 CFR {section} 52.45. The ABWR is a single-cycle, forced-circulation, boiling water reactor (BWR) with a rated power of 3,926 megawatts thermal (MWt) and a design power of 4,005 MWt. To the extent feasible and appropriate, the staff relied on earlier reviews for those ABWR design features that are substantially the same as those previously considered. Unique features of the ABWR design include internal recirculation pumps, fine-motion control rod drives, microprocessor-based digital logic and control systems, and digital safety systems. On the basis of its evaluation and independent analyses, the NRC staff concludes that, subject to satisfactory resolution of the confirmatory items identified in Section 1.8 of this SER, GE`s application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the US ABWR standard design.

  18. Integrated Safety Management Policy

    Broader source: Energy.gov [DOE]

    This Integrated Safety Management (ISM) System Description (ISMSD) defines how the U.S. Department of Energy (DOE) Office of Environmental Management (EM) integrates environment, safety, and health...

  19. Electrical Safety

    Energy Savers [EERE]

    ... Electrical Design Criteria ... of High-Voltage and Low-Current ... as a higher level of authority. Per the Integrated Safety Management model, ...

  20. Experimental Study and Computational Simulations of Key Pebble Bed Thermo-mechanics Issues for Design and Safety

    SciTech Connect (OSTI)

    Tokuhiro, Akira; Potirniche, Gabriel; Cogliati, Joshua; Ougouag, Abderrafi

    2014-07-08

    An experimental and computational study, consisting of modeling and simulation (M&S), of key thermal-mechanical issues affecting the design and safety of pebble-bed (PB) reactors was conducted. The objective was to broaden understanding and experimentally validate thermal-mechanic phenomena of nuclear grade graphite, specifically, spheres in frictional contact as anticipated in the bed under reactor relevant pressures and temperatures. The contact generates graphite dust particulates that can subsequently be transported into the flowing gaseous coolent. Under postulated depressurization transients and with the potential for leaked fission products to be adsorbed onto graphite 'dust', there is the potential for fission products to escape from the primary volume. This is a design safety concern. Furthermore, earlier safety assessment identified the distinct possibility for the dispersed dust to combust in contact with air if sufficient conditions are met. Both of these phenomena were noted as important to design review and containing uncertainty to warrant study. The team designed and conducted two separate effects tests to study and benchmark the potential dust-generation rate, as well as study the conditions under which a dust explosion may occure in a standardized, instrumented explosion chamber.

  1. Facility Safety

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

    2012-12-04

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

  2. Facility Safety

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

    2005-12-22

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

  3. Facility Safety

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

    1995-10-13

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

  4. Designing for thermal comfort in combined chilled ceiling/displacement ventilation environments

    SciTech Connect (OSTI)

    Loveday, D.L.; Hodder, S.G.; Jeal, L.D.; Parsons, K.C.; Taki, A.H.

    1998-10-01

    This paper presents general guidance on designing for thermal comfort in combined chilled ceiling/displacement ventilation environments. Thermal comfort measurements involving 184 human subjects were carried out in a laboratory-based test room, constructed to resemble a normal office and equipped with a combined chilled ceiling and wall-mounted displacement ventilation system. Room characterization tests revealed that the chilled ceiling has a detrimental effect upon displacement flow, suppressing the stratified boundary layer at ceiling temperatures of 18 C--21 C and destroying displacement flow all together at low ceiling temperatures (14 C--16 C). Reduction in ceiling temperature was found to increase local air velocities at heights of 0.1 m and 1.1 m above the floor, showing further evidence of mixing, though there was an insignificant effect on local discomfort due to draft, as measured by subjective responses and by draft rating assessment. ISO Standard 7730 (1995) is shown to be valid, without modification, for predicting the thermal comfort of sedentary occupants performing office work in combined chilled ceiling/displacement ventilation environments. The vertical radiant asymmetry induced by a cooled ceiling does not significantly affect the thermal comfort of desk-seated occupants; this, together with relative humidity, is shown to require no additional comfort-related design limitations beyond those already in the literature and beyond the prevention of ceiling surface condensation.

  5. Experiment Safety Requirements

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

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

  6. Final safety evaluation report related to the certification of the Advanced Boiling Water Reactor design. Supplement 1

    SciTech Connect (OSTI)

    1997-05-01

    This report supplements the final safety evaluation report (FSER) for the US Advanced Boiling Water Reactor (ABWR) standard design. The FSER was issued by the US Nuclear Regulatory Commission (NRC) staff as NUREG-1503 in July 1994 to document the NRC staff`s review of the US ABWR design. The US ABWR design was submitted by GE Nuclear Energy (GE) in accordance with the procedures of Subpart B to Part 52 of Title 10 of the Code of Federal Regulations. This supplement documents the NRC staff`s review of the changes to the US ABWR design documentation since the issuance of the FSER. GE made these changes primarily as a result of first-of-a-kind-engineering (FOAKE) and as a result of the design certification rulemaking for the ABWR design. On the basis of its evaluations, the NRC staff concludes that the confirmatory issues in NUREG-1503 are resolved, that the changes to the ABWR design documentation are acceptable, and that GE`s application for design certification meets the requirements of Subpart B to 10 CFR Part 52 that are applicable and technically relevant to the US ABWR design.

  7. Safety provisions for UF{sub 6} handling in the design of a new UF{sub 6} conversion plant

    SciTech Connect (OSTI)

    Bannister, S.P.

    1991-12-31

    British Nuclear Fuels plc (BNFL) Fuel Division is currently undertaking the final design and construction of a new UF{sub 6} conversion plant at its production site at Springfields near Preston in the north of England. The Company has gained much experience in the handling of UF{sub 6} during operation of plants on site since 1961. The major hazard occurs during the liquefication cycle and the basis of the maximum credible incident scenario adopted for safety assessment and design purposes is discussed. This paper considers the design features which have been incorporated in the new plant to counter the hazards presented by the presence of UF{sub 6} in gaseous and liquid form and explains current thinking on operational procedures in areas of potential risk such as cylinder filling. The plant emergency response philosophy and systems are described and specific design provisions which have been included to satisfy the UK regulatory bodies are outlined in some detail.

  8. Environmental Restoration Disposal Facility (Project W-296) Safety Assessment

    SciTech Connect (OSTI)

    Armstrong, D.L.

    1994-08-01

    This Safety Assessment is based on information derived from the Conceptual Design Report for the Environmental Restoration Disposal Facility (DOE/RL 1994) and ancillary documentation developed during the conceptual design phase of Project W-296. The Safety Assessment has been prepared to support the Solid Waste Burial Ground Interim Safety Basis document. The purpose of the Safety Assessment is to provide an evaluation of the design to determine if the process, as proposed, will comply with US Department of Energy (DOE) Limits for radioactive and hazardous material exposures and be acceptable from an overall health and safety standpoint. The evaluation considered affects on the worker, onsite personnel, the public, and the environment.

  9. Final safety evaluation report related to the certification of the System 80+ design: Docket Number 52-002. Supplement 1

    SciTech Connect (OSTI)

    1997-05-01

    This report supplements the final safety evaluation report (FSER) for the System 80+ standard design. The FSER was issued by the US Nuclear Regulatory Commission (NRC) staff as NUREG-1462 in August 1994 to document the NRC staff`s review of the System 80+ design. The System 80+ design was submitted by Asea Brown Boveri-Combustion Engineering (ABB-CE), in accordance with the procedures of Subpart B to Part 52 of Title 10 of the Code of Federal Regulations. This supplement documents the NRC staff`s review of the changes to the System 80+ design documentation since the issuance of the FSER. ABB-CE made these changes as a result of its review of the System 80+ design details. The NRC staff concludes that the changes to the System 80+ design documentation are acceptable, and that ABB-CE`s application for design certification meets the requirements of Subpart B to 10 CFR Part 52 that are applicable and technically relevant to the System 80+ design.

  10. SOLERAS - Solar Controlled Environment Agriculture Project. Final report, Volume 4. Saudi Engineering Solar Energy Applications System Design Study

    SciTech Connect (OSTI)

    Not Available

    1985-01-01

    Literature summarizing a study on the Saudi Arabian solar controlled environment agriculture system is presented. Specifications and performance requirements for the system components are revealed. Detailed performance and cost analyses are used to determine the optimum design. A preliminary design of an engineering field test is included. Some weather data are provided for Riyadh, Saudi Arabia. (BCS)

  11. Safety Basis Report

    SciTech Connect (OSTI)

    R.J. Garrett

    2002-01-14

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

  12. CRAD, Assessment Criteria and Guidelines for Determining the Adequacy of Software Used in the Safety Analysis and Design of Defense Nuclear Facilities

    Broader source: Energy.gov [DOE]

    These guidelines and criteria provide a consistent overall framework for assessment of the processes that are currently in place to ensure that the software being used in the safety analysis and design of the SSCs in defense nuclear facilities is adequate. These reviews will be conducted only on software that is currently in use, not on software that was previously used as part of a safety analysis and design process.

  13. Improvement design study on steam generator of MHR-50/100 aiming higher safety level after water ingress accident

    SciTech Connect (OSTI)

    Oyama, S.; Minatsuki, I.; Shimizu, K.

    2012-07-01

    Mitsubishi Heavy Industries, Ltd. (MHI) has been studying on MHI original High Temperature Gas cooled Reactor (HTGR), namely MHR-50/100, for commercialization with supported by JAEA. In the heat transfer system, steam generator (SG) is one of the most important components because it should be imposed a function of heat transfer from reactor power to steam turbine system and maintaining a nuclear grade boundary. Then we especially focused an effort of a design study on the SG having robustness against water ingress accident based on our design experience of PWR, FBR and HTGR. In this study, we carried out a sensitivity analysis from the view point of economic and plant efficiency. As a result, the SG design parameter of helium inlet/outlet temperature of 750 deg. C/300 deg. C, a side-by-side layout and one unit of SG attached to a reactor were selected. In the next, a design improvement of SG was carried out from the view point of securing the level of inherent safety without reliance on active steam dump system during water ingress accident considering the situation of the Fukushima nuclear power plant disaster on March 11, 2011. Finally, according to above basic design requirement to SG, we performed a conceptual design on adapting themes of SG structure improvement. (authors)

  14. Los Alamos national Laboratory overview of the SAVY-4000 design: meeting the challenge for worker safety

    SciTech Connect (OSTI)

    Stone, Timothy Amos

    2012-06-12

    Incidents involving release of nuclear materials stored in containers of convenience such as food pack cans, slip lid taped cans, paint cans, etc. has resulted in defense board concerns over the lack of prescriptive performance requirements for interim storage of nuclear materials. Los Alamos National Laboratory (LANL) has shared in these incidents and in response proactively moved into developing a performance based storage container design, the SAVY-4000. The SAVY-4000 is the first vented general use nuclear material container demonstrated to meet the requirements of DOE M 441.1-1, Nuclear Material Packaging Manual. The SAVY-4000 is an innovative and creative design demonstrated by the fact that it can be opened and closed in a few seconds without torque wrenches or other tools; has a built-in, fire-rated filter that prevents the build-up of hydrogen gas, yet retains 99.97% of plutonium particulates, and prevents release of material even in a 12 foot drop. Finally, it has been tested to 500C for 2 hours, and will reduce the risk to the public in the event of an earthquake/fire scenario. This will allow major nuclear facilities to credit the container towards source term Material at Risk (MAR) reduction. The container was approved for nuclear material storage in theTA-55 Plutonium Facility on March 15, 2011, and the first order of 79 containers was received at LANL on March 21, 2011. The first four SAVY-4000 containers were packaged with plutonium on August 2, 2011. Key aspects ofthe SAVY-4000 vented storage container design will be discussed which include design qualification and testing, implementation plan development and status, risk ranking methodology for re-packaging, in use implementation with interface to LANMAS, surveillance strategy, the design life extension program as enhanced by surveillance activities and production status with the intent to extend well beyond the current five year design life.

  15. Corporate Analysis of DOE Safety Performance | Department of...

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

    Current Safety Performance Trends The Office of Environment, Health, Safety and Security, ... Strategic Safety Goals Occupational Safety Performance Occurrence Reporting Trends For ...

  16. Two new design tools maximize safety and efficiency for coiled tubing pumping treatments

    SciTech Connect (OSTI)

    Gary, S.C.; Walton, I.C.; Gu, H.

    1995-10-01

    This paper describes the use of two new computer tools to assist the engineer in the design and evaluation of coiled tubing (CT) pumping treatments. Sand fill cleanouts and nitrogen kickoffs continue to comprise the majority of the operations performed by CT; however, the ability to design and evaluate jobs of this type has been limited for many years to simple steady-state calculations and general rules of thumb, both strictly applicable to vertical wells. Using these tools and an engineering design methodology, these treatments can be performed in the most efficient manner possible. The tools optimize the fluids, rates and penetration schedules by considering the effect of deviation on particle transport, reservoir influx or leakoff or both, mixing of gases in the wellbore, and other aspects of the operation. Additionally, by optimizing the required movement of the CT, pipe fatigue can be held to a minimum, providing safer and more cost-effective treatments. Examples that use these tools to design CT treatments are presented.

  17. ORNL necessary and sufficient standards for environment, safety, and health. Final report of the Identification Team for other industrial, radiological, and non-radiological hazard facilities

    SciTech Connect (OSTI)

    1998-07-01

    This Necessary and Sufficient (N and S) set of standards is for Other Industrial, Radiological, and Non-Radiological Hazard Facilities at Oak Ridge National Laboratory (ORNL). These facility classifications are based on a laboratory-wide approach to classify facilities by hazard category. An analysis of the hazards associated with the facilities at ORNL was conducted in 1993. To identify standards appropriate for these Other Industrial, Radiological, and Non-Radiological Hazard Facilities, the activities conducted in these facilities were assessed, and the hazards associated with the activities were identified. A preliminary hazards list was distributed to all ORNL organizations. The hazards identified in prior hazard analyses are contained in the list, and a category of other was provided in each general hazard area. A workshop to assist organizations in properly completing the list was held. Completed hazard screening lists were compiled for each ORNL division, and a master list was compiled for all Other Industrial, Radiological Hazard, and Non-Radiological facilities and activities. The master list was compared against the results of prior hazard analyses by research and development and environment, safety, and health personnel to ensure completeness. This list, which served as a basis for identifying applicable environment, safety, and health standards, appears in Appendix A.

  18. Experiment Safety Requirements

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

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

  19. Computer analyses for the design, operation and safety of new isotope production reactors: A technology status review

    SciTech Connect (OSTI)

    Wulff, W.

    1990-01-01

    A review is presented on the currently available technologies for nuclear reactor analyses by computer. The important distinction is made between traditional computer calculation and advanced computer simulation. Simulation needs are defined to support the design, operation, maintenance and safety of isotope production reactors. Existing methods of computer analyses are categorized in accordance with the type of computer involved in their execution: micro, mini, mainframe and supercomputers. Both general and special-purpose computers are discussed. Major computer codes are described, with regard for their use in analyzing isotope production reactors. It has been determined in this review that conventional systems codes (TRAC, RELAP5, RETRAN, etc.) cannot meet four essential conditions for viable reactor simulation: simulation fidelity, on-line interactive operation with convenient graphics, high simulation speed, and at low cost. These conditions can be met by special-purpose computers (such as the AD100 of ADI), which are specifically designed for high-speed simulation of complex systems. The greatest shortcoming of existing systems codes (TRAC, RELAP5) is their mismatch between very high computational efforts and low simulation fidelity. The drift flux formulation (HIPA) is the viable alternative to the complicated two-fluid model. No existing computer code has the capability of accommodating all important processes in the core geometry of isotope production reactors. Experiments are needed (heat transfer measurements) to provide necessary correlations. It is important for the nuclear community, both in government, industry and universities, to begin to take advantage of modern simulation technologies and equipment. 41 refs.

  20. Environment/Health/Safety (EHS): Laser Safety

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

    Toncheva 510-495-2544 Cell 510-605-8476 Backup Deputy LSO - Robert Fairchild 510-495-2278 Cell 510-926-2051 What You Need to Do to Operate a Class 3B or 4 Laser at LBNL: Update...

  1. DOE Handbook: Supplementary guidance and design experience for the fusion safety standards DOE-STD-6002-96 and DOE-STD-6003-96

    SciTech Connect (OSTI)

    1999-01-01

    Two standards have been developed that pertain to the safety of fusion facilities. These are DOE- STD-6002-96, Safety of Magnetic Fusion Facilities: Requirements, and DOE-STD-6003-96, Safety of Magnetic Fusion Facilities: Guidance. The first of these standards identifies requirements that subscribers to that standard must meet to achieve safety in fusion facilities. The second standard contains guidance to assist in meeting the requirements identified in the first This handbook provides additional documentation on good operations and design practices as well as lessons learned from the experiences of designers and operators of previous fusion facilities and related systems. It is intended to capture the experience gained in the various fields and pass it on to designers of future fusion facilities as a means of enhancing success and safety. The sections of this document are presented according to the physical location of the major systems of a fusion facility, beginning with the vacuum vessel and proceeding to those systems and components outside the vacuum vessel (the "Ex-vessel Systems"). The last section describes administrative procedures that cannot be localized to specific components. It has been tacitly assumed that the general structure of the fusion facilities addressed is that of a tokamak though the same principles would apply to other magnetic confinement options.

  2. Coiled Tubing Safety Manual

    SciTech Connect (OSTI)

    Crow, W.

    1999-04-06

    This document addresses safety concerns regarding the use of coiled tubing as it pertains to the preservation of personnel, environment and the wellbore.

  3. Corporate Analysis of DOE Safety Performance

    Broader source: Energy.gov [DOE]

    The Office of Environment, Health, Safety and Security (EHSS), Office of Analysis develops analysis tools and performance dashboards, and conducts analysis of DOE safety performance corporately and on a variety of specific environment, safety and health topics.

  4. Facility Safety - DOE Directives, Delegations, and Requirements

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

    facility and programmatic safety requirements for DOE and NNSA for nuclear safety design criteria, fire protection, criticality safety, natural phenomena hazards (NPH)...

  5. Review and Approval of Nuclear Facility Safety Basis and Safety...

    Office of Environmental Management (EM)

    DOE STANDARD REVIEW AND APPROVAL OF NUCLEAR FACILITY SAFETY BASIS AND SAFETY DESIGN BASIS ... Neither a reviewer nor the preparer has veto power over ultimate resolution or ...

  6. SafetyDesign.pdf

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

  7. Conceptual Safety Design RM

    Office of Environmental Management (EM)

    Oil, and Gas Sectors in the United States (September 2015) | Department of Energy Conceptual Framework for Developing Resilience Metrics for the Electricity, Oil, and Gas Sectors in the United States (September 2015) Conceptual Framework for Developing Resilience Metrics for the Electricity, Oil, and Gas Sectors in the United States (September 2015) This report has been written for the Department of Energy's Office of Electricity Delivery and Energy Reliability to support the Office of

  8. Preliminary Safety Design RM

    Office of Environmental Management (EM)

    Radiological Data Demonstrate Protectiveness at Formerly Utilized Sites Remedial Action Program Sites | Department of Energy Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM Radiological Data Demonstrate Protectiveness at Formerly Utilized Sites Remedial Action Program Sites Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM Radiological Data Demonstrate Protectiveness at Formerly Utilized Sites Remedial Action Program Sites Pre-MARSSIM Surveys in a

  9. Final safety evaluation report related to the certification of the System 80{sup +} design (Docket No. 52-002). Volume 2, Chapters 15--22 and appendices

    SciTech Connect (OSTI)

    Not Available

    1994-08-01

    This final safety evaluation report (FSER) documents the technical review of the System 80+ standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the system 80+ design was submitted by Combustion Engineering, Inc., now Asea Brown Boveri-Combustion Engineering (ABB-CE) as an application for design approval and subsequent design certification pursuant to 10 CFR {section} 52.45. System 80+ is a pressurized water reactor with a rated power of 3914 megawatts thermal (MWt) and a design power of 3992 MWt at which accidents are analyzed. Many features of the System 80+ are similar to those of ABB-CE`s System 80 design from which it evolved. Unique features of the System 80+ design include: a large spherical, steel containment; an in-containment refueling water storage tank; a reactor cavity flooding system, hydrogen ignitors and a safety depressurization system for severe accident mitigation; a combustion gas turbine for an alternate ac source; and an advanced digitally based control room. On the basis of its evaluation and independent analyses, the NRC staff concludes that ABB-CE`s application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the System 80+ standard design. This document, Volume 2, contains Chapters 15 through 22 and Appendices A through E.

  10. Final safety evaluation report related to the certification of the System 80{sup +} design (Docket No. 52-002). Volume 1, Chapters 1--14

    SciTech Connect (OSTI)

    Not Available

    1994-08-01

    This final safety evaluation report (FSER) documents the technical review of the System 80+ standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the System 80+ design was submitted by Combustion Engineering, Inc., now Asea Brown Boveri-Combustion Engineering (ABB-CE) as an application for design approval and subsequent design certification pursuant to 10 CFR {section} 52.45. System 80+ is a pressurized water reactor with a rated power of 3914 megawatts thermal (MWt) and a design power of 3992 MWt at which accidents are analyzed. Many features of the System 80+ are similar to those of Abb-CE`s System 80 design from which it evolved. Unique features of the System 80+ design included: a large spherical, steel containment; an in-containment refueling water storage tank; a reactor cavity flooding system, hydrogen ignitors, and a safety depressurization system for severe accident mitigation; a combustion gas turbine for an alternate ac source; and an advanced digitally based control room. On the basis of its evaluation and independent analyses, the NRC staff concludes that ABB-CE`s application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the System 80+ standard design. This document, Volume 1, contains Chapters 1 through 14 of this report.

  11. Cognitive models applied to human effectiveness in national security environments (ergonomics of augmented cognition system design and application).

    SciTech Connect (OSTI)

    Ntuen, Celestine; Winchester, Woodrow III

    2004-06-01

    In complex simulation systems where humans interact with computer-generated agents, information display and the interplay of virtual agents have become dominant media and modalities of interface design. This design strategy is reflected in augmented reality (AR), an environment where humans interact with computer-generated agents in real-time. AR systems can generate large amount of information, multiple solutions in less time, and perform far better in time-constrained problem solving. The capabilities of AR have been leveraged to augment cognition in human information processing. In this sort of augmented cognition (AC) work system, while technology has become the main source for information acquisition from the environment, the human sensory and memory capacities have failed to cope with the magnitude and scale of information they encounter. This situation generates opportunity for excessive cognitive workloads, a major factor in degraded human performance. From the human effectiveness point of view, research is needed to develop, model, and validate simulation tools that can measure the effectiveness of an AR technology used to support the amplification of human cognition. These tools will allow us to predict human performance for tasks executed under an AC tool construct. This paper presents an exploration of ergonomics issues relevant to AR and AC systems design. Additionally, proposed research to investigate those ergonomic issues is discussed.

  12. LMFBR fuel-design environment for endurance testing, primarily of oxide fuel elements with local faults

    SciTech Connect (OSTI)

    Warinner, D.K.

    1980-01-01

    The US Department of Energy LMFBR Lines-of-Assurance are briefly stated and local faults are given perspective with an historical review and definition to help define the constraints of LMFBR fuel-element designs. Local-fault-propagation (fuel-element failure-propagation and blockage propagation) perceptions are reviewed. Fuel pin designs and major LMFBR parameters affecting pin performance are summarized. The interpretation of failed-fuel data is aided by a discussion of the effects of nonprototypicalities. The fuel-pin endurance expected in the US, USSR, France, UK, Japan, and West Germany is outlined. Finally, fuel-failure detection and location by delayed-neutron and gaseous-fission-product monitors are briefly discussed to better realize the operational limits.

  13. System design and algorithmic development for computational steering in distributed environments

    SciTech Connect (OSTI)

    Wu, Qishi; Zhu, Mengxia; Gu, Yi; Rao, Nageswara S

    2010-03-01

    Supporting visualization pipelines over wide-area networks is critical to enabling large-scale scientific applications that require visual feedback to interactively steer online computations. We propose a remote computational steering system that employs analytical models to estimate the cost of computing and communication components and optimizes the overall system performance in distributed environments with heterogeneous resources. We formulate and categorize the visualization pipeline configuration problems for maximum frame rate into three classes according to the constraints on node reuse or resource sharing, namely no, contiguous, and arbitrary reuse. We prove all three problems to be NP-complete and present heuristic approaches based on a dynamic programming strategy. The superior performance of the proposed solution is demonstrated with extensive simulation results in comparison with existing algorithms and is further evidenced by experimental results collected on a prototype implementation deployed over the Internet.

  14. Pacific Northwest Laboratory annual report for 1985 to the DOE Office of the Assistant Secretary for Environment, Safety and Health. Part 5. Overview and assessment

    SciTech Connect (OSTI)

    Faust, L.G.

    1986-02-01

    This volume is progress on work performed for the Office of Nuclear Safety, the Office of Operational Safety, and for the Office of Environmental Analysis for each project. Separate abstracts have been prepared for individual projects. ACR

  15. WIPP Documents - Nuclear Safety

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

    Nuclear Safety DOE/WIPP-07-3372, Revision 4 WIPP Documented Safety Analysis Approved November 2013 The Documented Safety Analysis addresses all hazards (both radiological and nonradiological) and the controls necessary to provide adequate protection to the public, workers, and the environment. The WIPP DSA demonstrates the extent to which the Waste Isolation Pilot Plant can be operated safely with respect to workers, the public, and the environment. DOE/WIPP-07-3373, Revision 4 WIPP Technical

  16. Electrical safety guidelines

    SciTech Connect (OSTI)

    Not Available

    1993-09-01

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

  17. Experiment Safety Requirements

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

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

  18. Experiment Safety Requirements

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

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

  19. Experiment Safety Requirements

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

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

  20. Safety | Argonne National Laboratory

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

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

  1. Experiment Safety Requirements

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

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

  2. Experiment Safety Requirements

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

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

  3. Experiment Safety Requirements

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

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

  4. DOE handbook electrical safety

    SciTech Connect (OSTI)

    1998-01-01

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

  5. Facility Safety

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

    2013-06-21

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

  6. Environment/Health/Safety (EHS)

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

    activities have included the removal or replacement of single walled underground storage tanks with environmentally safe double walled tanks, the renovation of many cooling...

  7. Environment/Health/Safety (EHS)

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

    Health Services HS Home Clinical Services Policies and Procedures Presentations Forms Contact Us AED Building 26 (510) 486-6266 Monday - Friday 7:00 am - 4:30 pm In case of...

  8. Environment/Health/Safety (EHS)

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

    A-Z Index 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 Accident Statistics Accident Statistics Archive Acronyms AccidentIncident Reporting Activity Hazard Document...

  9. Environment/Health/Safety (EHS)

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

    has been in the news. Measles is a highly contagious respiratory disease caused by a virus. It spreads through the air through coughing and sneezing. Measles can be spread days...

  10. Environment/Health/Safety (EHS)

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

    of reducing waste. Keep the following suggestions in mind the next time you go to the trash can. Use the back of single-sided and continuous feed paper for rough drafts, notes,...

  11. Environment/Health/Safety (EHS)

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

    ethyl ketone, lacquer thinner. Ignitable compressed gases: hydrogen, methane, acetylene, propane, butane, spray-paint cans. Oxidizers: ammonium persulfate, sodium nitrate,...

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

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

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

  13. Virtual Design Studio (VDS) - Development of an Integrated Computer Simulation Environment for Performance Based Design of Very-Low Energy and High IEQ Buildings

    SciTech Connect (OSTI)

    Chen, Yixing; Zhang, Jianshun; Pelken, Michael; Gu, Lixing; Rice, Danial; Meng, Zhaozhou; Semahegn, Shewangizaw; Feng, Wei; Ling, Francesca; Shi, Jun; Henderson, Hugh

    2013-09-01

    Executive Summary The objective of this study was to develop a “Virtual Design Studio (VDS)”: a software platform for integrated, coordinated and optimized design of green building systems with low energy consumption, high indoor environmental quality (IEQ), and high level of sustainability. This VDS is intended to assist collaborating architects, engineers and project management team members throughout from the early phases to the detailed building design stages. It can be used to plan design tasks and workflow, and evaluate the potential impacts of various green building strategies on the building performance by using the state of the art simulation tools as well as industrial/professional standards and guidelines for green building system design. Engaged in the development of VDS was a multi-disciplinary research team that included architects, engineers, and software developers. Based on the review and analysis of how existing professional practices in building systems design operate, particularly those used in the U.S., Germany and UK, a generic process for performance-based building design, construction and operation was proposed. It distinguishes the whole process into five distinct stages: Assess, Define, Design, Apply, and Monitoring (ADDAM). The current VDS is focused on the first three stages. The VDS considers building design as a multi-dimensional process, involving multiple design teams, design factors, and design stages. The intersection among these three dimensions defines a specific design task in terms of “who”, “what” and “when”. It also considers building design as a multi-objective process that aims to enhance the five aspects of performance for green building systems: site sustainability, materials and resource efficiency, water utilization efficiency, energy efficiency and impacts to the atmospheric environment, and IEQ. The current VDS development has been limited to energy efficiency and IEQ performance, with particular focus on evaluating thermal performance, air quality and lighting environmental quality because of their strong interaction with the energy performance of buildings. The VDS software framework contains four major functions: 1) Design coordination: It enables users to define tasks using the Input-Process-Output flow approach, which specifies the anticipated activities (i.e., the process), required input and output information, and anticipated interactions with other tasks. It also allows task scheduling to define the work flow, and sharing of the design data and information via the internet. 2) Modeling and simulation: It enables users to perform building simulations to predict the energy consumption and IEQ conditions at any of the design stages by using EnergyPlus and a combined heat, air, moisture and pollutant simulation (CHAMPS) model. A method for co-simulation was developed to allow the use of both models at the same time step for the combined energy and indoor air quality analysis. 3) Results visualization: It enables users to display a 3-D geometric design of the building by reading BIM (building information model) file generated by design software such as SketchUp, and the predicted results of heat, air, moisture, pollutant and light distributions in the building. 4) Performance evaluation: It enables the users to compare the performance of a proposed building design against a reference building that is defined for the same type of buildings under the same climate condition, and predicts the percent of improvements over the minimum requirements specified in ASHRAE Standard 55-2010, 62.1-2010 and 90.1-2010. An approach was developed to estimate the potential impact of a design factor on the whole building performance, and hence can assist the user to identify areas that have most pay back for investment. The VDS software was developed by using C++ with the conventional Model, View and Control (MVC) software architecture. The software has been verified by using a simple 3-zone case building. The application of the VDS concepts and framework for building design and performance analysis has been illustrated by using a medium-sized, five story office building that received LEED Platinum Certification from USGBC.

  14. Autoclave nuclear criticality safety analysis

    SciTech Connect (OSTI)

    D`Aquila, D.M.; Tayloe, R.W. Jr.

    1991-12-31

    Steam-heated autoclaves are used in gaseous diffusion uranium enrichment plants to heat large cylinders of UF{sub 6}. Nuclear criticality safety for these autoclaves is evaluated. To enhance criticality safety, systems are incorporated into the design of autoclaves to limit the amount of water present. These safety systems also increase the likelihood that any UF{sub 6} inadvertently released from a cylinder into an autoclave is not released to the environment. Up to 140 pounds of water can be held up in large autoclaves. This mass of water is sufficient to support a nuclear criticality when optimally combined with 125 pounds of UF{sub 6} enriched to 5 percent U{sup 235}. However, water in autoclaves is widely dispersed as condensed droplets and vapor, and is extremely unlikely to form a critical configuration with released UF{sub 6}.

  15. Report to the Secretary of Energy on Beyond Design Basis Event Pilot Evaluations, Results and Recommendations for Improvements to Enhance Nuclear Safety at DOE Nuclear Facilities, January 2013

    Broader source: Energy.gov [DOE]

    In the six months after the March 2011 Fukushima Daiichi nuclear power plant accident in Japan, the U.S. Department of Energy (DOE) took several actions to review the safety of its nuclear facilities and identify situations where near-term improvements could be made. These actions and recommendations were addressed in an August 2011 report to the Secretary of Energy, Review of Requirements and Capabilities for Analyzing and Responding to Beyond Design Basis Events.

  16. Safety and Health | Department of Energy

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

    Safety and Health Safety and Health PPPO's Safety and Health (S&H) program integrates safety and health requirements and controls into all work activities. S&H oversees implementation of Integrated Safety Management (ISM) within contractor activities to ensure protection of workers, the public, and the environment. PPPO promotes a working environment where each worker feels responsible for safety and health. Decision-making reflects safety as an overriding priority for all PPPO and

  17. Los Alamos National Laboratory (LANL) Safety Conscious Work Environmen...

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

    National Laboratory (LANL) Safety Conscious Work Environment (SCWE) Self-Assessment Los Alamos National Laboratory (LANL) Safety Conscious Work Environment (SCWE) Self-Assessment ...

  18. Waste Isolation Pilot Plant Safety Analysis Report

    SciTech Connect (OSTI)

    1995-11-01

    The following provides a summary of the specific issues addressed in this FY-95 Annual Update as they relate to the CH TRU safety bases: Executive Summary; Site Characteristics; Principal Design and Safety Criteria; Facility Design and Operation; Hazards and Accident Analysis; Derivation of Technical Safety Requirements; Radiological and Hazardous Material Protection; Institutional Programs; Quality Assurance; and Decontamination and Decommissioning. The System Design Descriptions`` (SDDS) for the WIPP were reviewed and incorporated into Chapter 3, Principal Design and Safety Criteria and Chapter 4, Facility Design and Operation. This provides the most currently available final engineering design information on waste emplacement operations throughout the disposal phase up to the point of permanent closure. Also, the criteria which define the TRU waste to be accepted for disposal at the WIPP facility were summarized in Chapter 3 based on the WAC for the Waste Isolation Pilot Plant.`` This Safety Analysis Report (SAR) documents the safety analyses that develop and evaluate the adequacy of the Waste Isolation Pilot Plant Contact-Handled Transuranic Wastes (WIPP CH TRU) safety bases necessary to ensure the safety of workers, the public and the environment from the hazards posed by WIPP waste handling and emplacement operations during the disposal phase and hazards associated with the decommissioning and decontamination phase. The analyses of the hazards associated with the long-term (10,000 year) disposal of TRU and TRU mixed waste, and demonstration of compliance with the requirements of 40 CFR 191, Subpart B and 40 CFR 268.6 will be addressed in detail in the WIPP Final Certification Application scheduled for submittal in October 1996 (40 CFR 191) and the No-Migration Variance Petition (40 CFR 268.6) scheduled for submittal in June 1996. Section 5.4, Long-Term Waste Isolation Assessment summarizes the current status of the assessment.

  19. Radiation Safety

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

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

  20. Nuclear safety information sharing agreement between NRC and DOE's Office

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

    of Environment, Health, Safety and Security | Department of Energy Nuclear safety information sharing agreement between NRC and DOE's Office of Environment, Health, Safety and Security Nuclear safety information sharing agreement between NRC and DOE's Office of Environment, Health, Safety and Security December 2014 agreement between NRC and DOE's Office of Environment, Health, Safety and Security to establish a framework for DOE and NRC to exchange information related to safety issues

  1. Fuel Storage Facility Final Safety Analysis Report. Revision 1

    SciTech Connect (OSTI)

    Linderoth, C.E.

    1984-03-01

    The Fuel Storage Facility (FSF) is an integral part of the Fast Flux Test Facility. Its purpose is to provide long-term storage (20-year design life) for spent fuel core elements used to provide the fast flux environment in FFTF, and for test fuel pins, components and subassemblies that have been irradiated in the fast flux environment. This Final Safety Analysis Report (FSAR) and its supporting documentation provides a complete description and safety evaluation of the site, the plant design, operations, and potential accidents.

  2. Safety harness

    DOE Patents [OSTI]

    Gunter, Larry W.

    1993-01-01

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

  3. Regulatory Safety Issues in the Structural Design Criteria of ASME Section III Subsection NH and for Very High Temperatures for VHTR & GEN IV

    SciTech Connect (OSTI)

    William J. O’Donnell; Donald S. Griffin

    2007-05-07

    The objective of this task is to identify issues relevant to ASME Section III, Subsection NH [1], and related Code Cases that must be resolved for licensing purposes for VHTGRs (Very High Temperature Gas Reactor concepts such as those of PBMR, Areva, and GA); and to identify the material models, design criteria, and analysis methods that need to be added to the ASME Code to cover the unresolved safety issues. Subsection NH was originally developed to provide structural design criteria and limits for elevated-temperature design of Liquid Metal Fast Breeder Reactor (LMFBR) systems and some gas-cooled systems. The U.S. Nuclear Regulatory Commission (NRC) and its Advisory Committee for Reactor Safeguards (ACRS) reviewed the design limits and procedures in the process of reviewing the Clinch River Breeder Reactor (CRBR) for a construction permit in the late 1970s and early 1980s, and identified issues that needed resolution. In the years since then, the NRC and various contractors have evaluated the applicability of the ASME Code and Code Cases to high-temperature reactor designs such as the VHTGRs, and identified issues that need to be resolved to provide a regulatory basis for licensing. This Report describes: (1) NRC and ACRS safety concerns raised during the licensing process of CRBR , (2) how some of these issues are addressed by the current Subsection NH of the ASME Code; and (3) the material models, design criteria, and analysis methods that need to be added to the ASME Code and Code Cases to cover unresolved regulatory issues for very high temperature service.

  4. Safety of Accelerator Facilities

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

    2011-07-21

    The order defines accelerators and establishes accelerator specific safety requirements and approval authorities which, when supplemented by other applicable safety and health requirements, promote safe operations to ensure protection of workers, the public, and the environment. Supersedes DOE O 420.2B.

  5. Health, Safety, and Environmental Protection Committee Page 1

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

    Health, Safety, & Quality Assurance Health, Safety, & Quality Assurance Nuclear Safety and Worker Safety and Health training Nuclear Safety and Worker Safety and Health training PPPO's Safety and Health, Nuclear Safety, and Quality Assurance programs collectively ensure protection of public and worker health and safety and the environment. This is accomplished by empowering and holding accountable managers, employees and contractors to prioritize health, safety and environmental

  6. Health, Safety, & Quality Assurance | Department of Energy

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

    Health, Safety, & Quality Assurance Health, Safety, & Quality Assurance Nuclear Safety and Worker Safety and Health training Nuclear Safety and Worker Safety and Health training PPPO's Safety and Health, Nuclear Safety, and Quality Assurance programs collectively ensure protection of public and worker health and safety and the environment. This is accomplished by empowering and holding accountable managers, employees and contractors to prioritize health, safety and environmental

  7. Analysis of environment, safety, and health (ES{ampersand}H) management systems for Department of Energy (DOE) Defense Programs (DP) facilities

    SciTech Connect (OSTI)

    Neglia, A. V., LLNL

    1998-03-01

    The purpose of this paper is to provide a summary analysis and comparison of various environment, safety, and health (ES&H) management systems required of, or suggested for use by, the Departrnent of Energy Defense Programs` sites. The summary analysis is provided by means of a comparison matrix, a set of Vean diagrams that highlights the focus of the systems, and an `End Gate` filter diagram that integrates the three Vean diagrams. It is intended that this paper will act as a starting point for implementing a particular system or in establishing a comprehensive site-wide integrated ES&H management system. Obviously, the source documents for each system would need to be reviewed to assure proper implementation of a particular system. The matrix compares nine ES&H management systems against a list of elements generated by identifying the unique elements of all the systems. To simplify the matrix, the elements are listed by means of a brief title. An explanation of the matrix elements is provided in Attachment 2 entitled, `Description of System Elements.` The elements are categorized under the Total Quality Management (TQM) `Plan, Do, Check, Act` framework with the added category of `Policy`. (The TQM concept is explained in the `DOE Quality Management implementation Guidelines,` July 1997 (DOE/QM- 0008)). The matrix provides a series of columns and rows to compare the unique elements found in each of the management systems. A `V` is marked if the element is explicitly identified as part of the particular ES&H management system. An `X` is marked if the element is not found in the particular ES&H management system, or if it is considered to be inadequately addressed. A `?` is marked if incorporation of the element is not clear. Attachment I provides additional background information which explains the justification for the marks in the matrix cells. Through the Vean diagrams and the `End Gate` filter in Section 3, the paper attempts to pictorially display the focus of each system with respect to ES&H, the hazard of concern, and any limitations with respect to the TQM categories. A summary evaluation and explanation of each of the systems is provided in Section 4 of the paper. Several other ES&H systems were reviewed in preparation of the paper, but were not specifically included as a system in this matrix. Only those ES&H management systems that are potentially applicable to DOE Defense Program sites were included as part of the matrix comparison. A description of other ES&H management systems that were evaluated, but not specifically incorporated in this matrix comparison, are provided in Attachment 3 entitled, `Other ES&H Management Systems Reviewed.` In the past, it has been difficult integrating ES&H into work planning for several reasons. One barrier to this integration has been the complexity caused by the existence of several `stove pipe` ES&H systems. By analyzing the unique elements of the various ES&H systems, as well as their strengths and limitations, and their similarities and differences, it is envisioned that this paper will aid in facilitating the integration of ES&H into work planning. This paper was developed by the Office of Defense Programs (DP-45) and all questions or comments should be directed to Anthony Neglia of that office at (301) 903-3531 or Anthony.Neglia@dp.doe.gov.

  8. Review and Approval of Nuclear Facility Safety Basis and Safety...

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

    104-2014, Review and Approval of Nuclear Facility Safety Basis and Safety Design Basis Documents by Website Administrator This Standard describes a framework and the criteria to be...

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

    SciTech Connect (OSTI)

    1997-04-01

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

  10. Nuclear safety analyses and core design calculations to convert the Texas A & M University Nuclear Science Center reactor to low enrichment uranium fuel. Final report

    SciTech Connect (OSTI)

    Parish, T.A.

    1995-03-02

    This project involved performing the nuclear design and safety analyses needed to modify the license issued by the Nuclear Regulatory Commission to allow operation of the Texas A& M University Nuclear Science Center Reactor (NSCR) with a core containing low enrichment uranium (LEU) fuel. The specific type of LEU fuel to be considered was the TRIGA 20-20 fuel produced by General Atomic. Computer codes for the neutronic analyses were provided by Argonne National Laboratory (ANL) and the assistance of William Woodruff of ANL in helping the NSCR staff to learn the proper use of the codes is gratefully acknowledged. The codes applied in the LEU analyses were WIMSd4/m, DIF3D, NCTRIGA and PARET. These codes allowed full three dimensional, temperature and burnup dependent calculations modelling the NSCR core to be performed for the first time. In addition, temperature coefficients of reactivity and pulsing calculations were carried out in-house, whereas in the past this modelling had been performed at General Atomic. In order to benchmark the newly acquired codes, modelling of the current NSCR core with highly enriched uranium fuel was also carried out. Calculated results were compared to both earlier licensing calculations and experimental data and the new methods were found to achieve excellent agreement with both. Therefore, even if an LEU core is never loaded at the NSCR, this project has resulted in a significant improvement in the nuclear safety analysis capabilities established and maintained at the NSCR.

  11. Health & Safety

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

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

  12. Safety, Security

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

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

  13. Design

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

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

  14. A safety overview of Sandia National Laboratories' reactor facilities

    SciTech Connect (OSTI)

    Philbin, J.S.

    1989-04-01

    This report provides an overview of Sandia National Laboratories' safety policies and practices supporting the operation of Sandia's nuclear reactor facilities. These policies and practices have evolved from Sandia's 30 years of experience and leadership in the design, construction, and operation of steady-state and pulse research reactors. The report illustrates how Sandia has implemented DOE orders and research reactor standards with the goal of reducing risks to the lowest reasonable levels for its employees, contractors, the public, and the environment. The impact of DOE orders and standards on virtually all aspects of reactor operations and administration is illustrated. Included in the report are descriptions of safety documentation (Technical Specifications and Safety Analysis Reports); the facility safety review system for addressing radiological protection and other environmental, safety and health issues; experiment activities; quality assurance; training and certification; and emergency planning.

  15. Safety and Security Officer

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

    2007-07-20

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

  16. CRITICALITY SAFETY CONTROLS AND THE SAFETY BASIS AT PFP

    SciTech Connect (OSTI)

    Kessler, S

    2009-04-21

    With the implementation of DOE Order 420.1B, Facility Safety, and DOE-STD-3007-2007, 'Guidelines for Preparing Criticality Safety Evaluations at Department of Energy Non-Reactor Nuclear Facilities', a new requirement was imposed that all criticality safety controls be evaluated for inclusion in the facility Documented Safety Analysis (DSA) and that the evaluation process be documented in the site Criticality Safety Program Description Document (CSPDD). At the Hanford site in Washington State the CSPDD, HNF-31695, 'General Description of the FH Criticality Safety Program', requires each facility develop a linking document called a Criticality Control Review (CCR) to document performance of these evaluations. Chapter 5, Appendix 5B of HNF-7098, Criticality Safety Program, provided an example of a format for a CCR that could be used in lieu of each facility developing its own CCR. Since the Plutonium Finishing Plant (PFP) is presently undergoing Deactivation and Decommissioning (D&D), new procedures are being developed for cleanout of equipment and systems that have not been operated in years. Existing Criticality Safety Evaluations (CSE) are revised, or new ones written, to develop the controls required to support D&D activities. Other Hanford facilities, including PFP, had difficulty using the basic CCR out of HNF-7098 when first implemented. Interpretation of the new guidelines indicated that many of the controls needed to be elevated to TSR level controls. Criterion 2 of the standard, requiring that the consequence of a criticality be examined for establishing the classification of a control, was not addressed. Upon in-depth review by PFP Criticality Safety staff, it was not clear that the programmatic interpretation of criterion 8C could be applied at PFP. Therefore, the PFP Criticality Safety staff decided to write their own CCR. The PFP CCR provides additional guidance for the evaluation team to use by clarifying the evaluation criteria in DOE-STD-3007-2007. In reviewing documents used in classifying controls for Nuclear Safety, it was noted that DOE-HDBK-1188, 'Glossary of Environment, Health, and Safety Terms', defines an Administrative Control (AC) in terms that are different than typically used in Criticality Safety. As part of this CCR, a new term, Criticality Administrative Control (CAC) was defined to clarify the difference between an AC used for criticality safety and an AC used for nuclear safety. In Nuclear Safety terms, an AC is a provision relating to organization and management, procedures, recordkeeping, assessment, and reporting necessary to ensure safe operation of a facility. A CAC was defined as an administrative control derived in a criticality safety analysis that is implemented to ensure double contingency. According to criterion 2 of Section IV, 'Linkage to the Documented Safety Analysis', of DOESTD-3007-2007, the consequence of a criticality should be examined for the purposes of classifying the significance of a control or component. HNF-PRO-700, 'Safety Basis Development', provides control selection criteria based on consequence and risk that may be used in the development of a Criticality Safety Evaluation (CSE) to establish the classification of a component as a design feature, as safety class or safety significant, i.e., an Engineered Safety Feature (ESF), or as equipment important to safety; or merely provides defense-in-depth. Similar logic is applied to the CACs. Criterion 8C of DOE-STD-3007-2007, as written, added to the confusion of using the basic CCR from HNF-7098. The PFP CCR attempts to clarify this criterion by revising it to say 'Programmatic commitments or general references to control philosophy (e.g., mass control or spacing control or concentration control as an overall control strategy for the process without specific quantification of individual limits) is included in the PFP DSA'. Table 1 shows the PFP methodology for evaluating CACs. This evaluation process has been in use since February of 2008 and has proven to be simple and effective. Each control identified i

  17. Light-Weight Radioisotope Heater Unit Safety Analysis Report (LWRHU-SAR). Volume I. A. Introduction and executive summary. B. Reference Design Document (RDD)

    SciTech Connect (OSTI)

    Johnson, E.W.

    1985-10-01

    The orbiter and probe portions of the NASA Galileo spacecraft contain components which require auxiliary heat during the mission. To meet these needs, the Department of Energy's (DOE's) Office of Special Nuclear Projects (OSNP) has sponsored the design, fabrication, and testing of a one-watt encapsulated plutonium dioxide-fueled thermal heater named the Light-Weight Radioisotope Heater Unit (LWRHU). This report addresses the radiological risks which might be encountered by people both at the launch area and worldwide should postulate mission failures or malfunctions occur, which would result in the release of the LWRHUs to the environment. Included are data from the design, mission descriptions, postulated accidents with their consequences, test data, and the derived source terms and personnel exposures for the various events.

  18. Light-Weight Radioisotope Heater Unit final safety analysis report (LWRHU-FSAR): Volume 1: A. Introduction and executive summary: B. Reference Design Document (RDD)

    SciTech Connect (OSTI)

    Johnson, E.W.

    1988-10-01

    The orbiter and probe portions of the National Aeronautics and Space Administration (NASA) Galileo spacecraft contain components which require auxiliary heat during the mission. To meet these needs, the Department of Energy's (DOE's) Office of Special Applications (OSA) has sponsored the design, fabrication, and testing of a one-watt encapsulated plutonium dioxide-fueled thermal heater named the Light-Weight Radioisotope Heater Unit (LWRHU). This report, prepared by Monsanto Research Corporation (MRC), addresses the radiological risks which might be encountered by people both at the launch area and worldwide should postulated mission failures or malfunctions occur, resulting in the release of the LWRHUs to the environment. Included are data from the design, mission descriptions, postulated accidents with their consequences, test data, and the derived source terms and personnel exposures for the various events. 11 refs., 44 figs., 11 tabs.

  19. Energy Department Announces Creation of New Health, Safety and...

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

    Creation of New Health, Safety and Security Office Energy Department Announces Creation of ... Environment; Office of Corporate Safety Analysis; Office of Enforcement; Office of ...

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

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

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

  1. Safety | Argonne National Laboratory

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

    Safety Argonne National Laboratory and the U.S. Department of Energy (DOE) are very concerned about the well-being of all employees. Students at the undergraduate and graduate level as well as postdoctoral appointees form an essential component of the research endeavor at the laboratory. However, research does not stand alone but must be integrated into a program of environment, safety, and security. From time to time, incidents regarding students and postdocs occur across the DOE complex. It is

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

    SciTech Connect (OSTI)

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

    2009-05-27

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

  3. SSC Safety Review Document

    SciTech Connect (OSTI)

    Toohig, T.E. [ed.

    1988-11-01

    The safety strategy of the Superconducting Super Collider (SSC) Central Design Group (CDG) is to mitigate potential hazards to personnel, as far as possible, through appropriate measures in the design and engineering of the facility. The Safety Review Document identifies, on the basis of the Conceptual Design Report (CDR) and related studies, potential hazards inherent in the SSC project independent of its site. Mitigative measures in the design of facilities and in the structuring of laboratory operations are described for each of the hazards identified.

  4. Pacific Northwest Laboratory annual report for 1979 to the DOE Assistant Secretary for Environment. Part 5. Environmental assessment, control, health, and safety

    SciTech Connect (OSTI)

    Baalman, R.W.; Dotson, C.W.

    1980-02-01

    Part 5 of the 1979 Annual Report to the Department of Energy Assistant Secretary for the Environment presents Pacific Northwest Laboratory's progress on work performed for the Office of Technology Impacts, the Office of Environmental Compliance and Overview, and the Office of Health and Environmental Research. The report is in four sections, corresponding to the program elements: technology impacts, environmental control engineering, operational and environmental compliance, and human health studies. In each section, articles describe progress made during FY 1979 on individual projects.

  5. Design and test of a robust multi-channel programmable sensor interface circuit for use in extreme environments

    SciTech Connect (OSTI)

    Van Cutsem, K.; De Cock, W.; Tavernier, S.

    2011-07-01

    This article describes the design of a sensor interface circuit for the amplification of voltages and currents. The created PCB was tested at high temperatures and under gamma irradiation. Two different operational amplifiers were compared. (authors)

  6. Safety Comes First | Jefferson Lab

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

    Safety Comes First Safety Comes First When it comes to providing for the safety of employees and visiting researchers and protecting the environment, the Thomas Jefferson National Accelerator Facility is one of the best. "I don't compare the labs, but the results here are very good," said Thomas Staker, who led a team of inspectors that conducted an extensive inspection of environment, safety and health programs at Jefferson Lab in May and June. Staker is director of the U.S.

  7. Request for Naval Reactors Comment on Proposed Prometheus Space Flight Nuclear Reactor High Tier Reactor Safety Requirements and for Naval Reactors Approval to Transmit These Requirements to JPL

    SciTech Connect (OSTI)

    D. Kokkinos

    2005-04-28

    The purpose of this letter is to request Naval Reactors comments on the nuclear reactor high tier requirements for the PROMETHEUS space flight reactor design, pre-launch operations, launch, ascent, operation, and disposal, and to request Naval Reactors approval to transmit these requirements to Jet Propulsion Laboratory to ensure consistency between the reactor safety requirements and the spacecraft safety requirements. The proposed PROMETHEUS nuclear reactor high tier safety requirements are consistent with the long standing safety culture of the Naval Reactors Program and its commitment to protecting the health and safety of the public and the environment. In addition, the philosophy on which these requirements are based is consistent with the Nuclear Safety Policy Working Group recommendations on space nuclear propulsion safety (Reference 1), DOE Nuclear Safety Criteria and Specifications for Space Nuclear Reactors (Reference 2), the Nuclear Space Power Safety and Facility Guidelines Study of the Applied Physics Laboratory.

  8. Towards intelligent microstructural design of Nanocomposite Materials. Lightweight, high strength structural/armor materials for service in extreme environments

    SciTech Connect (OSTI)

    Mara, Nathan Allan; Bronkhorst, Curt Allan; Beyerlein, Irene Jane

    2015-12-21

    The intent of this research effort is to prove the hypothesis that: Through the employment of controlled processing parameters which are based upon integrated advanced material characterization and multi-physics material modeling, bulk nanolayered composites can be designed to contain high densities of preferred interfaces that can serve as supersinks for the defects responsible for premature damage and failure.

  9. Safety Issues

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

    Site Safety Orientation April, 2015 Atmospheric Radiation Measurement Climate Research ... with operations at the Atmospheric Radiation Measurement Climate Research Facility...

  10. Biological Safety

    Broader source: Energy.gov [DOE]

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

  11. Office of Enforcement and Oversight's Office of Safety and Emergency...

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

    protection; fire protection; safety basis; quality assurance; civil, structural, and seismic design requirements; engineering design; configuration management; and...

  12. K Basin safety analysis

    SciTech Connect (OSTI)

    Porten, D.R.; Crowe, R.D.

    1994-12-16

    The purpose of this accident safety analysis is to document in detail, analyses whose results were reported in summary form in the K Basins Safety Analysis Report WHC-SD-SNF-SAR-001. The safety analysis addressed the potential for release of radioactive and non-radioactive hazardous material located in the K Basins and their supporting facilities. The safety analysis covers the hazards associated with normal K Basin fuel storage and handling operations, fuel encapsulation, sludge encapsulation, and canister clean-up and disposal. After a review of the Criticality Safety Evaluation of the K Basin activities, the following postulated events were evaluated: Crane failure and casks dropped into loadout pit; Design basis earthquake; Hypothetical loss of basin water accident analysis; Combustion of uranium fuel following dryout; Crane failure and cask dropped onto floor of transfer area; Spent ion exchange shipment for burial; Hydrogen deflagration in ion exchange modules and filters; Release of Chlorine; Power availability and reliability; and Ashfall.

  13. Jefferson Lab Names New Safety Director | Jefferson Lab

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

    New Safety Director Jefferson Lab Names New Safety Director NEWPORT NEWS, Va., April 9, 2008 - Mary K. Logue, an experienced safety professional responsible for the implementation of the Environment, Health and Safety program at the Department of Energy's Fermi National Accelerator Facility, has been named as the associate director for Environment, Safety, Health and Quality division at Thomas Jefferson National Accelerator Facility. Logue, currently an associate section head for environment,

  14. ORISE: Safety is our top priority

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

    Safety Integrated Safety Management Voluntary Protection Program VPP Star Status Environment Work Smart Standards Oak Ridge Institute for Science Education Safety at ORISE At the Oak Ridge Institute for Science and Education (ORISE) safety is our number one priority. We not only have a tradition of safety at work, but strongly encourage our employees to carry this mindset beyond the workplace and into their homes and communities. Employees are trained in how to work safely and are required to

  15. Integrated Safety Management

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

    2011-04-25

    The order ensures that DOE/NNSA, systematically integrates safety into management and work practices at all levels, so that missions are accomplished efficiently while protecting the workers, the public, and the environment. Supersedes DOE M 450.4-1 and DOE M 411.1-1C

  16. Chapter 23 - Environment, Energy and Water Efficiency, Renewable...

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

    Occupational Safety, and Drug-free Workplace. Chapter 23 - Environment, Energy and Water Efficiency, Renewable Energy Technologies, Occupational Safety, and Drug-free Workplace. ...

  17. Preparation of Documented Safety Analysis for Decommissioning...

    Office of Environmental Management (EM)

    should be addressed to: Office of Nuclear Safety (AU-30) Office of Environment, Health, ... The requirements for power, cooling water, and other external supplies to the ...

  18. Integrated Safety Management in QA Program Planning

    Broader source: Energy.gov [DOE]

    Presenter: Sonya Barnette, Office of Quality Assurance Policy and Assistance, Office of Nuclear Safety, Quality Assurance and Environment Track 9-8

  19. Safety Engineer

    Broader source: Energy.gov [DOE]

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

  20. Explosives Safety

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

    2012-06-27

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

  1. Seismic Safety Guide

    SciTech Connect (OSTI)

    Eagling, D.G.

    1983-09-01

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

  2. Nuclear Safety. Technical Progress Journal, October--December 1991: Volume 32, No. 4

    SciTech Connect (OSTI)

    Not Available

    1991-01-01

    This document is a review journal that covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

  3. Safety is the First Priority

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

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

  4. Environment, Safety & Health | National Nuclear Security Administratio...

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

    and Health Program; oversees the Environmental Management System, and provides oversight and direction for SNL waste management, water, air, and pollution prevention programs

  5. Environment, Safety, and Health Reporting Manual

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

    2004-03-19

    This Manual supplements DOE O 231.1A and provides detailed requirements for implementing Department of Energy reporting requirements, including time schedules for reporting and data elements to be reported. Cancels DOE M 231.1-1, DOE N 231.1.

  6. Environment, Safety and Health Reporting Manual

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

    2004-09-09

    This Manual supplements DOE O 231.1A and provides detailed requirement for implementing Department of Energy reporting requirements, including time schedules for reporting and data elements to be reported. The Page Change clarifies responsibilities pertaining to occupational injury and illness recordkeeping and recording; requires quarterly reconciliation of occupational injury and illness data; and provides clarification on data elements that must be reported and reconciled with local data records. Cancels DOE M 231.1-1c1, DOE N 231.1. Chg 1, 9-9-04.

  7. Environment, Safety and Health Reporting Manual

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

    2004-03-19

    This Manual supplements DOE O 231.1A and provides detailed requirement for implementing Department of Energy reporting requirements, including time schedules for reporting and data elements to be reported. The page change modifies policy previously established that requires recording and reporting occupational injuries and illnesses of subcontractors employees. Change 1 dated 9-9-04. Change 2 dated 6-12-07. Canceled by DOE O 231.1B

  8. Environment/Health/Safety (EHS): Site Map

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

    Group Members spacer image Organizational Chart spacer image Programs and Databases arrow image Operations spacer image Admin Help Desk (EHS) spacer image IT...

  9. Environment, Health, Safety & Security | Department of Energy

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

    The purpose of the training is to provide an enhanced understanding of the requirements of ... DOE National Training Center is located on the Office of Enterprise Assessment (EA) site. ...

  10. Environment/Health/Safety (EHS): Databases

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

    and to write evaluation reports) HMS - Hazard Management System Laser Management System Lessons Learned Best Practices REMS - Radiation Exposure Monitoring System SJHA Database...

  11. Environment/Health/Safety (EHS): JHA

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

    on the above image to learn more about the JHA. Download the PDF Version of the Flash animation Download the Step by Step Instructions for: An Individual A Supervisor (who is not a...

  12. Environment, Health, Safety & Security | Department of Energy

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

    is the SPLC's highest honor and recognizes a purchasing organization whose overall sustainable purchasing program exemplifies leadership-for DOE's GreenBuy Award Program....

  13. Radiation Safety System

    SciTech Connect (OSTI)

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

    2012-04-04

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

  14. Wireless Environment LLC | Open Energy Information

    Open Energy Info (EERE)

    Wireless Environment LLC Jump to: navigation, search Name: Wireless Environment LLC Place: Elyria, Ohio Product: Wireless Environment designs light-emitting diode lighting products...

  15. German Federal Ministry for the Environment, Nature Conservation...

    Open Energy Info (EERE)

    Federal Ministry for the Environment, Nature Conservation and Nuclear Safety Jump to: navigation, search Logo: German Federal Ministry for the Environment, Nature Conservation and...

  16. Report to the Secretary of Energy on Beyond Design Basis Event Pilot Evaluations, Results and Recommendations for Improvements to Enhance Nuclear Safety at DOE Nuclear Facilities

    Broader source: Energy.gov [DOE]

    In the six months after the March 2011 Fukushima Daiichi nuclear power plant accident in Japan, the U.S. Department of Energy (DOE) took several actions to review the safety of its nuclear facilities and identify situations where near-term improvements could be made.

  17. Safety Review Committee | The Ames Laboratory

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

    Safety Review Committee The Ames Laboratory Safety Review Committee is a standing committee of the Ames Laboratory. The committee chair reports to the Director, Adam Schwartz. The purpose of the committee is to make recommendations regarding the safety issues of activities affiliated with the Ames Laboratory. The committee implements and directs the Environment, Safety and Health Readiness Review process and facilitates the timely and orderly review of activities. The current members of the

  18. Integrated Safety Management (ISM) | Department of Energy

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

    Integrated Safety Management (ISM) Integrated Safety Management (ISM) The objective of ISM is to perform work in a safe and environmentally sound manner. More specifically, as described in DOE P 450.4, Safety Management System Policy: "The Department and Contractors must systematically integrate safety into management and work practices at all levels so that missions are accomplished while protecting the public, the worker, and the environment. This is to be accomplished through effective

  19. Facility Safety

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

    2002-05-20

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

  20. Transportation Safety

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

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

  1. Safety - 88-Inch Cyclotron

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (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 manner that protects the environment. In conducting its operations and research, NSD meets or exceeds Berkeley Lab, University of California, and U.S. Department of Energy policies and requirements. To report a life-threatening accident, call x7911 For all other accidents or near-hits, call x6999 For Emergency Status

  2. Safety equipment list

    SciTech Connect (OSTI)

    Lavender, J.C.; Roe, N.A.

    1995-04-13

    This analysis assigns preliminary safety class (SC) designations to major systems and structures associated with the Multi-Function Waste Tank Facility (MWTF) project in accordance with the Multi-Function QAPP, W-236A (Hall 1994). Also included are SC assignments for those subsystems and major components of the major systems discussed in this document (see Appendices A and B). Component safety classifications have been completed through inspection (using engineering judgement) for simple systems, and through use of logic models (i.e., fault trees) for complicated systems. This analysis is intended to augment the SC systems list supplied in Chapter 9 of the MWTF Preliminary Safety Analysis Report (WHC 1994). Whereas WHC (1994) only addresses select systems, this analysis addresses the SC ramifications of all MWTF systems and structures as identified in the Title 1 design media. This document provides additional analyses of the system safety classifications assignments, and classifies systems not addressed in WHC (1994). This analysis specifically describes the safety functions) that must be performed by each MWTF system.

  3. Nuclear Safety Research and Development Annual Report, December 2014 |

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

    Department of Energy Nuclear Safety Research and Development Annual Report, December 2014 Nuclear Safety Research and Development Annual Report, December 2014 December 8, 2014 - 1:22pm Addthis Nuclear Safety Research and Development Annual Report, December 2014 This document is the first annual report of DOE's Nuclear Safety Research and Development (NSR&D) Program, managed by the Office of Nuclear Safety in the Office of Environment, Health, Safety and Security. The report includes a

  4. Measuring Process Safety Management

    SciTech Connect (OSTI)

    Sweeney, J.C. (ARCO Chemical Co., Newtown Square, PA (United States))

    1992-04-01

    Many companies are developing and implementing Process Safety Management (PSM) systems. Various PSM models, including those by the Center for Chemical Process Safety (CCPS), the American Petroleum Institute (API), the Chemical Manufacturers Association (CMA) and OSHA have emerged to guide the design, development and installation of these systems. These models represent distillations of the practices, methods and procedures successfully used by those who believed that a strong correlation exists between sound PSM practices and achieving reductions in the frequency and severity of process incidents. This paper describes the progress of CCPS research toward developing a PSM performance measurement model. It also provides a vision for future CCPS research to define effectiveness indices.

  5. 2012 Nuclear Safety Workshop Presentations

    Broader source: Energy.gov [DOE]

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

  6. Module Safety Issues (Presentation)

    SciTech Connect (OSTI)

    Wohlgemuth, J.

    2012-02-01

    Description of how to make PV modules so that they are less likely to turn into safety hazards. Making modules inherently safer with minimum additional cost is the preferred approach for PV. Safety starts with module design to ensure redundancy within the electrical circuitry to minimize open circuits and proper mounting instructions to prevent installation related ground faults. Module manufacturers must control the raw materials and processes to ensure that that every module is built like those qualified through the safety tests. This is the reason behind the QA task force effort to develop a 'Guideline for PV Module Manufacturing QA'. Periodic accelerated stress testing of production products is critical to validate the safety of the product. Combining safer PV modules with better systems designs is the ultimate goal. This should be especially true for PV arrays on buildings. Use of lower voltage dc circuits - AC modules, DC-DC converters. Use of arc detectors and interrupters to detect arcs and open the circuits to extinguish the arcs.

  7. Path to development of quantitative safety goals

    SciTech Connect (OSTI)

    Joksimovic, V.; Houghton, W.J.

    1980-04-01

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

  8. Safety valve

    DOE Patents [OSTI]

    Bergman, Ulf C.

    1984-01-01

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

  9. New rocket propellant and motor design offer high-performance...

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

    New rocket propellant and motor design offer high-performance and safety New rocket propellant and motor design offer high-performance and safety Scientists recently flight tested...

  10. Inherently Risky Design?

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

    Inherently Risky Design? The History of Soviet Nuclear Reactors and the Notion of Safety Sonja Schmid, ... Program * Kurchatov turns to power reactors before first Soviet ...

  11. Vol 2, Integrated Safety Management System Guide

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

    1999-05-27

    This Department of Energy (DOE) Integrated Safety Management System (ISMS) Guide is approved for use by the Office of Environment, Safety and Health (EH) and is available for use by all DOE components and their contractors. This Guide is a consensus document coordinated by EH and prepared under the direction of the DOE Safety Management Implementation Team (SMIT). Canceled by DOE G 450.4-1B.

  12. Reactor operation safety information document

    SciTech Connect (OSTI)

    Not Available

    1990-01-01

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

  13. Westinghouse Earns 15th Consecutive Mine Safety Award

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

    for profit. This award recognizes Westinghouse's close attention to safety in a mining environment. WTS is the management and operating contractor for the DOE at the Waste...

  14. Delivering safety

    SciTech Connect (OSTI)

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

    2007-07-01

    In the United Kingdom there have been significant recent changes to the management of civil nuclear liabilities. With the formation in April 2005 of the Nuclear Decommissioning Authority (NDA), ownership of the civil nuclear licensed sites in the UK, including the Magnox Reactor Stations, passed to this new organisation. The NDAs mission is to seek acceleration of the nuclear clean up programme and deliver increased value for money and, consequently, are driving their contractors to seek more innovative ways of performing work. British Nuclear Group manages the UK Magnox stations under contract to the NDA. This paper summarises the approach being taken within its Reactor Sites business to work with suppliers to enhance working arrangements at sites, improve the delivery of decommissioning programmes and deliver improvements in safety and environmental performance. The UK Magnox stations are 1. generation gas-graphite reactors, constructed in the 1950's and 1960's. Two stations are currently still operating, three are shut-down undergoing defueling and the other five are being decommissioned. Despite the distractions of industry restructuring, an uncompromising policy of demanding improved performance in conjunction with improved safety and environmental standards has been adopted. Over the past 5 years, this policy has resulted in step-changes in performance at Reactor Sites, with increased electrical output and accelerated defueling and decommissioning. The improvements in performance have been mirrored by improvements in safety (DACR of 0 at 5 sites); environmental standards (reductions in energy and water consumption, increased waste recycling) and the overall health of the workforce (20% reduction in sickness absence). These achievements have, in turn, been recognised by external bodies, resulting in several awards, including: the world's first ISRS and IERS level 10 awards (Sizewell, 2006), the NUMEX plant maintenance award (Bradwell, 2006), numerous RoSPA awards at site and sector level and nomination, at Company level, for the RoSPA George Earle trophy for outstanding performance in Health and Safety (Reactor Sites, 2006). After 'setting the scene' and describing the challenges that the company has had to respond to, the paper explains how these improvements have been delivered. Specifically it explains the process that has been followed and the parts played by sites and suppliers to deliver improved performance. With the experience of already having transitioned several Magnox stations from operations to defueling and then to decommissioning, the paper describes the valuable experience that has been gained in achieving an optimum change process and maintaining momentum. (authors)

  15. Design Code Survey Form | Department of Energy

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

    Design Code Survey Form Design Code Survey Form Survey of Safety Software Used in Design of Structures, Systems, and Components 1. Introduction The Department's Implementation Plan ...

  16. Solid waste burial grounds interim safety analysis

    SciTech Connect (OSTI)

    Saito, G.H.

    1994-10-01

    This Interim Safety Analysis document supports the authorization basis for the interim operation and restrictions on interim operations for the near-surface land disposal of solid waste in the Solid Waste Burial Grounds. The Solid Waste Burial Grounds Interim Safety Basis supports the upgrade progress for the safety analysis report and the technical safety requirements for the operations in the Solid Waste Burial Grounds. Accident safety analysis scenarios have been analyzed based on the significant events identified in the preliminary hazards analysis. The interim safety analysis provides an evaluation of the operations in the Solid Waste Burial Grounds to determine if the radiological and hazardous material exposures will be acceptable from an overall health and safety standpoint to the worker, the onsite personnel, the public, and the environment.

  17. Safety Share from National Safety Council

    Broader source: Energy.gov [DOE]

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

  18. Integrated deterministic and probabilistic safety analysis for safety assessment of nuclear power plants

    SciTech Connect (OSTI)

    Di Maio, Francesco; Zio, Enrico; Smith, Curtis; Rychkov, Valentin

    2015-07-06

    The present special issue contains an overview of the research in the field of Integrated Deterministic and Probabilistic Safety Assessment (IDPSA) of Nuclear Power Plants (NPPs). Traditionally, safety regulation for NPPs design and operation has been based on Deterministic Safety Assessment (DSA) methods to verify criteria that assure plant safety in a number of postulated Design Basis Accident (DBA) scenarios. Referring to such criteria, it is also possible to identify those plant Structures, Systems, and Components (SSCs) and activities that are most important for safety within those postulated scenarios. Then, the design, operation, and maintenance of these “safety-related” SSCs and activities are controlled through regulatory requirements and supported by Probabilistic Safety Assessment (PSA).

  19. Integrated deterministic and probabilistic safety analysis for safety assessment of nuclear power plants

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

    Di Maio, Francesco; Zio, Enrico; Smith, Curtis; Rychkov, Valentin

    2015-07-06

    The present special issue contains an overview of the research in the field of Integrated Deterministic and Probabilistic Safety Assessment (IDPSA) of Nuclear Power Plants (NPPs). Traditionally, safety regulation for NPPs design and operation has been based on Deterministic Safety Assessment (DSA) methods to verify criteria that assure plant safety in a number of postulated Design Basis Accident (DBA) scenarios. Referring to such criteria, it is also possible to identify those plant Structures, Systems, and Components (SSCs) and activities that are most important for safety within those postulated scenarios. Then, the design, operation, and maintenance of these “safety-related” SSCs andmore » activities are controlled through regulatory requirements and supported by Probabilistic Safety Assessment (PSA).« less

  20. Nuclear Safety Research and Development (NSR&D) Program | Department of

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

    Energy Safety Research and Development (NSR&D) Program Nuclear Safety Research and Development (NSR&D) Program The Nuclear Safety Research and Development (NSR&D) Program is managed by the Office of Nuclear Safety, within the Office of Environment, Health, Safety and Security (AU) to provide corporate-level leadership supporting nuclear safety research and development throughout the Department of Energy (DOE). The NSR&D Program also consults with the Nuclear Safety Council,

  1. Safety and performance enhancement circuit for primary explosive detonators

    DOE Patents [OSTI]

    Davis, Ronald W.

    2006-04-04

    A safety and performance enhancement arrangement for primary explosive detonators. This arrangement involves a circuit containing an energy storage capacitor and preset self-trigger to protect the primary explosive detonator from electrostatic discharge (ESD). The circuit does not discharge into the detonator until a sufficient level of charge is acquired on the capacitor. The circuit parameters are designed so that normal ESD environments cannot charge the protection circuit to a level to achieve discharge. When functioned, the performance of the detonator is also improved because of the close coupling of the stored energy.

  2. Definition and means of maintaining the ventilation system confinement portion of the PFP safety envelope

    SciTech Connect (OSTI)

    Dick, J.D.; Grover, G.A.; O`Brien, P.M., Fluor Daniel Hanford

    1997-03-05

    The Plutonium Finishing Plant Heating Ventilation and Cooling system provides for the confinement of radioactive releases to the environment and provides for the confinement of radioactive contamination within designated zones inside the facility. This document identifies the components and procedures necessary to ensure the HVAC system provides these functions. Appendices E through J provide a snapshot of non-safety class HVAC equipment and need not be updated when the remainder of the document and Appendices A through D are updated.

  3. Beyond Design Basis Events | Department of Energy

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

    Beyond Design Basis Events Beyond Design Basis Events Beyond Design Basis Events Following the March 2011 Fukushima Daiichi nuclear plant accident in Japan, DOE embarked upon several initiatives to investigate the safety posture of its nuclear facilities relative to beyond design basis events (BDBEs). These initiatives included issuing Safety Bulletin 2011-01, Events Beyond Design Safety Basis Analysis, and conducting two DOE nuclear safety workshops. DOE also issued two reports documenting the

  4. Perspectives on reactor safety

    SciTech Connect (OSTI)

    Haskin, F.E.; Camp, A.L.

    1994-03-01

    The US Nuclear Regulatory Commission (NRC) maintains a technical training center at Chattanooga, Tennessee to provide appropriate training to both new and experienced NRC employees. This document describes a one-week course in reactor, safety concepts. The course consists of five modules: (1) historical perspective; (2) accident sequences; (3) accident progression in the reactor vessel; (4) containment characteristics and design bases; and (5) source terms and offsite consequences. The course text is accompanied by slides and videos during the actual presentation of the course.

  5. safety and security | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    safety and security

  6. AFR-100 safety analyses

    SciTech Connect (OSTI)

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

    2012-07-01

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

  7. Complete Safety Training

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

    Complete Safety Training Print Facility Safety Training Required for ALL Users Users must register with the ALS to obtain an LBNL ID number before they can complete safety training...

  8. Dam Safety 2015

    Broader source: Energy.gov [DOE]

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

  9. Industrial Safety | The Ames Laboratory

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

    General Safety includes traditional safety disciplines such as machine guarding, personal protective equipment (PPE), electrical safety, accident prevention and investigation, ...

  10. NEW - DOE O 420.1 Chg 1, Facility Safety

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

    The Order establishes facility and programmatic safety requirements for DOE and NNSA for nuclear safety design criteria, fire protection, criticality safety, natural phenomena hazards (NPH) mitigation, and System Engineer Program. This Page Change is limited in scope to changes necessary to invoke DOE-STD-1104, Review and Approval of Nuclear Facility Safety Basis and Safety Design Basis Document, and revised DOE-STD-3009-2014, Preparation of Nonreactor Nuclear Facility Documented Safety Analysis as required methods. DOE O 420.1C Chg 1, dated 2-27-15, cancels DOE O 420.1C, dated 12-4-12.

  11. NREL Earns Prestigious Safety and Environmental Certifications - News

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

    Releases | NREL Earns Prestigious Safety and Environmental Certifications February 15, 2012 The U.S. Department of Energy's National Renewable Energy Laboratory (NREL) has received three significant certifications demonstrating the lab's commitment to the environment, safety, and management excellence. Certifications earned by NREL include: ISO 14001:2004 (environment); ISO 9001:2008 (quality); and OHSAS 18001 (health and safety). In July 2011, a team of external auditors from NSF

  12. NREL Recommended for Prestigious Safety and Environmental Certifications -

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

    News Releases | NREL Recommended for Prestigious Safety and Environmental Certifications June 10, 2014 The Energy Department's National Renewable Energy Laboratory (NREL) has been recommended for recertification to three significant international standards demonstrating the laboratory's commitment to the environment, safety, and quality excellence. The management system certifications include: ISO 14001:2004 (environment); OHSAS 18001:2007 (health and safety), and ISO 9001:2008 (quality,

  13. Y-12 Sustainable Design Principles for Building Design and Construction

    SciTech Connect (OSTI)

    Jackson, J. G.

    2008-11-01

    B&W Y-12 is committed to modernizing the Y-12 complex to meet future needs with a sustainable and responsive infrastructure and to integrating sustainability principles and practices into Y-12 work (Y72-001, B&W Y-12 Environmental, Safety and Health Policy). This commitment to sustainability and specifically sustainable design of buildings is also incorporated into Presidential Executive Orders (EO), DOE Orders (DOE O), and goals. Sustainable building design is an approach to design, construct, and operate facilities in an efficient and environmentally sound manner that will produce a healthful, resource-efficient and productive working environment that is inherently protective of the environment. The DOE has established the following 5 Guiding Principles for High Performance Sustainable Building (HPSB), and has issued directives that require Y-12 to incorporate the principles and a number of supporting specific practices and techniques into building design, construction and renovation projects: (1) Employ Integrated Design Principles; (2) Optimize Energy Performance; (3) Protect and Conserve Water; (4) Enhance Indoor Environmental Quality; and (5) Reduce Environmental Impact of Materials. The purpose of this document is to present the required sustainable building principles, practices and techniques, summarize the key drivers for incorporating them into Y-12 projects, and present additional recommendations and resources that can be used to support sustainable buildings to enhance the environmental and economic performance of the Y-12 Complex.

  14. Nuclear Safety | Department of Energy

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

    Nuclear Safety Nuclear Safety The Office of Nuclear Safety establishes and maintains nuclear safety policy, requirements, and guidance including policy and requirements relating to ...

  15. Hydrogen Safety Panel

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

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

  16. Material Safety Data Sheets

    Broader source: Energy.gov [DOE]

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

  17. Integrated Safety & Environmental Management System | Stanford Synchrotron

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

    Radiation Lightsource Integrated Safety & Environmental Management System How do you plan for SAFETY in your job? In an effort to provide a formal and organized process to manage all aspects of Environment, Safety and Health (ES&H) issues at its laboratories, the DOE developed the Integrated Safety and Environmental Management System (ISEMS). In short, it's a process that allows people (such as staff and Users) at all levels to plan, perform, assess and improve their implementation

  18. Enterprise Assessments Review of Explosives Safety Program Implementation

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

    at the Pantex Plant - November 2015 | Department of Energy Explosives Safety Program Implementation at the Pantex Plant - November 2015 Enterprise Assessments Review of Explosives Safety Program Implementation at the Pantex Plant - November 2015 November 2015 Review of the Explosives Safety Program Implementation at the Pantex Plant The U.S. Department of Energy (DOE) Office of Enterprise Assessments (EA), Office of Environment, Safety and Health Assessments, conducted an independent review

  19. SEISMIC ANALYSIS FOR PRECLOSURE SAFETY

    SciTech Connect (OSTI)

    E.N. Lindner

    2004-12-03

    The purpose of this seismic preclosure safety analysis is to identify the potential seismically-initiated event sequences associated with preclosure operations of the repository at Yucca Mountain and assign appropriate design bases to provide assurance of achieving the performance objectives specified in the Code of Federal Regulations (CFR) 10 CFR Part 63 for radiological consequences. This seismic preclosure safety analysis is performed in support of the License Application for the Yucca Mountain Project. In more detail, this analysis identifies the systems, structures, and components (SSCs) that are subject to seismic design bases. This analysis assigns one of two design basis ground motion (DBGM) levels, DBGM-1 or DBGM-2, to SSCs important to safety (ITS) that are credited in the prevention or mitigation of seismically-initiated event sequences. An application of seismic margins approach is also demonstrated for SSCs assigned to DBGM-2 by showing a high confidence of a low probability of failure at a higher ground acceleration value, termed a beyond-design basis ground motion (BDBGM) level. The objective of this analysis is to meet the performance requirements of 10 CFR 63.111(a) and 10 CFR 63.111(b) for offsite and worker doses. The results of this calculation are used as inputs to the following: (1) A classification analysis of SSCs ITS by identifying potential seismically-initiated failures (loss of safety function) that could lead to undesired consequences; (2) An assignment of either DBGM-1 or DBGM-2 to each SSC ITS credited in the prevention or mitigation of a seismically-initiated event sequence; and (3) A nuclear safety design basis report that will state the seismic design requirements that are credited in this analysis. The present analysis reflects the design information available as of October 2004 and is considered preliminary. The evolving design of the repository will be re-evaluated periodically to ensure that seismic hazards are properly evaluated and identified. This document supersedes the seismic classifications, assignments, and computations in ''Seismic Analysis for Preclosure Safety'' (BSC 2004a).

  20. Curtis Wynne Earns Certification as Safety Professional

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

    Curtis C. Wynne Earns Certification as Safety Professional CARLSBAD, N.M., May 24, 2001 - Curtis C. Wynne of Westinghouse TRU Solutions LLC (WTS) has earned designation as a...

  1. Nuclear Safety Research and Development Proposal Review and Prioritization and Criteria

    Energy Savers [EERE]

    Nuclear Safety Research and Development Proposal Review and Prioritization Process and Criteria Nuclear Safety Research and Development Program Office of Nuclear Safety Office of Environment, Health, Safety, and Security U.S. Department of Energy December 2015 NSR&D Proposal Review and Prioritization Process and Criteria 2 | P a g e Nuclear Safety Research and Development Program 1. Introduction Per the Department of Energy (DOE) Nuclear Safety Research and Development (NSR&D) Program

  2. Facility Safety (9-23-10)--Withdrawn

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

    2010-09-23

    Withdrawn, 5-19-2014--This approval includes revision of the three implementing Guides: DOE G 420.1-1, Nonreactor Nuclear Safety Design Criteria and Explosive Safety Criteria Guide for Use with DOE O 420.1, Facility Safety; DOE G 420.1-2, Guide for the Mitigation of Natural Phenomena Hazards for DOE Nuclear Facilities and NonNuclear Facilities; and DOE G 420.1-3, Implementation Guide for DOE Fire Protection and Emergency Services Programs for Use with DOE O 420.1B, Facility Safety

  3. Criticality Safety | Department of Energy

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

    Services » Nuclear Safety » Criticality Safety Criticality Safety Nuclear Safety Basis The Nuclear Facility Safety Program establishes and maintains the DOE requirements for nuclear criticality safety. The DOE detailed requirements for criticality safety are contained in Section 4.3 of the DOE Order 420.1,Facility Safety. Criticality safety requirements are based on the documented safety analysis required by 10 CFR 830, Subpart B. Related Links 10 CFR 830, Nuclear Safety Management American

  4. Safety Management System Policy

    Energy Savers [EERE]

    Health, Safety and Security U.S. Department of Energy POLICY Washington, D.C. Approved: 4-25-11 SUBJECT: INTEGRATED SAFETY MANAGEMENT POLICY PURPOSE AND SCOPE To establish the Department of Energy's (DOE) expectation for safety, 1 including integrated safety management that will enable the Department's mission goals to be accomplished efficiently while ensuring safe operations at all departmental facilities and activities. This Policy cancels and supersedes DOE Policy (P) 411.1, Safety

  5. Nuclear Safety Regulatory Framework

    Energy Savers [EERE]

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

  6. Complete Safety Training

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

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

  7. Complete Safety Training

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

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

  8. Complete Safety Training

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

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

  9. Complete Safety Training

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

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

  10. Complete Safety Training

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

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

  11. Complete Safety Training

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

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

  12. Vehicle Battery Safety Roadmap Guidance

    SciTech Connect (OSTI)

    Doughty, D. H.

    2012-10-01

    The safety of electrified vehicles with high capacity energy storage devices creates challenges that must be met to assure commercial acceptance of EVs and HEVs. High performance vehicular traction energy storage systems must be intrinsically tolerant of abusive conditions: overcharge, short circuit, crush, fire exposure, overdischarge, and mechanical shock and vibration. Fail-safe responses to these conditions must be designed into the system, at the materials and the system level, through selection of materials and safety devices that will further reduce the probability of single cell failure and preclude propagation of failure to adjacent cells. One of the most important objectives of DOE's Office of Vehicle Technologies is to support the development of lithium ion batteries that are safe and abuse tolerant in electric drive vehicles. This Roadmap analyzes battery safety and failure modes of state-of-the-art cells and batteries and makes recommendations on future investments that would further DOE's mission.

  13. AWEA Wind Project Operations and Maintenance and Safety Seminar

    Broader source: Energy.gov [DOE]

    The AWEA Wind Project O&M and Safety Seminar is designed for owners, operators, turbine manufactures, material suppliers, wind technicians, managers, supervisors, engineers, and occupational...

  14. The Process, Methods and Tool Used To Integrate Safety During...

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

    The Process, Methods and Tool Used To Integrate Safety During Design of a Category 2 Nuclear Facility August 2009 Presenter: Lynn J. Harkey, SDIT Project Engineer, Uranium ...

  15. AGING FACILITY CRITICALITY SAFETY CALCULATIONS

    SciTech Connect (OSTI)

    C.E. Sanders

    2004-09-10

    The purpose of this design calculation is to revise and update the previous criticality calculation for the Aging Facility (documented in BSC 2004a). This design calculation will also demonstrate and ensure that the storage and aging operations to be performed in the Aging Facility meet the criticality safety design criteria in the ''Project Design Criteria Document'' (Doraswamy 2004, Section 4.9.2.2), and the functional nuclear criticality safety requirement described in the ''SNF Aging System Description Document'' (BSC [Bechtel SAIC Company] 2004f, p. 3-12). The scope of this design calculation covers the systems and processes for aging commercial spent nuclear fuel (SNF) and staging Department of Energy (DOE) SNF/High-Level Waste (HLW) prior to its placement in the final waste package (WP) (BSC 2004f, p. 1-1). Aging commercial SNF is a thermal management strategy, while staging DOE SNF/HLW will make loading of WPs more efficient (note that aging DOE SNF/HLW is not needed since these wastes are not expected to exceed the thermal limits form emplacement) (BSC 2004f, p. 1-2). The description of the changes in this revised document is as follows: (1) Include DOE SNF/HLW in addition to commercial SNF per the current ''SNF Aging System Description Document'' (BSC 2004f). (2) Update the evaluation of Category 1 and 2 event sequences for the Aging Facility as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2004c, Section 7). (3) Further evaluate the design and criticality controls required for a storage/aging cask, referred to as MGR Site-specific Cask (MSC), to accommodate commercial fuel outside the content specification in the Certificate of Compliance for the existing NRC-certified storage casks. In addition, evaluate the design required for the MSC that will accommodate DOE SNF/HLW. This design calculation will achieve the objective of providing the criticality safety results to support the preliminary design of the Aging Facility. As the ongoing design evolution remains fluid, the results from this design calculation should be evaluated for applicability to any new or modified design. Consequently, the results presented in this document are limited to the current design. The information contained in this document was developed by Environmental and Nuclear Engineering and is intended for the use of Design and Engineering in its work regarding the various criticality related activities performed in the Aging Facility. Yucca Mountain Project personnel from Environmental and Nuclear Engineering should be consulted before the use of the information for purposes other than those stated herein or use by individuals other than authorized personnel in Design and Engineering.

  16. TWRS safety program plan

    SciTech Connect (OSTI)

    Calderon, L.M., Westinghouse Hanford

    1996-08-01

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

  17. Floating LNG plant will stress reliability and safety

    SciTech Connect (OSTI)

    Kinney, C.D.; Schulz, H.R.; Spring, W.

    1997-07-01

    Mobil has developed a unique floating LNG plant design after extensive studies that set safety as the highest priority. The result is a production, storage and offloading platform designed to produce 6 million tons per year of LNG and up to 55,000 bpd of condensate from 1 Bcfd of feed gas. All production and off-loading equipment is supported by a square donut-shaped concrete hull, which is spread-moored. The hull contains storage tanks for 250,000 m{sup 3} of LNG, 6540,000 bbl of condensate and ballast water. Both LNG and condensate can be directly offloaded to shuttle tankers. Since the plant may be moved to produce from several different gas fields during its life, the plant and barge were designed to be generic. It can be used at any location in the Pacific Rim, with up to 15% CO{sub 2}, 100 ppm H{sub 2}S, 55 bbl/MMcf condensate and 650 ft water depth. It can be modified to handle other water depths, depending upon the environment. In addition, it is much more economical than an onshore grassroots LNG plant, with potential capital savings of 25% or more. The paper describes the machinery, meteorology and oceanography, and safety engineering.

  18. Status of Safety and Environmental Activities in the US Fusion Program

    SciTech Connect (OSTI)

    David A. Petti; Susana Reyes; Lee C. Cadwallader; Jeffery F. Latkowski

    2004-09-01

    This paper presents an overview of recent safety efforts in both magnetic and inertial fusion energy. Safety has been a part of fusion design and operations since the inception of fusion research. Safety research and safety design support have been provided for a variety of experiments in both the magnetic and inertial fusion programs. The main safety issues are reviewed, some recent safety highlights are discussed and the programmatic impacts that safety research has had are presented. Future directions in the safety and environmental area are proposed.

  19. Use of DRACS to Enhance HTGRs Passive Safety and Economy

    SciTech Connect (OSTI)

    Haihua Zhao; Hongbin Zhang; Ling Zou

    2011-06-01

    This paper discusses the use of DRACS to Enhance HTGRs Passive Safety and Economy. One of the important requirements for Gen. IV High Temperature Gas Cooled Reactors (HTGR) is passive safety. Currently all the HTGR designs use Reactor Vessel Auxiliary Cooling System (RVACS) for passive decay heat removal. [1] The decay heat first is transferred to core barrel by conduction and radiation, and then to reactor vessel by thermal radiation and convection; finally the decay heat is transferred to natural circulated air or water systems. RVACS can be characterized as a surface based decay heat removal system. Similar concepts have been widely used in sodium cooled fast reactor (SFR) designs, advanced light water reactors like AP1000. The RVACS is especially suitable for smaller power reactors since small systems have relatively larger surface area. RVACS tends to be less expensive. However, it limits the largest achievable power level for modular HTGRs due to the mismatch between the reactor power (proportional to volume) and decay heat removal capability (proportional to surface). When the relative decay heat removal capability is reduced, the peak fuel temperature increases, even close to the design limit. Annual designs with internal reflector can mitigate this effect therefore further increase the power. Another way to increase power is to increase power density. However, it is also limited by the decay heat removal capability. Besides safety, HTGRs also need to be economical in order to compete with other reactor designs. The limit of decay heat removal capability set by using RVACS has affected the economy of HTGRs. Forsberg [2] pointed out other disadvantages of using RVACS such as conflicting functional requirements for the reactor vessel and scaling distortion for integral effect test of the system performance. A potential alternative solution is to use a volume based passive decay removal system, call Direct Reactor Auxiliary Cooling Systems (DRACS), to remove or mitigate the limitation on decay heat removal capability. DRACS has been widely used in SFR designs and in liquid salt cooled high temperature reactors. The containment cooling system in BWR is another example of volume based decay removal systems. DRACS composes of natural circulation loops with two sets of heat exchangers, one in reactor side and another is in environment side. DRACS has the benefits of increasing the power as needed (scalability) and modularity. This paper introduces the concept of using DRACS to enhance HTGRs passive safety and economy.

  20. Assessing Beyond Design Basis Seismic Events and Implications...

    Office of Environmental Management (EM)

    Defense Nuclear Facilities Safety Board Topics Covered: Department of Energy Approach to Natural Phenomena Hazards Analysis and Design (Seismic) Design Basis and Beyond Design...

  1. Novel Cleanup Agents Designed Exclusively for Oil Field Membrane Filtration Systems Low Cost Field Demonstrations of Cleanup Agents in Controlled Experimental Environments

    SciTech Connect (OSTI)

    David Burnett; Harold Vance

    2007-08-31

    The goal of our project is to develop innovative processes and novel cleaning agents for water treatment facilities designed to remove fouling materials and restore micro-filter and reverse osmosis (RO) membrane performance. This project is part of Texas A&M University's comprehensive study of the treatment and reuse of oilfield brine for beneficial purposes. Before waste water can be used for any beneficial purpose, it must be processed to remove contaminants, including oily wastes such as residual petroleum hydrocarbons. An effective way of removing petroleum from brines is the use of membrane filters to separate oily waste from the brine. Texas A&M and its partners have developed highly efficient membrane treatment and RO desalination for waste water including oil field produced water. We have also developed novel and new cleaning agents for membrane filters utilizing environmentally friendly materials so that the water from the treatment process will meet U.S. EPA drinking water standards. Prototype micellar cleaning agents perform better and use less clean water than alternate systems. While not yet optimized, the new system restores essentially complete membrane flux and separation efficiency after cleaning. Significantly the amount of desalinated water that is required to clean the membranes is reduced by more than 75%.

  2. Y-12 receives two significant safety awards | Y-12 National Security...

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

    Yvonne Bishop, acting vice president of B&W Y-12's Environment, Safety and Health. "We care about our own safety and that of our co-workers." The Star of Excellence recognizes...

  3. Final Design RM | Department of Energy

    Energy Savers [EERE]

    Final Design RM Final Design RM The Final Design (FD) Review Module (RM) is a tool that assists Department of Energy (DOE) federal project review teams in evaluating the technical sufficiency of the final design prior to CD-3 approval. The FD RM focuses on the engineering design, technology, safety, and quality assurance to determine whether it meets overall design commitments, technical and safety requirements. PDF icon Final Design RM More Documents & Publications Seismic Design

  4. Automatic safety rod for reactors

    DOE Patents [OSTI]

    Germer, John H. (San Jose, CA)

    1988-01-01

    An automatic safety rod for a nuclear reactor containing neutron absorbing material and designed to be inserted into a reactor core after a loss-of-core flow. Actuation is based upon either a sudden decrease in core pressure drop or the pressure drop decreases below a predetermined minimum value. The automatic control rod includes a pressure regulating device whereby a controlled decrease in operating pressure due to reduced coolant flow does not cause the rod to drop into the core.

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

    SciTech Connect (OSTI)

    EVANS, C B

    2004-12-21

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

  6. Optical Safety of LEDs

    SciTech Connect (OSTI)

    none,

    2013-06-01

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

  7. Hydrogen Safety Knowledge Tools

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

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

  8. Office of Nuclear Safety

    Broader source: Energy.gov [DOE]

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

  9. Program Analyst (Transportation Safety)

    Broader source: Energy.gov [DOE]

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

  10. Nuclear Explosive Safety Manual

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

    2009-04-14

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

  11. Construction Safety Advisory Committee

    Broader source: Energy.gov [DOE]

    This charter describes the function and role of the Department of Energy (DOE) Construction Safety Advisory Committee (CSAC).

  12. Index of /safety

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

    safety Icon Name Last modified Size Description [DIR] Parent Directory - [DIR] hazardousradioactive..> 17-Apr-2013 12:29 -

  13. Chemical Safety Program

    Office of Energy Efficiency and Renewable Energy (EERE)

    The Department of Energy's (DOE's) Chemical Safety Program provides a forum for the exchange of best practices, lessons learned, and guidance in the area of chemical management. This content is supported by the Chemical Safety Topical Committee which was formed to identify chemical safety-related issues of concern to the DOE and pursue solutions to issues identified.

  14. Radiation Safety Poster | Y-12 National Security Complex

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

    Radiation Safety Poster Radiation Safety Poster Radiation Safety Poster

  15. Topsides equipment, operating flexibility key floating LNG design

    SciTech Connect (OSTI)

    Yost, K.; Lopez, R.; Mok, J.

    1998-03-09

    Use of a large-scale floating liquefied natural gas (LNG) plant is an economical alternative to an onshore plant for producing from an offshore field. Mobil Technology Co., Dallas, has advanced a design for such a plant that is technically feasible, economical, safe, and reliable. Presented were descriptions of the general design basis, hull modeling and testing, topsides and storage layouts, and LNG offloading. But such a design also presents challenges for designing topsides equipment in an offshore environment and for including flexibility and safety. These are covered in this second article. Mobil`s floating LNG plant design calls for a square concrete barge with a moon-pool in the center. It is designed to produce 6 million tons/year of LNG with up to 55,000 b/d of condensate from 1 bcfd of raw feed gas.

  16. FHR Generic Design Criteria

    SciTech Connect (OSTI)

    Flanagan, George F; Holcomb, David Eugene; Cetiner, Sacit M

    2012-06-01

    The purpose of this document is to provide an initial, focused reference to the safety characteristics of and a licensing approach for Fluoride-Salt-Cooled High-Temperature Reactors (FHRs). The document does not contain details of particular reactor designs nor does it attempt to identify or classify either design basis or beyond design basis accidents. Further, this document is an initial attempt by a small set of subject matter experts to document the safety and licensing characteristics of FHRs for a larger audience. The document is intended to help in setting the safety and licensing research, development, and demonstration path forward. Input from a wider audience, further technical developments, and additional study will be required to develop a consensus position on the safety and licensing characteristics of FHRs. This document begins with a brief overview of the attributes of FHRs and then a general description of their anticipated safety performance. Following this, an overview of the US nuclear power plant approval process is provided that includes both test and power reactors, as well as the role of safety standards in the approval process. The document next describes a General Design Criteria (GDC) - based approach to licensing an FHR and provides an initial draft set of FHR GDCs. The document concludes with a description of a path forward toward developing an FHR safety standard that can support both a test and power reactor licensing process.

  17. FHR Generic Design Criteria

    SciTech Connect (OSTI)

    Flanagan, G.F.; Holcomb, D.E.; Cetiner, S.M.

    2012-06-15

    The purpose of this document is to provide an initial, focused reference to the safety characteristics of and a licensing approach for Fluoride-Salt-Cooled High-Temperature Reactors (FHRs). The document does not contain details of particular reactor designs nor does it attempt to identify or classify either design basis or beyond design basis accidents. Further, this document is an initial attempt by a small set of subject matter experts to document the safety and licensing characteristics of FHRs for a larger audience. The document is intended to help in setting the safety and licensing research, development, and demonstration path forward. Input from a wider audience, further technical developments, and additional study will be required to develop a consensus position on the safety and licensing characteristics of FHRs. This document begins with a brief overview of the attributes of FHRs and then a general description of their anticipated safety performance. Following this, an overview of the US nuclear power plant approval process is provided that includes both test and power reactors, as well as the role of safety standards in the approval process. The document next describes a General Design Criteria (GDC)–based approach to licensing an FHR and provides an initial draft set of FHR GDCs. The document concludes with a description of a path forward toward developing an FHR safety standard that can support both a test and power reactor licensing process.

  18. Safety Cinema: Safety Videos: Los Alamos National Laboratory

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

    Safety CinemaTM VideosINDUSTRIAL HYGIENE AND SAFETY Safety Videos » Safety Cinema Safety Videos Home Safety Cinema Human Beings Beryllium Integrated Safety CONTACTS Occupational Safety and Health Division Office 505 606-0295 Video Contact Lorrie Bonds Lopez safetyvideos@lanl.gov 505 667-0216 Safety Cinema Play videos - download flyers and more Safety practices for work and home, supporting the well-being of every worker throughout each day. safety cinema logo "Let's take care of ourselves

  19. Safety Recall on 2 Types of APC Surge Protectors | Jefferson Lab

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

    Safety Recall on 2 Types of APC Surge Protectors Consumer Product Safety Recall Notice on 2 Types of APC Surge Protectors: Action Required This Product Safety Recall Notice is being sent on behalf of Jefferson Lab's Environment, Safety, Health and Quality (EHS&Q) Division. Everyone at Jefferson Lab, be advised: The Consumer Product Safety Commission has issued the recall of two (2) different types of American Power Conversion (APC) multi-plug surge protectors. The recall involves APC7 and

  20. Secretarial Policy Statement on Nanoscale Safety

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

    2005-09-15

    The safety of its employees, the public, and the environment is the Department's number one priority. This policy statement is issued to establish a framework for working safely with nanomaterials. Does not cancel/supersede other directives. Certified 10-2-14

  1. Safety analysis report for the Waste Storage Facility. Revision 2

    SciTech Connect (OSTI)

    Bengston, S.J.

    1994-05-01

    This safety analysis report outlines the safety concerns associated with the Waste Storage Facility located in the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The three main objectives of the report are: define and document a safety basis for the Waste Storage Facility activities; demonstrate how the activities will be carried out to adequately protect the workers, public, and environment; and provide a basis for review and acceptance of the identified risk that the managers, operators, and owners will assume.

  2. Office of Nuclear Safety and Environmental Assessments | Department of

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

    Energy Nuclear Safety and Environmental Assessments Office of Nuclear Safety and Environmental Assessments MISSION The Office of Nuclear Safety and Environmental Assessments conducts assessments to provide critical feedback and objective information on programs and performance in protecting our workers, the public and environment from radiological hazards with a focus on hazardous nuclear facilities and operations.This information provides assurance to our stakeholders and identifies areas

  3. Striving for Environmental, Security, Safety and Health and Sustainability

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

    Excellence | Department of Energy Striving for Environmental, Security, Safety and Health and Sustainability Excellence Striving for Environmental, Security, Safety and Health and Sustainability Excellence FE's FY 2011 Environment, Security, Safety and Health Annual Report. PDF icon FE's FY 2011 ESS&H Annual Report More Documents & Publications Fossil Energy Today - Fourth Quarter, 2012 Fossil Energy Today - Third Quarter, 2011 Inspection Report: IG-0693

  4. Office of Heath, Safety and Security Now Two New Offices

    Broader source: Energy.gov [DOE]

    To serve you better, DOE has structured the former HSS into to new organizations: the Office Independent Enterprise Assessment (IEA); and Office of Environment, Health, Safety and Security (EHSS).

  5. Improved Nuclear Safety Through International Standards

    SciTech Connect (OSTI)

    Doctor, Steven R.; Moffitt, Robert L.; Taylor, Theodore T.; Trosman, Grigory

    1999-12-01

    This paper describes the 1986 Chornobyl accident, notes some of its effects, and reviews the cause. International efforts to improve reactor safety to prevent another such accident are listed. The U.S. Department of Energy (DOE) program to improve the safety of Soviet-designed nuclear power plants is outlined, followed by a more detailed description of the specific projects related to nondestructive evaluation. Future directions are proposed, and conclusions are provided.

  6. Fast reactor safety: proceedings of the international topical meeting. Volume 1

    SciTech Connect (OSTI)

    Not Available

    1985-07-01

    The emphasis of this meeting was on the safety-related aspects of fast reactor design, analysis, licensing, construction, and operation. Relative to past meetings, there was less emphasis on the scientific and technological basis for accident assessment. Because of its broad scope, the meeting attracted 217 attendees from a wide cross section of the design, safety analysis, and safety technology communities. Eight countries and two international organizations were represented. A total of 126 papers were presented, with contributions from the United States, France, Japan, the United Kingdom, Germany, and Italy. Sessions covered in Volume 1 include: impact of safety and licensing considerations on fast reactor design; safety aspects of innovative designs; intra-subassembly behavior; operational safety; design accommodation of seismic and other external events; natural circulation; safety design concepts; safety implications derived from operational plant data; decay heat removal; and assessment of HCDA consequences.

  7. Criticality safety basics, a study guide

    SciTech Connect (OSTI)

    V. L. Putman

    1999-09-01

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

  8. User Environment

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

    Getting Started Configuration User Environment Programming Running Jobs File Storage Software and Tools Performance and Optimization Retirement Plans Jesup Dirac Edison Phase I Euclid - Retired 01/31/2013 Franklin - Retired 04/30/12 Bassi Storage & File Systems Data & Analytics Connecting to NERSC Queues and Scheduling Job Logs & Statistics Application Performance Training & Tutorials Software Policies User Surveys NERSC Users Group User Announcements Help Staff Blogs Request

  9. Framework Development Supporting the Safety Portal

    SciTech Connect (OSTI)

    Prescott, Steven Ralph; Kvarfordt, Kellie Jean; Vang, Leng; Smith, Curtis Lee

    2015-07-01

    In a collaborating scientific research arena it is important to have an environment where analysts have access to a shared repository of information, documents, and software tools, and be able to accurately maintain and track historical changes in models. The new Safety Portal cloud-based environment will be accessible remotely from anywhere regardless of computing platforms given that the platform has available Internet access and proper browser capabilities. Information stored at this environment would be restricted based on user assigned credentials. This report discusses current development of a cloud-based web portal for PRA tools.

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

    SciTech Connect (OSTI)

    Timothy J. Leahy

    2010-06-01

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

  11. Enterprise Assessments Targeted Review of the Safety System Management of the Secondary Confinement System and Power Distribution Safety System at the Y-12 National Security Complex Highly Enriched Uranium Materials Facility … December 2015

    Energy Savers [EERE]

    Targeted Review of the Safety System Management of the Secondary Confinement System and Safety Significant Power Distribution System at the Y-12 National Security Complex Highly Enriched Uranium Materials Facility December 2015 Office of Nuclear Safety and Environmental Assessments Office of Environment, Safety and Health Assessments Office of Enterprise Assessments U.S. Department of Energy i Table of Contents Acronyms

  12. Thermal reactor safety

    SciTech Connect (OSTI)

    Not Available

    1980-06-01

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

  13. TWRS safety management plan

    SciTech Connect (OSTI)

    Popielarczyk, R.S., Westinghouse Hanford

    1996-08-01

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

  14. Hydrogen Technologies Safety Guide

    SciTech Connect (OSTI)

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

    2015-01-01

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

  15. Integrated Safety Management Safety Culture Resources | Department of

    Energy Savers [EERE]

    Energy Safety Culture Resources Integrated Safety Management Safety Culture Resources A collection of resources available in implementing ISM safety culture activities Safety from the Operator's Perspective: We are All in This Together (2005) Transcript, Keeping the Edge: Enhancing Performance Through Managing Culture (2003), Edgar H. Schein, Ph.D. Proceedings of the Advisory Committee on Reactor Safeguards Safety Culture Workshop (2003) Safety Culture in Nuclear Installations: Guidance for

  16. EM's Safety Chief Talks Safety Culture Improvements With EM Update |

    Office of Environmental Management (EM)

    Department of Energy Safety Chief Talks Safety Culture Improvements With EM Update EM's Safety Chief Talks Safety Culture Improvements With EM Update March 31, 2016 - 1:05pm Addthis EM Safety, Security, and Quality Programs Deputy Assistant Secretary James Hutton EM Safety, Security, and Quality Programs Deputy Assistant Secretary James Hutton WASHINGTON, D.C. - EM Safety, Security, and Quality Programs Deputy Assistant Secretary James Hutton recently spoke with EM Update about the EM

  17. DOE Explosives Safety Manual

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

    1996-03-29

    This Manual describes DOE's explosives safety requirements applicable to operations involving the development, testing, handling, and processing of explosives or assemblies containing explosives.

  18. safety analysis report

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

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

  19. safety of space

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

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

  20. Safety Staff Contact Information

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

    Safety Staff Contact Information Print Contact Extension Location CONTROL ROOM (247) 4969 80-140 Floor Operations Floor Operators 7464 (RING) 80-159 Building Manager Jeff Troutman...

  1. SSRL Safety Office Memo

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

    new regulations (NFPA70E) which outline the "Standard for Electrical Safety in the Workplace". Specifically it requires that the Arc Flash Hazard be categorized and PPE stated...

  2. Lift truck safety review

    SciTech Connect (OSTI)

    Cadwallader, L.C.

    1997-03-01

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

  3. FEOSH Annual Safety Training

    Broader source: Energy.gov [DOE]

    The Department of Energy (DOE) has developed an annual safety training course that is mandatory for all current DOE Federal employees and for each new hire.

  4. Aviation Management and Safety

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

    2011-06-15

    To establish a policy framework that will ensure safety, efficiency and effectiveness of government or contractor aviation operations. Supersedes DOE O 440.2B.

  5. Aviation Management and Safety

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

    2011-06-15

    To establish a policy framework that will ensure safety, efficiency and effectiveness of government or contractor aviation operations. Cancels DOE O 440.2B.

  6. Pressure Safety Program Implementation at ORNL

    SciTech Connect (OSTI)

    Lower, Mark; Etheridge, Tom; Oland, C. Barry

    2013-01-01

    The Oak Ridge National Laboratory (ORNL) is a US Department of Energy (DOE) facility that is managed by UT-Battelle, LLC. In February 2006, DOE promulgated worker safety and health regulations to govern contractor activities at DOE sites. These regulations, which are provided in 10 CFR 851, Worker Safety and Health Program, establish requirements for worker safety and health program that reduce or prevent occupational injuries, illnesses, and accidental losses by providing DOE contractors and their workers with safe and healthful workplaces at DOE sites. The regulations state that contractors must achieve compliance no later than May 25, 2007. According to 10 CFR 851, Subpart C, Specific Program Requirements, contractors must have a structured approach to their worker safety and health programs that at a minimum includes provisions for pressure safety. In implementing the structured approach for pressure safety, contractors must establish safety policies and procedures to ensure that pressure systems are designed, fabricated, tested, inspected, maintained, repaired, and operated by trained, qualified personnel in accordance with applicable sound engineering principles. In addition, contractors must ensure that all pressure vessels, boilers, air receivers, and supporting piping systems conform to (1) applicable American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (2004) Sections I through XII, including applicable code cases; (2) applicable ASME B31 piping codes; and (3) the strictest applicable state and local codes. When national consensus codes are not applicable because of pressure range, vessel geometry, use of special materials, etc., contractors must implement measures to provide equivalent protection and ensure a level of safety greater than or equal to the level of protection afforded by the ASME or applicable state or local codes. This report documents the work performed to address legacy pressure vessel deficiencies and comply with pressure safety requirements in 10 CFR 851. It also describes actions taken to develop and implement ORNL’s Pressure Safety Program.

  7. Preliminary safety evaluation of the advanced burner test reactor.

    SciTech Connect (OSTI)

    Dunn, F. E.; Fanning, T. H.; Cahalan, J. E.; Nuclear Engineering Division

    2006-09-15

    Results of a preliminary safety evaluation of the Advanced Burner Test Reactor (ABTR) pre-conceptual design are reported. The ABTR safety design approach is described. Traditional defense-in-depth design features are supplemented with passive safety performance characteristics that include natural circulation emergency decay heat removal and reactor power reduction by inherent reactivity feedbacks in accidents. ABTR safety performance in design-basis and beyond-design-basis accident sequences is estimated based on analyses. Modeling assumptions and input data for safety analyses are presented. Analysis results for simulation of simultaneous loss of coolant pumping power and normal heat rejection are presented and discussed, both for the case with reactor scram and the case without reactor scram. The analysis results indicate that the ABTR pre-conceptual design is capable of undergoing bounding design-basis and beyond-design-basis accidents without fuel cladding failures. The first line of defense for protection of the public against release of radioactivity in accidents remains intact with significant margin. A comparison and evaluation of general safety design criteria for the ABTR conceptual design phase are presented in an appendix. A second appendix presents SASSYS-1 computer code capabilities and modeling enhancements implemented for ABTR analyses.

  8. KiloPower Project - KRUSTY Experiment Nuclear Design (Technical...

    Office of Scientific and Technical Information (OSTI)

    KRUSTY design sensitivities; KRUSTY reactivity coefficients; KRUSTY criticality safety and control; KRUSTY core activationdose; and KRUSTY shielding, room activationdose. ...

  9. Safety equipment list for the light duty utility arm system

    SciTech Connect (OSTI)

    Barnes, G.A.

    1998-03-02

    The initial issue (Revision 0) of this Safety Equipment List (SEL) for the Light Duty Utility Arm (LDUA) requires an explanation for both its existence and its being what it is. All LDUA documentation leading up to creation of this SEL, and the SEL itself, is predicated on the LDUA only being approved for use in waste tanks designated as Facility Group 3, i.e., it is not approved for use in Facility Group 1 or 2 waste tanks. Facility Group 3 tanks are those in which a spontaneous or induced hydrogen gas release would be small, localized, and would not exceed 25% of the LFL when mixed with the remaining air volume in the dome space; exceeding these parameters is considered unlikely. Thus, from a NFPA flammable gas environment perspective the waste tank interior is not classified as a hazardous location. Furthermore, a hazards identification and evaluation (HNF-SD-WM-HIE-010, REV 0) performed for the LDUA system concluded that the consequences of actual LDUA system postulated accidents in Flammable Gas Facility Group 3 waste tanks would have either NO IMPACT or LOW IMPACT on the offsite public and onsite worker. Therefore, from a flammable gas perspective, there is not a rationale for classifying any of SSCs associated with the LDUA as either Safety Class (SC) or Safety Significant (SS) SSCs, which, by default, categorizes them as General Service (GS) SSCs. It follows then, based on current PHMC procedures (HNF-PRO-704 and HNF-IP-0842, Vol IV, Section 5.2) for SEL creation and content, and from a flammable gas perspective, that an SEL is NOT REQ@D HOWEVER!!! There is both a precedent and a prudency to capture all SSCS, which although GS, contribute to a Defense-In-Depth (DID) approach to the design and use of equipment in potentially flammable gas environments. This Revision 0 of the LDUA SEL has been created to capture these SSCs and they are designated as GS-DID in this document. The specific reasons for doing this are listed.

  10. Facility Safety | Department of Energy

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

    Facility Safety Facility Safety In addition to establishing nuclear safety requirements related to safety management programs that are essential to the safety of DOE nuclear facilities, the U.S. Department of Energy's (DOE) Office of Nuclear Facility Safety works proactively with headquarters and field offices to foster continuous improvement and nuclear safety excellence. In addition, the Office provides high quality, customer-oriented assistance that enables improved DOE program and field

  11. Facility Safety | Department of Energy

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

    Facility Safety Facility Safety In addition to establishing nuclear safety requirements related to safety management programs that are essential to the safety of DOE nuclear facilities, the U.S. Department of Energy's (DOE) Office of Nuclear Facility Safety works proactively with headquarters and field offices to foster continuous improvement and nuclear safety excellence. In addition, the Office provides high quality, customer-oriented assistance that enables improved DOE program and field

  12. CRAD, Facility Safety- Documented Safety Analysis

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) that can be used for assessment of a contractor's Documented Safety Analysis.

  13. CRAD, Facility Safety- Nuclear Facility Safety Basis

    Office of Energy Efficiency and Renewable Energy (EERE)

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) that can be used for assessment of a contractor's Nuclear Facility Safety Basis.

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

    SciTech Connect (OSTI)

    David Petti; Jim Kinsey; Dave Alberstein

    2014-01-01

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

  15. The color of safety

    SciTech Connect (OSTI)

    Carter, R.A.

    2006-06-15

    The industry's workforce is getting grayer as veteran miners approach retirement, and greener as new hires come onboard. Will the changing complexion of the industry affect future safety technology? The article discusses problems of noise, vibration, and communication faced by coal miners and reports some developments by manufacturers of mining equipment to improve health and safety. 1 fig., 4 photos.

  16. Integrated Safety Management Policy

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

    2011-04-25

    The policy establishes DOE's expectation for safety, including integrated safety management that will enable the Department’s mission goals to be accomplished efficiently while ensuring safe operations at all departmental facilities and activities. Supersedes DOE P 450.4, DOE P 411.1, DOE P 441.1, DOE P 450.2A, and DOE P 450.7

  17. Safety of Accelerator Facilities

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

    2001-01-08

    To establish accelerator-specific safety requirements which, when supplemented by other applicable safety and health requirements, will serve to prevent injuries and illnesses associated with Department of Energy (DOE) or National Nuclear Security Administration (NNSA) accelerator operations. Cancels DOE O 420.2. Canceled by DOE O 420.2B.

  18. Safety of Accelerator Facilities

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

    2004-07-23

    To establish accelerator-specific safety requirements which, when supplemented by other applicable safety and health requirements, will serve to prevent injuries and illnesses associated with Department of Energy (DOE) or National Nuclear Security Administration (NNSA) accelerator operations. Cancels DOE O 420.2A. Certified 5-13-08. Canceled by DOE O 420.2C.

  19. Managing a Process Safety Management inspection

    SciTech Connect (OSTI)

    Mulvey, N.P. [AcuTech Consulting, Inc., Princeton, NJ (United States)

    1995-12-31

    The Occupational Safety and Health Administration (OSHA) Process Safety Management (PSM) regulations (29 CFR {section} 1910.119) have been in effect for almost three years. State level risk management programs, in New Jersey, California, and Delaware have been in effect for over six years. More recently, Nevada and Louisiana have enacted process safety management programs. These regulations have had a significant impact on all phases of plant operations, including preliminary design, construction, startup, and operations. Through proper planning and the commitment of resources, many facilities are beginning to realize the benefits of well developed PSM programs. This paper will discuss in greater detail some of these benefits, and in particular, the subject of governmental inspections of facilities for process safety management programs.

  20. Trends in HFE Methods and Tools and Their Applicability to Safety Reviews

    SciTech Connect (OSTI)

    O'Hara, J.M.; Plott, C.; Milanski, J.; Ronan, A.; Scheff, S.; Laux, L.; and Bzostek, J.

    2009-09-30

    The U.S. Nuclear Regulatory Commission's (NRC) conducts human factors engineering (HFE) safety reviews of applicant submittals for new plants and for changes to existing plants. The reviews include the evaluation of the methods and tools (M&T) used by applicants as part of their HFE program. The technology used to perform HFE activities has been rapidly evolving, resulting in a whole new generation of HFE M&Ts. The objectives of this research were to identify the current trends in HFE methods and tools, determine their applicability to NRC safety reviews, and identify topics for which the NRC may need additional guidance to support the NRC's safety reviews. We conducted a survey that identified over 100 new HFE M&Ts. The M&Ts were assessed to identify general trends. Seven trends were identified: Computer Applications for Performing Traditional Analyses, Computer-Aided Design, Integration of HFE Methods and Tools, Rapid Development Engineering, Analysis of Cognitive Tasks, Use of Virtual Environments and Visualizations, and Application of Human Performance Models. We assessed each trend to determine its applicability to the NRC's review by considering (1) whether the nuclear industry is making use of M&Ts for each trend, and (2) whether M&Ts reflecting the trend can be reviewed using the current design review guidance. We concluded that M&T trends that are applicable to the commercial nuclear industry and are expected to impact safety reviews may be considered for review guidance development. Three trends fell into this category: Analysis of Cognitive Tasks, Use of Virtual Environments and Visualizations, and Application of Human Performance Models. The other trends do not need to be addressed at this time.

  1. Environment/Health/Safety (EHS): Report an Accident or Incident

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

    or 9-911 immediately or the emergency number on your desk phone if off site. Please stay on the line until it is answered. If calling from a cellular phone, call 911 and be...

  2. Our Commitment to Environment, Security, Safety and Health

    Broader source: Energy.gov [DOE]

    The Office of Fossil Energy is committed to conducting our mission to achieve the greatest benefit for all our stakeholders, including our employees and the public, while actively adhering to the...

  3. Environment/Health/Safety (EHS): Environmental Restoration Program...

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

    groundwater issues and the City of Berkeley for the technical review of underground storage tanks. Assessment and characterization of areas potentially contaminated with...

  4. Environment/Health/Safety (EHS): Radiation Protection Group:...

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

    be appointed by the Laboratory Director for three year renewable terms on the basis of knowledge of the principles and practices of the control of radiation hazards and on...

  5. Environment/Health/Safety (EHS): Radiation Protection Group:...

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

    David Shuh (CS) Amy Kronenberg (LSD) Jim O'Neil (LSD) Jeff Kortright (MSD) Henrik Scheller (PBD) John Christensen (ESD), SAC Liaison Marty White (NSD, PH), DSC Liaison Link to...

  6. Office of Environment, Safety and Health Evaluations Appraisal...

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

    procedures and methods specific to ES&H appraisals conducted by Independent Oversight. ... The processes described in this guide are used for all ES&H appraisals, including periodic ...

  7. Inspection Of Environment, Safety, And Health Management At The...

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

    Working Group FRAM Functions, Responsibilities, and Authorities Manual FY Fiscal Year HAC Hazards Analysis Checklist ... The team performs inspections that focus on workplace ...

  8. Safety assessment of spent-fuel transportation in extreme environments

    SciTech Connect (OSTI)

    Sandoval, R.P.; Weber, J.P.; Newton, G.J.

    1981-01-01

    Preliminary estimates of the health effects and/or consequences resulting from a malevolent attack on a spent fuel truck shipment in downtown New York City have been made. This estimate is based upon a measured quantity (0.78 +- 0.05 g) of respirable radioactive material released from a 1/4 scale event. A linear extrapolation from the 1/4 scale event to the generic full scale event has been made and an aerosolized release fraction (0.0023 percent) of the total heavy metal inventory of a three-PWR assembly truck cask has been calculated. Although scaling of the source term parameters is tentative at this point in the program, a full scale experiment is planned in 1981 to verify the scaling methodology used in these calculations. A preliminary correlation between spent fuel and surrogate fuel source terms has been shown to be feasible and that radionuclide size partitioning can be determined experimentally. Finally, it has been shown, based on our preliminary experimental source term data, that a maximum of 25 total latent cancer fatalities could occur, assuming a release in downtown New York City. This is 20 times smaller than the latent cancer fatalities predicted in the Urban Study.

  9. Environment/Health/Safety (EHS): Radiation Protection Group

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

    facility BELLA facility BELLA facility BELLA NDCX NDCX Gretina Gamma particle device PET Scanner APEX APEX APEX LASER LASER Rifle, CO Rifle, CO The group: Authorizes work with...

  10. Office of Environment, Safety and Health Evaluations Appraisal...

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

    July 2009 ii guidance, insights gained from Independent Oversight activities, and feedback from customers and constituents. Therefore, users of this process guide, as well as...

  11. Assistant Secretary for Environment, Safety and Health Endorses VPP and

    Office of Environmental Management (EM)

    Ft Peck Assiniboine & Sioux Tribes Ft Peck Assiniboine & Sioux Tribes Poplar, Montana Poplar, Montana DOE Grant Projects Status Report: DOE Grant Projects Status Report: 1. Wind Development Project 1. Wind Development Project 2. Energy Options Analysis 2. Energy Options Analysis Tracey LeBeau & Jim Williamson Tracey LeBeau & Jim Williamson October 2006 October 2006 2 Wind Project Wind Project * * Two 50KW wind turbines erected July 2006 Two 50KW wind turbines erected July 2006

  12. Environment, Safety, and Health Program for Department of Energy Operations

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

    1990-03-27

    This Page Change transmits revised page of DOE O 5480.1B to update the "sunset" clause of paragraph 8c(20)(c).

  13. Environment, Safety, and Health Program for Department of Energy Operations

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

    1989-07-20

    This Page Change transmits revised page 1 (and 2) of Attachment 1 to DOE O 5480.1B to reinstate the environmental protection provision to the subject Order which was deleted with the issuance of DOE O 5480.11. Canceled by DOE N 251.4.

  14. Environment, Safety, and Health Program for Department of Energy Operations

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

    1988-02-18

    This Page Change transmits revised pages of DOE O 5480.1B to update the "sunset" clause of paragraph 8c(20)(c).

  15. Environment, Safety, and Health Program for Department of Energy Operations

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

    1989-01-23

    This Page Change transmits revised pages of DOE O 5480.1B to update the "sunset" clause of paragraph 8c(20)(c).

  16. ALS beamline design requirements: A guide for beamline designers

    SciTech Connect (OSTI)

    1996-06-01

    This manual is written as a guide for researchers in designing beamlines and endstations acceptable for use at the ALS. It contains guidelines and policies related to personnel safety and equipment and vacuum protection. All equipment and procedures must ultimately satisfy the safety requirements set aside in the Lawrence Berkeley National Laboratory (LBNL) Health and Safety Manual (PUB-3000) which is available from the ALS User Office or on the World WideWeb from the LBNL Homepage (http:// www.lbl.gov).

  17. Risk Informed Safety Margin Characterization (RISMC) Advanced Test Reactor Demonstration Case Study

    Broader source: Energy.gov [DOE]

    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...

  18. Independent Activity Report, Defense Nuclear Facilities Safety Board Public Meeting- October 2012

    Broader source: Energy.gov [DOE]

    Defense Nuclear Facilities Safety Board Public Meeting on the Status of Integration of Safety Into the Design of the Uranium Processing Facility [HIAR-Y-12-2012-10-02

  19. Foundational development of an advanced nuclear reactor integrated safety code.

    SciTech Connect (OSTI)

    Clarno, Kevin; Lorber, Alfred Abraham; Pryor, Richard J.; Spotz, William F.; Schmidt, Rodney Cannon; Belcourt, Kenneth; Hooper, Russell Warren; Humphries, Larry LaRon

    2010-02-01

    This report describes the activities and results of a Sandia LDRD project whose objective was to develop and demonstrate foundational aspects of a next-generation nuclear reactor safety code that leverages advanced computational technology. The project scope was directed towards the systems-level modeling and simulation of an advanced, sodium cooled fast reactor, but the approach developed has a more general applicability. The major accomplishments of the LDRD are centered around the following two activities. (1) The development and testing of LIME, a Lightweight Integrating Multi-physics Environment for coupling codes that is designed to enable both 'legacy' and 'new' physics codes to be combined and strongly coupled using advanced nonlinear solution methods. (2) The development and initial demonstration of BRISC, a prototype next-generation nuclear reactor integrated safety code. BRISC leverages LIME to tightly couple the physics models in several different codes (written in a variety of languages) into one integrated package for simulating accident scenarios in a liquid sodium cooled 'burner' nuclear reactor. Other activities and accomplishments of the LDRD include (a) further development, application and demonstration of the 'non-linear elimination' strategy to enable physics codes that do not provide residuals to be incorporated into LIME, (b) significant extensions of the RIO CFD code capabilities, (c) complex 3D solid modeling and meshing of major fast reactor components and regions, and (d) an approach for multi-physics coupling across non-conformal mesh interfaces.

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

    SciTech Connect (OSTI)

    Curtis Smith; Diego Mandelli

    2013-03-01

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

  1. Safety System Oversight Annual Award | Department of Energy

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

    Safety System Oversight Annual Award Safety System Oversight Annual Award The Safety System Oversight (SSO) Annual Award is a special award designed to recognize superior or exemplary service by an employee who has performed SSO functions. This special award program has been established in accordance with the requirements of Department of Energy (DOE) Order 331.1C, Employee Performance Management and Recognition Program. PDF icon SSO_Annual_Award_guidance_15_04_06.pdf Responsible Contacts

  2. Beyond Design Basis Event Pilot Evaluations

    Broader source: Energy.gov [DOE]

    This document provides Results and Recommendations for Improvements to Enhance Nuclear Safety at Department of Energy Nuclear Facilities based upon Beyond Design Basis Event Pilot Evaluations

  3. Complete Experiment Safety Documentation

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

    Complete Experiment Safety Documentation Print User Safety Overview Upon receiving beam time: 1. Log in to ALSHub to complete an Experiment Safety Sheet (ESS). The ALS This e-mail address is being protected from spambots. You need JavaScript enabled to view it is available to support you through this process. Please contact This e-mail address is being protected from spambots. You need JavaScript enabled to view it at the email link or at (510) 486-7222 at if you have questions or need more

  4. Complete Experiment Safety Documentation

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

    Complete Experiment Safety Documentation Print User Safety Overview Upon receiving beam time: 1. Log in to ALSHub to complete an Experiment Safety Sheet (ESS). The ALS This e-mail address is being protected from spambots. You need JavaScript enabled to view it is available to support you through this process. Please contact This e-mail address is being protected from spambots. You need JavaScript enabled to view it at the email link or at (510) 486-7222 at if you have questions or need more

  5. Complete Experiment Safety Documentation

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

    Complete Experiment Safety Documentation Print User Safety Overview Upon receiving beam time: 1. Log in to ALSHub to complete an Experiment Safety Sheet (ESS). The ALS This e-mail address is being protected from spambots. You need JavaScript enabled to view it is available to support you through this process. Please contact This e-mail address is being protected from spambots. You need JavaScript enabled to view it at the email link or at (510) 486-7222 at if you have questions or need more

  6. Complete Experiment Safety Documentation

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

    Complete Experiment Safety Documentation Print User Safety Overview Upon receiving beam time: 1. Log in to ALSHub to complete an Experiment Safety Sheet (ESS). The ALS This e-mail address is being protected from spambots. You need JavaScript enabled to view it is available to support you through this process. Please contact This e-mail address is being protected from spambots. You need JavaScript enabled to view it at the email link or at (510) 486-7222 at if you have questions or need more

  7. Safety shutdown separators

    DOE Patents [OSTI]

    Carlson, Steven Allen; Anakor, Ifenna Kingsley; Farrell, Greg Robert

    2015-06-30

    The present invention pertains to electrochemical cells which comprise (a) an anode; (b) a cathode; (c) a solid porous separator, such as a polyolefin, xerogel, or inorganic oxide separator; and (d) a nonaqueous electrolyte, wherein the separator comprises a porous membrane having a microporous coating comprising polymer particles which have not coalesced to form a continuous film. This microporous coating on the separator acts as a safety shutdown layer that rapidly increases the internal resistivity and shuts the cell down upon heating to an elevated temperature, such as 110.degree. C. Also provided are methods for increasing the safety of an electrochemical cell by utilizing such separators with a safety shutdown layer.

  8. Categorical Exclusion Determinations: Health, Safety, and Security...

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

    Health, Safety, and Security Categorical Exclusion Determinations: Health, Safety, and Security Categorical Exclusion Determinations issued by Health, Safety, and Security. ...

  9. Department of Energy Nuclear Safety Policy

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

    2011-02-08

    It is the policy of the Department of Energy to design, construct, operate, and decommission its nuclear facilities in a manner that ensures adequate protection of workers, the public, and the environment. Supersedes SEN-35-91.

  10. Fusion safety program Annual report, Fiscal year 1995

    SciTech Connect (OSTI)

    Longhurst, G.R.; Cadwallader, L.C.; Carmack, W.J.

    1995-12-01

    This report summarizes the major activities of the Fusion Safety Program in FY-95. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory, and Lockheed Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL, at other DOE laboratories, and at other institutions. Among the technical areas covered in this report are tritium safety, beryllium safety, chemical reactions and activation product release, safety aspects of fusion magnet systems, plasma disruptions, risk assessment failure rate database development, and safety code development and application to fusion safety issues. Most of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER). Also included in the report are summaries of the safety and environmental studies performed by the Fusion Safety Program for the Tokamak Physics Experiment and the Tokamak Fusion Test Reactor and the technical support for commercial fusion facility conceptual design studies. A final activity described is work to develop DOE Technical Standards for Safety of Fusion Test Facilities.

  11. RADIATION PROTECTION OF THE PUBLIC AND THE ENVIRONMENT

    National Nuclear Security Administration (NNSA)

    AND THE ENVIRONMENT U.S. DEPARTMENT OF ENERGY Office of Health, Safety and Security DOE ... under the control of the Department of Energy (DOE) pursuant to the Atomic Energy Act ...

  12. An Overview of the Safety Case for Small Modular Reactors

    SciTech Connect (OSTI)

    Ingersoll, Daniel T

    2011-01-01

    Several small modular reactor (SMR) designs emerged in the late 1970s and early 1980s in response to lessons learned from the many technical and operational challenges of the large Generation II light-water reactors. After the accident at the Three Mile Island plant in 1979, an ensuing reactor redesign effort spawned the term inherently safe designs, which later evolved into passively safe terminology. Several new designs were engineered to be deliberately small in order to fully exploit the benefits of passive safety. Today, new SMR designs are emerging with a similar philosophy of offering highly robust and resilient designs with increased safety margins. Additionally, because these contemporary designs are being developed subsequent to the September 11, 2001, terrorist attack, they incorporate a number of intrinsic design features to further strengthen their safety and security. Several SMR designs are being developed in the United States spanning the full spectrum of reactor technologies, including water-, gas-, and liquid-metal-cooled ones. Despite a number of design differences, most of these designs share a common set of design principles to enhance plant safety and robustness, such as eliminating plant design vulnerabilities where possible, reducing accident probabilities, and mitigating accident consequences. An important consequence of the added resilience provided by these design approaches is that the individual reactor units and the entire plant should be able to survive a broader range of extreme conditions. This will enable them to not only ensure the safety of the general public but also help protect the investment of the owner and continued availability of the power-generating asset. Examples of typical SMR design features and their implications for improved plant safety are given for specific SMR designs being developed in the United States.

  13. Integrated Safety Management Policy - DOE Directives, Delegations...

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

    P 450.4A, Integrated Safety Management Policy by David Weitzman Functional areas: Integrated Safety Management, Safety The policy establishes DOE's expectation for safety,...

  14. Safety Management System Policy | Department of Energy

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

    Program Management Safety Safety Management System Policy Safety Management System Policy Safety Management Systems provide a formal, organized process whereby people plan, ...

  15. Office of Nuclear Facility Safety Programs

    Broader source: Energy.gov [DOE]

    The Office of Nuclear Facility Safety Programs establishes nuclear safety requirements related to safety management programs that are essential to the safety of DOE nuclear facilities.

  16. Office of Nuclear Safety | Department of Energy

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

    Nuclear Safety Office of Nuclear Safety Mission The Office of Nuclear Safety establishes nuclear safety requirements and expectations for the Department to ensure protection of ...

  17. Strategic Safety Goals | Department of Energy

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

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

  18. Safety Culture in Nuclear Installations

    Broader source: Energy.gov [DOE]

    IAEA-TECDOC-1329 Safety Culture in Nuclear Installations, Guidance for use in the Enhancement of Safety Culture, International Atomic Energy Agency IAEA, December 2002.

  19. Environmental, safety, and health engineering

    SciTech Connect (OSTI)

    Woodside, G.; Kocurek, D.

    1997-12-31

    A complete guide to environmental, safety, and health engineering, including an overview of EPA and OSHA regulations; principles of environmental engineering, including pollution prevention, waste and wastewater treatment and disposal, environmental statistics, air emissions and abatement engineering, and hazardous waste storage and containment; principles of safety engineering, including safety management, equipment safety, fire and life safety, process and system safety, confined space safety, and construction safety; and principles of industrial hygiene/occupational health engineering including chemical hazard assessment, personal protective equipment, industrial ventilation, ionizing and nonionizing radiation, noise, and ergonomics.

  20. Safety & Training | Advanced Photon Source

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

    Safety & Training The UES Group provides facility ESH oversight for all user experiment safety and day-to-day beamline activities. The UES Floor Coordinators are deployed around...

  1. Defense Nuclear Facility Safety Board

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

    8, 2014 Defense Nuclear Facility Safety Board Defense Nuclear Facility Safety Board (DNSFB) Vice Chairwoman Jesse Roberson visited and toured the WIPP site this week. While...

  2. Software for the occupational health and safety integrated management system

    SciTech Connect (OSTI)

    Vătăsescu, Mihaela

    2015-03-10

    This paper intends to present the design and the production of a software for the Occupational Health and Safety Integrated Management System with the view to a rapid drawing up of the system documents in the field of occupational health and safety.

  3. Radiation Safety Test

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

    Safety Test. This form can also be picked up and filled out in the CAMD front office, rm. 107 A minimum passing score is 80% (24 out of 30) After completing the test, you will ...

  4. Nuclear Explosive Safety

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

    2014-07-10

    The Order establishes requirements to implement the nuclear explosive safety (NES) elements of DOE O 452.1E, Nuclear Explosive and Weapon Surety Program, for routine and planned nuclear explosive operations (NEOs).

  5. Nuclear Explosive Safety

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

    2006-06-12

    The directive provides supplemental details to support the requirements of DOE O 452.2C, Nuclear Explosive Safety, dated 6-12-06. Canceled by DOE M 452.2-1A.

  6. Reliability and Safety

    Office of Energy Efficiency and Renewable Energy (EERE)

    DOE solar reliability and safety research and development (R&D) focuses on testing photovoltaic (PV) modules, inverters, and systems for long-term performance, and helping investors, consumers,...

  7. Promulgating Nuclear Safety Requirements

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

    1996-05-15

    Applies to all Nuclear Safety Requirements Adopted by the Department to Govern the Conduct of its Nuclear Activities. Cancels DOE P 410.1. Canceled by DOE N 251.85.

  8. Packaging and Transportation Safety

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

    2010-05-14

    The order establishes safety requirements for the proper packaging and transportation of DOE, including NNSA, offsite shipments and onsite transfers of radioactive and other hazardous materials and for modal transportation. Supersedes DOE O 460.1B.

  9. Packaging and Transportation Safety

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

    1995-09-27

    Establishes safety requirements for the proper packaging and transportation of offsite shipments and onsite transfers of hazardous materials andor modal transport. Cancels DOE 1540.2 and DOE 5480.3

  10. Packaging and Transportation Safety

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

    1995-09-27

    Establishes safety requirements for the proper packaging and transportation of Department of Energy (DOE) offsite shipments and onsite transfers of hazardous materials and for modal transport. Canceled by DOE 460.1A

  11. Packaging and Transportation Safety

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

    1996-10-02

    Establishes safety requirements for the proper packaging and transportation of Department of Energy (DOE) offsite shipments and onsite transfers of hazardous materials and for modal transport. Cancels DOE O 460.1.

  12. Documented Safety Analysis for the B695 Segment

    SciTech Connect (OSTI)

    Laycak, D

    2008-09-11

    This Documented Safety Analysis (DSA) was prepared for the Lawrence Livermore National Laboratory (LLNL) Building 695 (B695) Segment of the Decontamination and Waste Treatment Facility (DWTF). The report provides comprehensive information on design and operations, including safety programs and safety structures, systems and components to address the potential process-related hazards, natural phenomena, and external hazards that can affect the public, facility workers, and the environment. Consideration is given to all modes of operation, including the potential for both equipment failure and human error. The facilities known collectively as the DWTF are used by LLNL's Radioactive and Hazardous Waste Management (RHWM) Division to store and treat regulated wastes generated at LLNL. RHWM generally processes low-level radioactive waste with no, or extremely low, concentrations of transuranics (e.g., much less than 100 nCi/g). Wastes processed often contain only depleted uranium and beta- and gamma-emitting nuclides, e.g., {sup 90}Sr, {sup 137}Cs, or {sup 3}H. The mission of the B695 Segment centers on container storage, lab-packing, repacking, overpacking, bulking, sampling, waste transfer, and waste treatment. The B695 Segment is used for storage of radioactive waste (including transuranic and low-level), hazardous, nonhazardous, mixed, and other waste. Storage of hazardous and mixed waste in B695 Segment facilities is in compliance with the Resource Conservation and Recovery Act (RCRA). LLNL is operated by the Lawrence Livermore National Security, LLC, for the Department of Energy (DOE). The B695 Segment is operated by the RHWM Division of LLNL. Many operations in the B695 Segment are performed under a Resource Conservation and Recovery Act (RCRA) operation plan, similar to commercial treatment operations with best demonstrated available technologies. The buildings of the B695 Segment were designed and built considering such operations, using proven building systems, and keeping them as simple as possible while complying with industry standards and institutional requirements. No operations to be performed in the B695 Segment or building system are considered to be complex. No anticipated future change in the facility mission is expected to impact the extent of safety analysis documented in this DSA.

  13. Nuclear Energy Safety Technologies

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

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

  14. SSRL Safety Office Memo

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

    Safety Office SSO 01/24/06 Memo to SSRL staff concerning operation of Circuit Breakers and Disconnect Switches Recently SLAC has adopted new regulations (NFPA70E) which outline the "Standard for Electrical Safety in the Workplace". Specifically it requires that the Arc Flash Hazard be categorized and PPE stated for all circuit breakers and disconnect switches. This memo identifies requirement for operating circuit breakers or disconnect switches at SSRL. SSRL staff members shall be

  15. Risk and Safety Assessment

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

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

  16. Safety system status monitoring

    SciTech Connect (OSTI)

    Lewis, J.R.; Morgenstern, M.H.; Rideout, T.H.; Cowley, P.J.

    1984-03-01

    The Pacific Northwest Laboratory has studied the safety aspects of monitoring the preoperational status of safety systems in nuclear power plants. The goals of the study were to assess for the NRC the effectiveness of current monitoring systems and procedures, to develop near-term guidelines for reducing human errors associated with monitoring safety system status, and to recommend a regulatory position on this issue. A review of safety system status monitoring practices indicated that current systems and procedures do not adequately aid control room operators in monitoring safety system status. This is true even of some systems and procedures installed to meet existing regulatory guidelines (Regulatory Guide 1.47). In consequence, this report suggests acceptance criteria for meeting the functional requirements of an adequate system for monitoring safety system status. Also suggested are near-term guidelines that could reduce the likelihood of human errors in specific, high-priority status monitoring tasks. It is recommended that (1) Regulatory Guide 1.47 be revised to address these acceptance criteria, and (2) the revised Regulatory Guide 1.47 be applied to all plants, including those built since the issuance of the original Regulatory Guide.

  17. CANISTER HANDLING FACILITY CRITICALITY SAFETY CALCULATIONS

    SciTech Connect (OSTI)

    C.E. Sanders

    2005-04-07

    This design calculation revises and updates the previous criticality evaluation for the canister handling, transfer and staging operations to be performed in the Canister Handling Facility (CHF) documented in BSC [Bechtel SAIC Company] 2004 [DIRS 167614]. The purpose of the calculation is to demonstrate that the handling operations of canisters performed in the CHF meet the nuclear criticality safety design criteria specified in the ''Project Design Criteria (PDC) Document'' (BSC 2004 [DIRS 171599], Section 4.9.2.2), the nuclear facility safety requirement in ''Project Requirements Document'' (Canori and Leitner 2003 [DIRS 166275], p. 4-206), the functional/operational nuclear safety requirement in the ''Project Functional and Operational Requirements'' document (Curry 2004 [DIRS 170557], p. 75), and the functional nuclear criticality safety requirements described in the ''Canister Handling Facility Description Document'' (BSC 2004 [DIRS 168992], Sections 3.1.1.3.4.13 and 3.2.3). Specific scope of work contained in this activity consists of updating the Category 1 and 2 event sequence evaluations as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2004 [DIRS 167268], Section 7). The CHF is limited in throughput capacity to handling sealed U.S. Department of Energy (DOE) spent nuclear fuel (SNF) and high-level radioactive waste (HLW) canisters, defense high-level radioactive waste (DHLW), naval canisters, multicanister overpacks (MCOs), vertical dual-purpose canisters (DPCs), and multipurpose canisters (MPCs) (if and when they become available) (BSC 2004 [DIRS 168992], p. 1-1). It should be noted that the design and safety analyses of the naval canisters are the responsibility of the U.S. Department of the Navy (Naval Nuclear Propulsion Program) and will not be included in this document. In addition, this calculation is valid for the current design of the CHF and may not reflect the ongoing design evolution of the facility. However, it is anticipated that design changes to the facility layout will have little or no impact on the criticality results and/or conclusions presented in this document. This calculation is subject to the ''Quality Assurance Requirements and Description'' (DOE 2004 [DIRS 171539]) because the CHF is included in the Q-List (BSC 2005 [DIRS 171190], p. A-3) as an item important to safety. This calculation is prepared in accordance with AP-3.12Q, ''Design Calculations and Analyses'' [DIRS 168413].

  18. Transient Safety Analysis of Fast Spectrum TRU Burning LWRs with...

    Office of Scientific and Technical Information (OSTI)

    The objective of this proposal was to perform a detailed transient safety analysis of the Resource-Renewable BWR (RBWR) core designs using the U.S. NRC TRACEPARCS code system. ...

  19. Spent nuclear fuel project path forward preliminary safety evaluation

    SciTech Connect (OSTI)

    Brehm, J.R.; Crowe, R.D.; Siemer, J.M.; Wojdac, L.F.; Hosler, A.G.

    1995-03-01

    This preliminary safety evaluation (PSE) provides validation of the initial project design criteria for the Spent Nuclear Fuel Project (SNFP) Path Forward for removal of fuel from K Basins.

  20. System 80+{trademark} Standard Design: CESSAR design certification. Volume 6: Amendment I

    SciTech Connect (OSTI)

    Not Available

    1990-12-21

    This report, entitled Combustion Engineering Standard Safety Analysis Report - Design Certification (CESSAR-DC), has been prepared in support of the industry effort to standardize nuclear plant designs. These documents describe the Combustion Engineering, Inc. System 80+{sup TM} Standard Design. This report, Volume 6, in conjunction with Volume 7, provides a description of engineered safety features.